ML082950389
| ML082950389 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/01/2008 |
| From: | Ginna |
| To: | Fish T H Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML080030004 | List: |
| References | |
| 50-244/08-301, TAC U01687 | |
| Download: ML082950389 (202) | |
Text
2008 Giiina NRC Exam RO Ouestion 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.
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. 1.7%RTP 2. The ARVs auto setpoint must be raised. c. 1. 3.5 % RTP 2. The ARVs auto setpoint must be raiseid. d. 1.7%RTP 2. The ARVs auto setpoint must be lowered.
Answer: Incorrect Correct Incorrect Incorrect 2008 Girina NRC Exam a. 1. This is the 1 minute expected value per Reactor Theory, Chapter 2, Nuclear 2. If S/G pressure is lowered this will also lower Tavg due to Tcold going down 1. This is the expected value per Reactor Theory, Chapter 2, Nuclear 2. As decay heat lowers over time Thot lowers. To keep Tavg at 547"F, S/G 1. This is the 1 minute expeci:ed value per Reactor Theory, Chapter 2, Nuclear 2. As decay heat lowers over time Thot lowers. To keep Tavg at 547"F, S/G 1. This is the expected value per Reactor Theory, Chapter 2, Nuclear 2. If S/G pressure is lowered this will also lower Tavg due to Tcold going down Physics, pages 107-109. due to ARV operations and Thot lowering due to decay heat lowering. Physics, pages 107-109.
pressure must go up. Physics, pages 107-109. pressure must go up. Physics, pages 107-109. due to ARV operations and Thot lowering due to decay heat lowering.
Explanation:
Exanainatb:
RO 2008 Ginna NRC 1 #I 1 I Rev. 2 I Level: RO Lt?t?smfin:
RRT02C I Nuclear Physics 3.03 I Define decav heat Reactor Theory, Chapter 2, Nuclear Physics, pages 107- EK1.04 - Knowledge of the operational implications of the following IJsed on Audit Exam - No rnm, 2008 Ginna NRC Exam Question 2 Plant conditions are as follows: 0 0 Subcooling margin is lowering.
The unit was at 90% power when a Ihss of Coolant Accident and a Loss of Off-Site Power occurred.
Manual Safety Injection (SI) and Containment Isolation (CI) were performed.
All systems performed as designed.
RCS pressure is 1510 psig and slowly lowering. Pressurizer level is 15 % and rising rapidly.
Which of the following is the cause for a these indications?
- a. SI accumulator Injection.
- b. Pressurizer vapor space leak.
- c. SI pumps refilling the Pressurizer.
RO d. Leak in the Pressurizer variable leg.
2008 Ginna NRC Exam Incorrect Correct Incorrect RO a. b. RCS pressure is above SI accumulator pressure of -750#. May choose this due to Pzr level raising. These are the classic indications of a vapor space break. Due to the high Rx head temperature and the LOOP (no RCP running and no MEW 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
- c. Answer: Incorrect i b. Pressurizer vapor space leak. due to Pzr level raising.
A leak in the Pressurizer variable leg will make the d/p go up which would indicate a lower Pressurizer level. d. Explanation:
I I I mce in expected indication for a PRZR vapor 2008 Giiina NRC Exam RO Ouestion 3 Plant conditions are as follows: 0 0 0 The unit has experienced a large break LOCA and a loss of offsite power.
Neither Diesel Generator (DIG) started automatically. Following a manual start of 1A D/G and manually loading of Bus 14 and 18 per Attachment 8.5, the HCO observed the following:
o 1A EDG load 2000 kw Which ONE of the following is the LONGES'C 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. e. (.5) hours, D/G loading will remain the
- same. d. (2) hours, D/G loading will lower.
2008 Ginna NRC Exam Incorrect Incorrect Incorrect Correct Answer: a. 1. D/G KW Ratings are: 1950 KW continuous, 2250 KW for two (2) hours, 2300 KW for one-half (.5) 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 D/G will lower by itself. This is a known and expected condition.
- 1. D/G KW Ratings are: 1950 KW continuous, 2250 KW for two (2) hours, 2300 KW for one-half (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. 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. 1. D/G KW Ratings are: 1950 KW continuous, 2250 KW for two (2) hours, 2300 KW for one-half (.5) hours. The time limit is 2 hrs. not .5 hrs. 2. FSAR section 8 tables 8.3.2.a and b show D/G loading lowering over time due to lower loading on the CglCFs. 1. EDG KW Ratings are: 1950 KW continuous, 2250 KW for two (2) hours, 2300 KW for one-half (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. 2. Due to the removal of heathteam from Cnmt by the CRCFs and CS the load on the D/G will lower by iiself. This is a known and expected condition.
- b. c. d. RO d. (2) hours, D/G loading will slowly lower.
Explanation:
FSAR section 8 tables 2008 Giiina NRC Exam RO Question 4 Plant conditions are as follows: 0 The unit has experienced a Loss of Coolant Accident (LOCA). 0 RCS pressure is 1400 psig and trending down rapidly.
0 Containment pressure is 8 psig and trending up.
0 "A" and "C" SI pumps are running. 1. 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 psig. 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 psig. 2. Mass loss is less if RCPs are turned off, resulting in greater assurance of natural circulation.
- c. 1. When RCS pressure minus maximurn S/G pressure is 200 psig. 2. Mass loss is greater if RCPs are left ~mnning, resulting in possible deeper core uncovery.
- d. 1. When RCS pressure minus maximum S/G pressure is 230 psig. 2. Mass loss is greater if RCPs are left iunning, resulting in possible deeper core uncovery.
I 2008 Giiina NRC Exam Incorrect Incorrect Incorrect Correct RO a. Due to adverse conditions RCPs should be secured when the d/p is less than 240 psig 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. Correct given d/p to secure the RCPs. Securing of RCPs at this specific time has no bearing on assuring natural circulation. Due to adverse conditions RCPs should be secured when the d/p is less than 240 b. c. d. Answer: d. 1. When RCS pressure minus maximum SJG pressure is 230 psig.
- 2. Mass loss is greater if RCPs are left running, resulting in possible deeper core uncovery.
Explanation:
psig so 230 psig is the first correct pressure of the given options. Prior to cold leg saturation water is being removed from break and no difference in mass loss for RCP running or not. After cold leg saturation phase separation 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 psig (240 psig adverse containment). Adverse containment conditions are in effect due to Cnmt pressure > 4 psig.
2008 Giinna NRC Exam RO Question 5 Plant conditions are as follows: 0 0 0 The unit is at 50% power. A leak develops that completely drains the reference side of VCT level transmitter LT-112. Assume the leak affects only the VCT level transmitter LT-112. With NO operator intervention, how will the plant respond?
Actual VCT will trend . . . a. b. c. d. up until 83%, because of continuous au1:omatic makeup. down to 20% and then trend up due to automatic makeup. down until the VCT is empty and all running charging pumps lose suction. down to 5% at which time the Charging Pumps will take a suction from the RWST.
2008 Giinna NRC Exam Answer: Incorrect
- c. down until the VCT is empty and all running charging pumps lose suction. will cause the control system to think there is a low level in the VCT. LT-112 indication at 20% starts the makeup but since it has failed high there will b. Explanation:
Correct Incorrect RO - be no auto makeup.
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 110 auto makeup. The logic is 2 out of 2, both ILT-112 and LT-139 must both see VCT level at 5% to shift. LT-112 is failed high, logic will not be met. c. d. I Incorrect I a. I If it is assumed that the leak on the reference side of the VCT level transmitter I - , ,. fhe@t&R& 1 5 I Rev. 3 I Level: RO I id Volume Control System s) of a loss or malfunction of the following
/or instrumentation on the Chemical and Volume 1 CJA Rx Coolant Makeup 6) LT-112 Bank 3 - 3 2008 Ginna NRC Exam RO Question 6 Plant conditions are as follows: 0 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 been stopped due to cavitation to the RHR pumps. 1. What is correct concerning the RCS and the loss of RHR? 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 longer.
- 2. Charging to loop B cold leg.
2008 Ginna NRC Exam Correct Incorrect Incorrect Incorrect Answer: a. 1. When less than 64" the RCS is in a reduced inventory condition and due to 2. RWST gravity feed is the preferred method to raise RCS loop level per step 1. When less than 64" the RCS is in a reduced inventory condition and due to 2. Charging to loop B cold kg is the second preferred method to raise RCS loop 1. When greater than 64" the RCS is not in a reduced inventory condition, times
- 2. RWST gravity feed is the preferred method to raise RCS loop level per step 1. When greater than 64" the RCS is not in a reduced inventory condition, times 2. Charging to loop B cold leg is the second preferred method to raise RCS loop boil off core uncovery will occur. 10 of AP-RHR.2.
- b. boil off core uncovery will occur. level per step 11 of AP-RHR.2. to boiling and core uncovery would be significantly longer.
- c. 10 of AP-RHR.2.
- d. to boiling and core uncovery would be significantly longer. level per step 11 of AP-RHR.2.
RO a. 1. The RCS is 2. RWST gravity feed. a reduced inventory condition, core uncovery occur in a short period of time. Explanation:
2008 Ginna NRC Exam RO Ouestion 7 Plant conditions are as follows: e 0 The unit has been at 100% power for the last year. All systems are in their normal at power alignment.
Due to a malfunction, Pressurizer Pressure Controller - 43 1K output begins and continues to slowly rise.
If NO operator action is taken, what will the p:lant response be? Spray valves initially . . a. close, heaters will energize, one PORV will eventually lift. b. close, heaters will energize, two PORV!; will eventually lift.
- c. open, Reactor will trip, RCS pressure will eventually stabilize at approximately 1500 psig. d. open, Reactor will trip, RCS pressure w:ill eventually stabilize at approximately normal operating pressure.
2008 Giiina NRC Exam Answer: c. open, Reactor will trip, RCS pressure wi I1 eventually stabilize at approximately 1500 psig. RO Explanation:
Incorrect Incorrect Correct Incorrect
- a. - b. - C. - d. - 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 the 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).
If the output for controller 43 1 K rises this will result in the Spray valves opening. The heaters would only energize if the output for 43 1 K lowers. If it is not known or forgotten that the output from 431K goes to PORV-431C, then the operation of (2) PORVs is plausible.
A sensed low pressure demand would 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. Correct operation of the Spray valves however, pressure will not return to normal due to the trip and the continued Pzr spray and subsequent cooldown.
2008 Ginna NRC Exam Question 8 E-3, Steam Generator Tube Rupture, Step 5 requires that feed to a ruptured steam generator be continued until narrow range level is above a minimum level.
What is the bases for maintaining a minimum level in a ruptured steam generator?
- a. To maximize back pressure and minimze 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.
RO d. To promote thermal stratification in the ruptured SG during the subsequent RCS cooldown and depressurization.
2008 Ginna NRC Exam Answer: d. To promote thermal stratification in the ruptured SG during the subsequent RCS cooldown and depressurization.
Explanation:
Incorrect Incorrect Incorrect Correct a. b. - C. - d. - RO 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.
If chosen to recover via Blowdowns this would seem to be a plausible bases but is not the reason for the 7% level requirement per the Background document.
Failure of additional steam generator U-tubes would not be wanted during a SGTR and any action that pr,evented this from occurring maybe the correct thing to do, but is not the bases for the step in the background document.
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 primary-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.
I 2008 Ginna NRC Exam Ouestion 9 Plant conditions are as follows:
RO A Reactor startup is in progress following a five week Refueling Outage.
MTC is predicted to be zero at 15% Reactor Power.
The reactor is critical.
N 35 - 1x10 -8 amps and stable N 36 - 1x10 -8 amps and stable Plant startup is on hold to complete required testing. A steam line break occurs.
5% of rated steam flow is leaking out.
Which one of the following describes the response of the reactor, assuming no reactor trip occurs? Tavg will trend. . . a. up. The reactor will go to 5% power. b. down. The reactor will go subcritical.
- e. down. The reactor will go to 5% power. d. up. The reactor will go subcritical.
2008 Ginna NRC Exam Incorrect Correct Incorrect Incorrect Answer: 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. Plausible if assumes a (-MTC) and not certain of plant response.
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)] 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. Plausible if is forgotten the Rx is at BOL, and has a (+ MTC). If it is assumed the Rx is at MOL or EOL with a (-MTC>l this answer would be correct. 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. Plausible if assumes the wrong Tavg response and a (-MTC). b. c. d. b. down. The reactor will go subcritical.
Exdanation
- RO I 2008 Ginna NRC Exam Question 10 Plant conditions are as follows: 0 0 0 0 The unit is operating at 14% power. The turbine is rolling up to 1800 rpm. "A" Condensate Pumps is 00s. "B" and "C" Condensate Pumps have just tripped. Which one of the following combinations will occur if no operator action is taken?
MFPs TRIP: a. Immediately
- b. Immediately
- c. After 60 seconds d. After 60 seconds REACTOR TRIPS on; TURBINE TRIPS on: Lo-Lo S/G Level Reactor Trip Turbine Trip MFW pump Trip Turbine Trip MFW pump Trip Lo-Lo S/G Level Reactor Trip RO 2008 Ginna NRC Exam Answer: Incorrect Incorrect Incorrect Correct RO a. b. MFPs trip when <15 psi seal water pressure above Feedwater pump suction pressure (60 second time delay). MFPs trip when <15 psi seal water pressure above Feedwater pump suction pressure (60 second time delay).
MFP trips only cause a Turbine trip when one of the Generator output breakers (1G or 9X) is closed. Turbine trip less than 50% will not cause the Rx to trip. MFP trips only cause a Turbine trip when one of the Generator output breakers (1G or 9X) is closed. MFPs trip when <15 psi seal water pressure above Feedwater pump suction pressure (60 second time delay). With no feed to the S/Gs, the levels will drop and at 17% in 2/3 S/Gs a Rx Trip is generated which in turn generates a Turbine Trip. c. d. d. After 60 seconds Lo-Lo S/G Level Reactor Trip Explanation:
And Feedwater Systems that a loss or malfunction in the Condensate anc AR-H- 1 1, FEED PUMP SEAL WATER LO DIFF 2008 Ginna NRC Exam Question 11 Plant conditions occurred as follows: 1200 - The unit is operating at rated power and all systems in their normal alignment.
1205 - A small Loss of Coolant Accident (LOCA) occurs and the Letdown system is secured 1215 - A Station Blackout occurs (and no Diesel Generators will start). 1225 - Due to a fault, Instrument Bus A is deenergized.
1235 - Battery 1B is dead due to excessive loading.
1245 - An automatic SI actuates due to low Pressurizer pressure.
1250 - The HCO notices the Letdown Isolation Valve-427 is OPEN. per the procedure in an effort to slclw the downward trend of Pressurizer water level.
When did the Letdown Isolation Valve-427 OPEN? (Assume no operator actions have been performed.)
The Letdown Isolation Valve-427 went OPEN shortly after. . . a. 1215. b. 1225. c. 1235. d. 1245.
2008 Ginna NRC Exam Correct Incorrect Incorrect Incorrect RO a. b. c. d. Answer: a. 1215. AOV-427 was closed during the isolation of the Letdown system that was given in the stem, due to the loss cd the SNIA compressors on the station blackout AOV-427 went to its failed position-open. 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 lo,gic 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 PIS to AOV-427 and it fails open on a loss of power to the solenoid.
DC MCC 1B does power AOV-427 and its fail position on loss of DC power is open 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.
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. interlocks, and the related automatic action(s) for the following to a Station Blackout: Existing valve positioning on a loss of Volume Control System LP R4701C, Instrument and Service Air System Pg. 22 10905-0717 AOV-427 I 2008 Ginna NRC Exam RO Ouestion 12 Plant conditions are as follows: 0 The unit is at 50% power. 0 The Electric plant is in a Normal 50/50 lineup. 0 Annunciator L-5, Safeguard Bus Main Breaker Overcurrent Trip just alarmed. 1. What caused the alarm to come in? and 2. In accordance with Annunciator Response Procedure L-5, which one of the following correctly lists - ALL the required operator action(s) after the faulted component is identified and isolated from the bus to support restoring power to the affected bus?
- a. b. C. d. 1. Bus 18 time rate over 1500 amps. 2. Ensure the associated DIG supply breaker is in Pull stop. Depress the Overcurrent RESET pushbutton for the affected safeguards bus Normal Feed breaker. 1. Bus 17 time rate over 1500 amps. 2. Ensure associated 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. 1. Bus 14 time rate over 3000 amps. 2. Ensure associated DIG supply breaker is in Pull stop. Reset the affected Safeguards bus Normal Feed breaker. Depress the Overcurrerit RESET pushbutton for the affected Safeguards bus Normal Feed breaker. 1. Bus 16 time rate over 3000 amps. 2. Ensure the associated D/G supply bre'aker is in Pull stop. Depress the Overcurrent RESET pushbutton for the affected Safeguards bus Normal Feed breaker.
2008 Ginna NRC Exam Answer: Incorrect RO 2. Must also reset the affected Safeguards bus Normal Feed breaker. 1. Bus 17 time rate over 1600 amps is the correct rating, not 1500 amps. b. c. 1. Bus 14 time rate over 3000 amps. 2. Ensure associated 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.
Correct Explanation:
- 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
- c. I Incorrect I a. I 1. Bus 18 time rate over 1600 amps is the correct rating, not 1500 amps. 1 Incorrect Trip. 1. Bus 16 time rate over 3000 amps is correct. 2. Must also reset the affected Safeguards bus Normal Feed breaker.
- d. Electrical Distr m alarm setpoints and operate controls 2008 Ginna NRC Exam RO Question 13 The Control Room Team is restoring power to Instrument Bus "D" while implementing ECA-0.1, Loss of All AC Power Recovery Without SI Required.
1, Where can Instrument Bus "D" be powered from?
and 2. What is the basis for restoring power to Instrument Bus "D"? a. 1. MCC "A" or MCC "B". 2. Instrument Bus "D" powers some required CVCS instrumentation.
- 2. Instrument Bus "D' powers some required Pressurizer level instrumentation.
- d. 1. MCC "A" or MCC "D'. 2. Instrument Bus "D" powers some required Pressurizer level instrumentation.
I 2008 Ginna NRC Exam Correct Incorrect Incorrect Incorrect RO a. b. c. d. MCC A (Maint. supply) or IvICC B (Normal supply).
CVCS instrumentation per ECA-0.1 step 4 background document.
MCC "D' powers Instrument Bus "C". Instrument Bus "D' does not power any Pressurizer level instruments.
MCC "D" powers Instrument Bus "C" and Instrument Bus "D' does not power any Pressurizer level instruments.
Answer: a. 1. MCC "A" or MCC "B". 2. Instrument Bus "D" powers some required CVCS instrumentation.
Explanation:
nt and equipment conditions evaluate the procedure determine the appropriate EXPECTED ACTIONS or RESPONSE NOT OBTAINED instructions to implement. (ECA-Power Restoration pg. 11 Power Recovery Without SI ECA-0.1, LOSS of All AC 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 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 s ystemskomponents 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.
I 2008 Giinna NRC Exam Incorrect Incorrect Incorrect Correct RO a. b. c. d. Water Hammer is a concern but is not referenced in the background document.
Cooling to the Cnmt and ECCS systems is a concern but is not referenced in the background document. Thermal Shock is a concern but is not referenced in the background document. Required per ECA-0.0, step S and reason is per the Background document:
Defeating the large loads as automatic 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 Answer: d. To allow a Service Water Pump to automatically load on the AC emergency bus to provide Diesel Generator cooling should that asociated Diesel Generator start..
Explanation: service water pump is permitted to automatically load on the AC emergency bus to provide D/G cooling should the diesel have started. RESPONSE NOT OBTAINED instructions to implement in ECA- contained in EOP for Loss of nuclear st 2008 Ginna NRC Exam RO Question 15 Plant conditions occurred as follows:
a e e An unisolable Instrument Air header ntpture has occurred.
The unit was tripped and E-0, Reactor Trip or Safety Injection was entered. Following the Reactor Trip a Safety Valve on the "A" S/G opened and has failed to completely reclose. While executing E-0, the "A" S/G developed a tube rupture.
E-3, Steam Generator Tube Rupture, is now being performed.
"A" S/G pressure has fallen to 600 psig;. No operator controlled cooldown has been started.
All other systems have function as required. All appropriate actions have been performed. Which one of the following is the correct methd used to lower RCS pressure?
- a. PRZR PORV using normal supply.
- b. PRZR PORV using backup supply.
- c. Auxiliary Spray using Charging Pumps. d. Normal Sprays.
I Incorrect Correct 2008 Giiina NRC Exam Answer: a. b. Due to the IA rupture that can't be isolated the normal motive force (air) is not available.
Nitrogen is available and can be valved in and is correct per RNO step b. PRZR PORV using backup supply.
Incorrect Incorrect Explanation:
22a of E-3. Need IA to open AOV-296 which failed closed on the IA header rupture.
Need IA to open the spray valves which failed closed on the IA header rupture. c. d. RO LP R1401C' Pzr and PR.T 2008 Giiina NRC Exam RO Question 16 Plant conditions occurred as follows:
0 0 0 0 While at rated power, there was a disturbance on the electrical power grid which required the unit to perform a load reduction.
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 Curvc:, if current conditions continue which Megavar limit will be met FIRST and what type of load is the Generator carrying?
- a. 1. -159 Megavars 2. Inductive Load b. 1.325 Megavars 2. Inductive L,oad c. 1.325 Megavars 2. Capacitive Load d. 1. -1 59 Megavars 2. Capacitive Load GENERATOR CAPABILITY CURVE 13 0 KV 3 pharc'S.0 Hr liOC RPW 60 prig Hydrogan -52 Power Factor Rated Cold Gas 4E C 500 400 300 200 100 se 83 -3 DO -200 -303 -430 Megawatts 2008 Giinna NRC Exam Answer: Incorrect Incorrect
- d. 1. - 159 Megavars 2. Capacitive Load a. Wrong type of load. b. Wrong side of the curve and wrong type of load. ExDlanation:
Incorrect Correct RO c. d. Wrong side of the curve. With current leading voltage it is a Capacitive Load and the Megavar limit can Emamination:
1 RO2008GinnaNRC lQue$h #I I 16 I Rev. 3 I Level: RO 1 R5701C I Real and Reactive Load in AC Generators 000077 Generator Voltage and Electric Grid Disturbances 3.5 AA2.01 - Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: Operating point Used on Last (2) NRC Exams - No 1
$1 2008 Giiina 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.
Which ONE of the following actions will be attempted to isolate the break and which indication is used to determine if the leak has been isolated in accordance with ECA- 1.2? a. Isolate Charging piping then one SI Hot Leg pipe at a time; RCS pressure is monitored, because SI flow will repressurize the RCS with the break isolated.
- b. Isolate one SI Cold Leg pipe at a time then Charging piping; RCS pressure is monitored, because SI flow will repressurize the RCS with the break isolated.
- c. Isolate one SI Cold Leg pipe at a time then Charging piping; Pressurizer level is monitored, because with the break isolated, RCS inventory will rapidly rise. d. Isolate Charging piping then one SI Hot Leg pipe at a time; Pressurizer level is monitored, because with the break isolated, RCS inventory will rapidly rise.
2008 Giiina NRC Exam Answer: b. Isolate one SI Cold Leg pipe at a time then Charging piping; RCS pressure ld monitorel flow will repressurize the RCS with the: break isolated.
Explanation:
Incorrect Correct Incorrect Incorrect RO because S Charging is isolated in step 4. of ES-1.2, SI Cold Leg (not Hot leg) is isolated in step 3. RCS pressure is mon;!tored, because SI flow will repressurize the RCS with the break isolated.
Isolate SI Cold Leg piping per step 3f of ECA-1.2. Charging is isolated in step
Isolate SI Cold Leg piping per step 3f of ECA-1.2. Charging is isolated in step 4. Reasonable to conclude this is a viable means of indication that the leak is isolated however not called for in ECA-1.2.
Charging is isolated in step 4. of ES-1.2, SI Cold Leg (not Hot leg) is isolated in 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. WE04 LOCA Outside Containment EA1.2 - Ability to operate and / or monitor the following as they apply 2008 Giiina NRC Exam RO Ouestion 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. MEW, SAFW, feed and bleed, condensate 2008 Giiina NRC Exam Answer: RO a. SAFW, MFW, condensate, feed and bleed. Explanation:
Correct Incorrect Incorrect Incorrect
- a. b. - C. - d. - As per FR-H.1 pages 6-16, lLsts the order as SAFW, MFW, condensate, feed and bleed. By knowing the correct order the correct plant operation is assured.
Recently the correct order w,as MEW 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 %.hen both were available.
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. procedure determine the appropriate EXPECTED ACTIONS or Secondary Heat Sink) and the following: Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat I 2008 Giiina NRC Exam RO Question 19 Plant conditions occurred as follows:
0 0 A control rod dropped. The plant was operating at rated power. The Control Room staff have entered AP-RCC.3, Dropped Rod Recovery. 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. b. C. d. 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. 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. 1. Restore AFD to within limits or be less than 50% Rated Thermal Power in 30 minutes. 2. By limiting the amount of power dist:ribution skewing, core peaking factors are consistent with the assumptions used in the safety analyses.
- 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 the assumptions used in the safety analyses.
1 2008 Girina NRC Exam Incorrect Incorrect correct RO a. 1. Per ITS 3.2.3 action A.l: Restore AFD to within limits or be less than 50% 2. Concerns associated with SDM are always valid and should be addressed
- 1. Correct action however the time is limited to 30 minutes. 2. Concerns associated with SDM are always valid and should be addressed
- 1. Per ITS 3.2.3 action A.l: Restore AFD to within limits or be less than 50% Rated Thermal Power in 30 minutes. however, this is not the bases for the LCO. b. however, this is not the ba.ses for the LCO. c. Answer: 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 dis'kibution skewing, core peaking factors are consistent with the assumptions used in the safety analyses.
Exdanation
- Incorrect - d. safety analysis requirements.
- 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. the following in accordance with (Technical Specifications, TS Bases, TRM, COLR, PTLR, ODCM): AK3.05 - Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod Tech-Spec limits for reduction of load to 50% power if flux cannot be braught back within specified associated Bases
>I 2008 Giinna NRC Exam RO Ouestion 20 Plant conditions occurred as follows: 0 0 0 With the reactor critical during a startup, Control Rods were stopped at 80 steps withdrawn on Control Bank "D". Intermediate Range channel N-35 indicates 1.15E-8 amps and is stable. Intermediate Range channel N-36 indicated 1.02E-8 amps and then failed low. All Power Range Instruments indicated 2% power. Which ONE of the following describes the acti.ons 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-36 and continue with the startup.
I Incorrect Incorrect Incorrect 2008 Giiina NRC Exam Answer: d. Position the Level Trip switch to BYPASS for N-36 and continue with the startup.
- a. b. Not applicable per ITS 3.3.1 IUA 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. 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-l 1 amps complete shutdown is not required.
Not required per ITS 3.3.1 RIA E. 1 or 2, 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
- c. Explanation:
Correct RO shutdown is not required.
Per ITS 3.3.1 WA E.2 and EIR-NIS.2.
Place affected IR Level Trip switch to d. I I BYPASS and be > 8 % power in (2) hours. I 2008 Giinna NRC Exam Question 21 RO Plant conditions occurred as follows: 0 0 0 0 0 The unit was at 100% reactor power. Condenser vacuum began to degrade. The crew responded using AP-TURBA, Loss of Condenser Vacuum. The crew lowered power as directed.
The source of Condenser air in-leakage was found and patched but is still leaking.
Conditions ten minutes later are as follows: o Power is now at 75% of full electrical output.
o Condenser back pressure is 7" He; absolute and degrading slowly.
o Annunciator H-7, Tondenser Hi Pressure" is LIT. o Annunciator D-24, Turbine Trip Auto Stop" is NOT LIT. o The CRS directs the HCO to trip ihe reactor. 1. Why was the Reactor Trip directed? and
- 2. Have the annunciators listed functioned properly?
- a. b. C. d. 1. Trip was directed due to operating outside of allowable turbine operating range and was degrading.
- 2. Annunciator H-7, Tondenser Hi Pressure" should NOT have alarmed until 22" Hg Condenser vacuum.
- 1. Trip was directed since turbine failed to automatically trip. 2. Annunciator D-24 'I Turbine Trip Auto Stop" should have alarmed at 25" Hg Condenser vacuum.
- 1. Trip was directed due to operating oui:side of allowable turbine operating range and was degrading
- 2. Annunciators have functioned as designed.
towards an automatic trip setpoint.
- 1. Trip was directed since turbine failed to automatically trip. 2. Annunciators have functioned as designed.
2008 Gi nna NRC Exam RO
,I 2008 Giiina NRC Exam RO Answer: C. 1. Trip was directed due to operating cutside of allowable turbine operating range and was 2. Annunciators have functioned as designed. degrading towards an automatic trip setpoint.
Explanation:
Incorrect Incorrect Correct Incorrect
- 1. Directed per AP-TURB.4 step 2.a RNO. 2. Annunciator H-7, "Condenser Hi Pressure" alarms at 25.5" Hg Condenser
- 1. Turbine will not automatically trip until
<20" Vacuum. 2. Annunciator D-24 It Turbine Trip Auto Stop" which has many causes to bring 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. vacuum and should be lit. 1. Directed per AP-TURB.4 step 2.a RNO. 2. Annunciators alarmed correctly.
- 1. Turbine will not automatically trip until c20" Vacuum. 2. Annunciators alarmed correctly.
AA2.02 - Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Cortditions requiring reactor and/or AR D-24 and H-7 Fig-13, Figure Back Pressure LP R4 10 1 C, Main Turbine I 2008 Giinna NRC Exam RO This page intentionally blank.
I 2008 Giinna NRC Exam RO Ouestion 22 Plant conditions occurred as follows: 0 0 The Control Room has been abandoned due to a fire in the Main Control Board.
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 Complex Fire. Which one of the following correctly lists all the indications at the Intermediate Building Emergency Local Indicating Panel (IBELIP)?
- a. b. c. d. RCS Loop A Thot RCS Loop A Tcold Motor Driven AFW Pump Flow RCS Loop A Thot RCS Loop A Tcold Turbine Driven AFW Pump Flow RCS Loop B Thot RCS Loop B Tcold Turbine Driven AFW Pump Flow RCS Loop B Thot RCS Loop B Tcold Motor Driven AFW Pump Flow A and B S/G Pressure A WR S/G Level B WR S/G Level A S/G Pressure A WR S/G Level B WR S/G Level A and B S/G Pressure '4 WR S/G Level ,B WR S/G Level 13 S/G Pressure A WR S/G Level 13 WR S/G Level I 2008 Ginna NRC Exam Correct Incorrect RO b. c. As per ER-FIRE.l, Attachment 3 HCO, step 7.0. RCS loo^ B ThotlTcold and B S/G Pressure not available at IBELIP. Answer: b. RCS Loop A Thot A SIG Pressure RCS Loop A Tcold Turbine Driven AFW Pump Flow A WR S/G Level B WR S/G Level Explanation:
I Incorrect I a. 1 Motor Driven AFW Pump Flow and B S/G Pressure not available at IBELIP.
1 1 Incorrect I d. I Motor Driven AFW Pump Flow and B S/G Pressure not available at XBELIP. 1 liary Feedwa.ter Systems, state their purpose, function, and Shutdown for Control Question 23 ,I 2008 Giiina NRC Exam RO Plant conditions are as follows:
0 0 0 0 A Steam Line Break has occurred. All equipment actuated as required.
The Control Room staff has isolated this faulted Steam Generator. Safety Injection and Containment Isolation have been reset. RCS pressure is 1850 psig and slowly trending up. 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. Establish Charging.
- 3. Stop 1 RHR pump. Ensure RCS pressure remains stable, then stop the second RHR pump. c. 1. Stop 1 SI pump. 2. Check RCS pressure stable and then establish Charging.
- 3. Verify SI flow not required, then stop any running SI pumps and BOTH RHR pumps. d. 1. Establish Charging.
- 2. Check RCS pressure stable and stop 1 SI pump. 3. Stop 1 RHR pump. Ensure RCS pressure remains stable, then stop any running SI pumps and the second RHR pump.
I 2008 Ginna NRC Exam Incorrect RO d. Answer: a. 1. Establish Charging.
Explanation:
Correct + Charging established first, then all pumps stopped, then verification of SI not required per ES- 1.1, SI Termination steps 5-8. Flow reduction sequence not correct.
Charging established first, then all pumps stopped, then verification of !$I not required per ES- 1.1, SI Termination steps Flow reduction sequence not correct. Charging established first, then all pumps stopped, then verification of !$I not required per ES-1.1, SI Termination steps 5-8. 5-8. Flow reduction sequence not correct. Charging established first, then all pumps stopped, then verification of !;I not required per ES-1.1, SI Termination steps 5-8. rmine and interpret the following as they apply ES- 1.1, SI Termination I 2008 Giiina NRC Exam RO Question 24 Plant conditions are as follows: 0 The unit has experienced a Loss of Cocdant Accident (LOCA). All plant equipment operated as designed.
0 E-0 and E-1 have been completed. While performing ES- 1.2, Post LOCA Cooldown and Depressurization, Reactor Coolant System (RCS) conditions are determined to be adequate 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 . . . a. remain the same. Due to reduced SI flow, RCS temperature will rise and with it RCS pressure.
- 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 Gina 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.
Incorrect Incorrect Correct Incorrect Exdanation:
- a. b. c. d. Subcooling will lower due to lower SI flow and subsequently lower RCS pressure. RCS temperature is controlled by dumping steam. Subcooling will lower due to lower SI flow and subsequently lower RCS pressure.
As SI flow lowers due to stopping of (1) SI pump RCS pressure will lower to a new equilibrium value.
RCS temperature is controlled by dumping steam.
llsed on Audit Exam - No 2008 Giiina 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.l, Response to Imminent Pressurized Thermal Shock Condition was entered. 0 All SI pumps were stopped.
0 Adequate subcooling was verified.
0 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.) a. Lower RCS subcooling by opening a PCIRV. b. Fully open an ARV to lower the RCS le& rate. c. Feed the S/Gs as rapidly as possible to rctum S/G levels to normal levels.
- d. Run SI Pumps as needed to maintain Pressurizer water level above 7%.
11 2008 Giiina NRC Exam a. b. c. d. Answer: 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 co responding 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 complete.
This would result in a cooldown and is not allowed till the 1 hr soak time is complete.
This would result in a rise in RCS pressure and is not allowed till the 1 hr soak time is complete.
RO a. Lower RCS subcooling by opening a PORV. Explanation:
Correct Incorrect Incorrect Incorrect Thermal Shock) and the following: Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal I1 2008 Gina NRC Exam Question 26: Plant conditions occurred as follows: 0 0 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 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. b. C. d. 1 Reactor Head area is subcooled.
- 2. Continue cooldown rate in RCS cold legs less than 25°F per hour. 1. Reactor Head area is subcooled.
- 2. Raise cooldown rate in RCS cold legs to less than 50°F per hour.
- 1. Steam voids are forming in the reactor head area. 2. Repressurize the RCS within allowable limits and continue cooldown.
- 1. Steam voids are forming in the reactor head area. 2. Continue with cooldown and stop dep:ressurization.
RO 2008 Girina NRC Exam Answer: Incorrect Incorrect Correct a. b. c. For given set of conditions the Rx head area is not subcooled. This is the correct cooldown for the given conditions.
For given set of conditions the Rx head area is not subcooled.
Max cooldown rate is 25°F per hour for given conditions.
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 required due to steam voiding in the head region.
A RO c. 1. Steam voids are forming in the reactor head area.
- 2. Repressurize the RCS within allowable limits and continue cooldown.
, 2008 Giiina NRC Exam RO Ouestion 27 Plant conditions are as follows: 0 0 0 The reactor has tripped due to a Loss OF Coolant Accident (LOCA).
The Control Room staff is working through the EOPs. 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 2 and if they are NOT, then dispatch personnel to the Relay Room to open the dampers by a. b. C. d. 1. Extinguished
- 2. pushing in the trip relay plungers 1. Bright 2. pushing in the trip relay plungers
- 1. Extinguished
- 2. opening breakers that supply power to the dampers
- 1. Bright 2. opening breakers that supply power to the dampers I 2008 Giiina NRC Exam Incorrect Incorrect Incorrect Answer: b. c. 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 saiety 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 confjguration.
- d. RO a. 1. Extinguished
- 2. pushing in the trip relay plungers Explanation:
1 Correct I a. I Per FR-Z.3 step 2b and RNCI 2b.
II 2008 Giiina NRC Exam RO Ouestion 28 Plant conditions are as follows:
0 0 0 0 The unit is at 15% power.
Annunciator A-15, RCP B CCW RETtJRN HI TEMP OR LO FLOW 165 GPM 125°F is lit. MOV-759B, CCW from RCP 1B ISOL, VLV indicates closed and cannot be reopened.
All RCP seal injection parameters indicate normal.
What is the condition of the plant in (5) minutes, after the Control Room staff completes all of their required actions for these given conditions?
- a. "A" RCP is secured, "B" RCP is secured and the unit is at 0% power. b. "A" RCP is running, "B" RCP is secure13 and the unit is at 0% power. c. "A" RCP is secured, "B" RCP is running and the unit is at 0% power. d. "A" RCP is running, "B" RCP is running and the unit is at 15% power.
,I 2008 Giiina NRC Exam Answer: b. "A" RCP is running, "B" RCP is secured and the unit is at 0% power. ~~ Incorrect Correct Incorrect Incorrect RO a. b. c. d. RNO step 4a/b instructs to trip the Rx and only the affected RCP. Want to have (1) running RCP for decay heat removal and better control for plant cooldown.
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. Correct answer only the RCPs are reversed therefore incorrect.
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 triD the Rx and onlv the affected RCP. Explanation:
2008 Giiina NRC Exam RO Ouestion 29 Prior to starting a Reactor Coolant Pump (RCP) ensure its Oil Lift Pump has been delivering oil to the 1 for at least 2 -* The Oil Lift Pump WHITE indicating light will be lit 3 a. 1. upper thrust shoes 2. two minutes
- 3. by a pressure switch when proper lift pressure is attained.
- b. 1. lower radial bearing 2. oneminute
- 3. as soon as the Oil Lift Pump starts c. 1. upper thrust shoes 2. two minutes 3. as soon as the Oil Lift Pump starts d. 1. lower radial bearing 2. one minute 3. by a pressure switch when proper lift pressure is attained.
,I 2008 Ginna NRC Exam Correct Incorrect RO a. b. Per precaution 4.5 of S-2.1, Reactor Coolant Pump Operation. All answers are incorrect per precaution 4.5 of S-2.1, Reactor Coolant Pump ODeration.
Answer: Incorrect Incorrect
- a. 1. upper thrust shoes
- 2. two minutes 3. by a pressure switch when proper lift pressure is attained.
- c. d. Oil Lift Pump WHITE indicating light will be lit by a pressure switch when proper lift pressure is attained.
Oil Lift Pump must run for at least two minutes.
Explanation:
2008 Giinna NRC Exam Ouestion 30 Plant conditions are as follows: 0 0 0 0 VCT level is 25%. 0 0 0 The plant has been operating for two ufeeks following a Refueling outage.
The reactor is currently at 100% powe1'. CCW Surge Tank is 50%. 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.
RO d. Rods will step out to maintain Tavg and Tref approximately equal.
2008 Giiina NRC Exam Answer: c. Rods will step in to maintain Tavg and Tref approximately equal.
Explanation:
RO Incorrect I a. I Level control system for VCT will divert the excess water. Level won't go much Correct J - higher than
-30%. RCP #1 Seal Return flow is at a much lower pressure than CCW pressure. CCW Surge Tank level will lower not rise. RCP #1 Seal Return flow is ;it a much lower pressure than CCW pressure.
CCW Surge Tank will lower and u'ater will return to the VCT. Since CCW is not borated this is the same as a dilution.
As 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 1.5"F rods will step in to lower Tavg. This response would be correct if there were an inadvertent boration occurring but due to the given conditioiis a dilution is occurring.
K3.01 Knowledge of the effect that a loss or malfunction of the CVCS will have on the following:
CRDS (automatic) Volume Control System, I 2008 Giiina NRC Exam RO Ouestion 31 Plant conditions are as follows: 0 0 0 0 The unit is in MODE
- 5. RHR is in shutdown cooling.
RCS temperature is 180°F and stable. 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 plant respond in the next 15 minutes? a. b. C. d. RCS temperature will rise because HCV-624 and HCV-625 will fail closed and HCV-626 will fail open, therefore providing no cooling.
RCS temperature will lower because HCV-624 and HCV-625 will fail open and HCV-626 will fail closed, therefore providing maximum cooling. RCS temperature will remain unchanged because HCV-624, HCV-625 are pinned locally and are unaffected by the loss of Instrument Air. RCS 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.
'I 2008 Girina NRC Exam Incorrect Correct RO a. b. This is correct if the failure positions of HCV-624,625 and 626 were reversed. HCV-624 and 625 fail open and HCV-626 will fail closed, therefore providing Answer: b. RCS temperatue will lower because HCV-624 and HCV-625 will fail open and HCV-626 will fail closed, therefore providing maximum cooling.
Explanation:
Incorrect Incorrect
- c. d. HCV-624, HCV-625 and HCV-626 are not normally operated locally. MOV-738A and MOV-738EL are unaffected by the loss of Instrument Air but I maximum cooling. 1 Tscbalcpd Rd@43?M@S cruestfora HiMary: lWFR S!3 Content: I I 0-2.2, Plant Shutdown from Ite%erptrreclo None Hot Shutdown to Cold psovddraai Conditions drrrlnght LP R2501C, Residual Heat Removal System ' Used on Last (2) NRC Exams - No Used on Audit Exam - No IQuusa Bfirnk # Common Exam Bank PWR Industry 55.41(a)(7)
I 55.43 RCS temperature will lower because HCV-624 and HCV-625 will fail open and HCV-626 will fail closed, therefore providing maximum cooling.
I 2008 Giiina NRC Exam Question 32 Plant conditions are as follows:
e A unit startup is in progress in accordance with 0-1.1, Plant Heatup from Cold Shutdown to Hot Shutdown.
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" Charging Imp is Operable and prlwiding normal charging flow. RCS Tcold - 120°F The conditions described above are IMPROPESR because . . . a. if the SI pump were to start, it would ov'erpressurize the RCS. b. the heatup rate is too high for the RCS temperature and pressure.
- c. the number of ECCS pumps available to provide injection is inadequate.
RO d. running one RCP and two RHR pumps produces non-uniform core cooling.
I 2008 Girina NRC Exam Correct Incorrect Answer: a. b. With the RCS solid this violates ITS 3.4.12, LTOP System, A.l. Heatup rate is limited to a maximum of 50°F per hour when less than 220°F RCS temrierature.
1 RO ~ Incorrect
- a. if the SI pump were to start, it would overpressurize the RCS. c. No ECCS pumps are required in Mode 5. Explanation:
Incorrect
- d. Non-uniform cooling is not the concern for the given conditions. - Cold Shutdown to Hot I 2008 Ginna NRC Exam Ouestion 33 Plant conditions occurred as follows: 0 0 The plant was operating at 100% powei. when a Reactor Trip and SI occurred. Shortly after the SI actuation the follouhg conditions were observed:
o R-7, Incore Detector Area radial:ion 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 result in these conditions?
- a. "B" RCP #1 seal has failed. b. PCV-435, Pressurizer Safety valve is stuck open.
- c. SOV-592, Reactor Head Vent valve has failed open. d. An Incore Thimble Tube has ruptured at the bottom of the reactor vessel.
,I 2008 Giiina NRC Exam Answer: b. Exolanation:
PCV-435, Pressurizer Safety valve is stuck open.
Incorrect Correct Incorrect Incorrect RO 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-3 13), and the excess letdown relief lift:; 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 rupture disc failure in such a short time. Pzr Safety failing open woulld 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.
SOV-592 is isolated by SV-590 which is normally closed, therefore there would be no release to the containment or the PRT. Incore thimble tube failure is likely to result in the containment radiation conditions described but will not result in the abnormal PRT conditions.
- b. c. d. loss or malfunction of the PRTS will have on the following: Containment 2008 Girina NRC Exam RO Question 34 Plant conditions are as follows:
The unit is at 75% power.
The electric plant is in an Alternate 50/50 lineup. "B" CCW pump is running.
"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 Giiina NRC Exam Answer: Incorrect Incorrect
- 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. a. b. Correct power supplies however, CCW pumps starts immediately, Service Water pumps are delayed 40 seconds. 7T is P/S in an Alt 50/50 1int:uD. Explanation:
Incorrect
- c. Correct d. RO I 7T is PIS in an Alt 50/50 lintxp and CCW pumps starts immediately, Service Water pumps are delayed 40 seconds. 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. components
- a. Component Cooling Water Pumps pump, including emergency backup Distribution System pgs. LP R2801C, Component Cooling Water System I 2008 Ginn a NRC Exam RO Question 35 Concerning Pressurizer Sprays: 1. What design feature assists in minimizing the Thermal Shock to the Pressurizer Spray Nozzle?
and 2. With spray valves PCV-43 1A and PCV-43 1B closed and both RCPs running, what is the TOTAL design Pressurizer Spray flow going through i;he Pressurizer Spray Nozzle? a. 1. Each Spray line has a hole that is drilled thru the disk of the Spray Valve. 2. (2) gpm b. 1. Each Spray line has a bypass line with a manually opened valve.
- 2. (2) gpm c. 1. Each Spray line has a hole that is drilled thru the disk of the Spray Valve. 2. (4) gpm d. 1. Each Spray line has a bypass line with a manually opened valve.
- 2. (4) gpm 2008 Ginma NRC Exam Answer: b. 1. Each Spray line has a bypass line with a manually opened valve.
- 2. (2) gpm Explanation:
RO is design feature, but not at Ginna.
ss line = (2) gpm total.
bypass line provides the flow. ss line = (2) gpm total. is design feature, but not at Ginna.
ss line = (2) gpm total. bypass line provides the flow. ss line = (2) gpm total.
K4.01 - Knowledge of PZR PCS design feature(s) and/or interlock(s) which provide for the following:
Spray valve warm-up LP R1401C, Pressurizer Pressurizer Relief Tank I 2008 Giiina NRC Exam RO Ouestion 36 Plant conditions are as follows:
0 0 0 The unit was at 100% reactor power. Rod control is in Manual and all other controls are in automatic.
PT-430, Pressurizer Pressure detector is slowly failing high. 1. How will this affect the associated Over Ternperature 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 Ginina NRC Exam Answer: d. 1. The Over Temperature Delta-T trip setpoint will rise. 2. LESS Conservative.
- a. b. c. d. Explanation: 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.
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.
Because the failure causes the setpoint to be higher it is less conservative.
As pressure goes up so does Ihe 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 being LESS conservative and putting the core at greater risk.
Incorrect Incorrect Incorrect Correct RO 2008 Ginria NRC Exam Ouestion 37 RO Plant conditions occurred as follows: 0 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 performed.
At this time, how many Component Cooling Water Containment Penetration Valves (not including any check valves), are closed due to this event? a. 1 b. 2 c. 3 d. 4 I 2008 Gin na NRC Exam RO Answer: b. 2 Exdanation: ~ ~~ Incorrect Correct Incorrect Incorrect With the loss of MCC-D only (2) valves will be closed as described in "b" below. If AOV-745 is forgotlen, this answer would be selected. 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. 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 won't shut this would be the correct choice however as outlined in "b" above only (2) CCW Containment Penetration Valves will be shut . K1.08 - Knowledge of the physical connections and/or cause effect I 2008 Ginina NRC Exam RO Ouestion 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 1C Containment Recirc Fans were running and 1D Containment Recirc Fan was in Pull-Stop due to maintenance on its breaker.
0 The White Lights for 1B and 1C Conta.mnment Recirc Fan Vibrations have just illuminated.
0 Annunciator B-32, Containment Recirc Fan Vibration have just alarmed. What is the status of the Containment Recirc Fans and what operator actions are required?
- a. 1 A, 1B and 1C Containment Recirc Fans are running. An A0 must be sent to reset the "Vibration Reset" in the Intermediate Building (clean side) and at the Containment Sound Monitor listen for abnormalities.
- b. Only 1A Containment Recirc Fan is running. 1B and 1C Containment Recirc Fans can be manually restarted. . An A0 must be sent to reset the "Vibration Reset" in the Intermediate Building (clean side), then the e. lA, 1B and 1C Containment Recirc Fans are running.
Immediately stop 1B and 1C Containment Recirc Fans, and then send an A0 to reset the "Vibration Reset" in the Intermediate Building (clean side), then the 1B and 1C Containment Recirc Fans can be manually restarted and at the Containment Sound Monitor listen for abnormalities.
- d. Only 1A Containment Recirc Fan is running.
An A0 must be sent to reset the "Vibration Reset" in the Intermediate Building (clean side), then the 1B and 1C Containment Recirc Fan control switches must be placed in stop then fans will automatically restart.
$1 2008 Ginna NRC Exam RO Answer: a. 1 A, 1B and 1C Containment Recirc Fans are running.
An A0 must be sent to reset the "Vibration Reset" in the Intermediate Building (clean side) and at the Containment Sound Monitor listen for abnormalities.
Explanation:
Correct Incorrect Incorrect Incorrect
- a. - b. - C. d. - All available fans will start 011 an SI signal and the Vibration indicators (fan, motor, coupling) will not trip the fans. Actions are required by AR-B-32, Containment Recirc Fan Vibration.
This is correct if the high vibrations were a fan trip but they are not. All available fans lA, 1B and 1C Containment Recirc Fans will be running.
An A0 will be sent to reset the "Vibration Reset" in the Intermediate Building (clean side) but this is not required for the fans to run. All available fans will start 011 an SI signal and the Vibration indicators (fan, motor, coupling) will not trip the fans.
Due to the given conditions even with the high vibrations annunciator in, the fans must be left running and monitored for possible failure. The fan are performing their safety function and must be left on. This is correct if the high vibrations were a fan trip but they are not. All available fans lA, 1B and 1C Containment Recirc Fans will be running. An A0 will be sent to reset the "Vibration Reset" in the Intermediate Building (clean side) but this is not required for the fans to run.
I 2008 Ginna NRC Exam RO Ouestion 39 Plant conditions are as follows: 0 0 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. All of the Service Water (SW) header isolation valves indicate open. FCV-4561 and FCV-4562, CNMT REClIRC 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 2. The FCVs are full open, they failed full open on the SI signal. b. 1, (12) valves 2. The FCVs are not fully open, they must be failed full open locally. c. 1. (12) valves 2. The FCVs are full open, they failed full open on the SI signal. d. 1. (6) valves 2. The FCVs are not fully open, they must be failed full open locally.
4 2008 Ginna NRC Exam Incorrect Answer: b. RO Incorrect
- d. 1. (6) valves 2. The FCVs are not fully open, they must be failed full open locally.
- c. Explanation:
Incorrect I a. Correct 1 FCV-4561 and FCV-4562 status lights are bright when failed fully open. 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. FCV-4561 and FCV-4562 status lights are bright when failed fully open. 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. 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 axe dim the valves are not full open and the RNO from ATT-27.0 directs the operator to have an A0 locally fail the valves full open. and/or monitor changes in parameters (to Verification, pg. 4 LP R5101C, Service Water 11 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, a Station Blackout occurred.
0 The Control Room Team is performing ECA-0.0, Loss of All AC Power. 0 Containment Pressure and Temperature are steadily rising. 1. What is the MINIMUM combination of Containment Cooling Systems that must be returned to service to meet the assumptions used in the DB LOCA accident analysis?
and 2. When would the Containment design Temperature limit FIRST be exceeded?
- a. 1. (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 2008 Ginna NRC Exam Answer: Incorrect Incorrect RO a. b. Need (2) Containment Recirc: Fans. Need (2) Containment Recirc: Fans. C. 1. (1) Containment Spray Pump and (2) Containment Recirc Fans 2. Containment Temperature
> 286°F Incorrect Correct Containment Temperature Limit is 286°F. 282°F is the Deak temDeratur: exDected following a DB LOCA. d. - C. Al.02 - Ability to predict and/or monitor changes in parameters (to I 2008 Ginna NRC Exam RO Ouestion 41 Plant conditions are as follows:
0 0 0 0 ARVs are in Manual.
The unit is performing a startup following a Mid-cycle maintenance outage.
The SHUTDOWN BANKS have been withdrawn.
The CONTROL BANKS are being withdrawn.
What plant evolution would result in the reactor going critical PRIOR to the expected value obtained in accordance with the Estimated Critical Posit]
on (ECP)? (Assume no other operator action.) a. Steam Generator operating level is reduced from 60% to 50%. b. (1) Steam Generator Automatic Relief Valve (ARV) 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.
2008 Ginna NRC Exam Answer: Incorrect Incorrect Incorrect Correct d. Steam is bypassed around the MSlVs to start the warm-up of the Main Steam Headers. a. b. Feedwater is reduced to achieve new S/G level. No change in reactivity.
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. Adds negative reactivity, cau.3ing the point when the Rx will go critical to be later than the ECP. 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. c. d. Explanation:
RO LP RRTOSC, Inherent 2008 Ginnia NRC Exam RO Question 42 Plant conditions are as follows:
The unit is operating at 90% power. All plant control systems are in their normal at power alignment.
Which of the following failures will cause Reactor Coolant System (RCS) Tavg to INITIALLY Rise? a. b. c. Low Pressure Heater Bypass Valve V-3959 fails open. Main Feedwater Bypass Valve to Steam Generator A, AOV-4271, spuriously opens. Instrument Air is lost to "B" Main Feedwater Regulating Valve, AOV-4270.
- d. V-5604, Exhaust Steam from the HP Turbine to # 5B FW Heater disc separates from its stem and fails closed.
11 2008 Ginna NRC Exam Answer: c. Instrument Air is lost to "B" Main Feedwater Regulating Valve, AOV-4270.
Incorrect Incorrect
Correct Incorrect RO a. b. c. Due to the loss of FW heating to both S/Gs, Tavg will lower. Main Feedwater Bypass Valves are isolated during power ascension.
No affect. AOV-4270 closes on a loss of IA, FW 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.
If ES steam is lost to ## 5B FTV Heater, FW temp to the B S/G will lower which d. Explanation:
I will cause Thot to lower which will result in Taig lowering.
I 2008 Ginna NRC Exam RO Ouestion 43 Plant conditions are as follows:
0 0 0 The unit is operating at 50% power. All plant control systems are in their normal at power alignment.
A leak develops on the Condensate Storage Tanks and cannot be isolated.
As CST water level drops, the FIRST volume lhat will require actions to be taken in accordance with Technical Specifications is when the comhined volumes of the CSTs goes below gallons.
- a. 25,200 b. 24,350 c. 23,450 d. 22,500 Answer: b. 24,350 Explanation:
I Incorrect I 2008 Ginna NRC Exam RO d. I Old ITS requirement prior to up-rate.
I 2008 Ginna NRC Exam RO Question 44 Plant conditions are as follows: 0 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.
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-97 10A, SAFW Pump "C" Recirculation Valve, is closed.
o MOV-9703A, SAFW Crossover Valve, is open.
o MOV-9701A, SAFW Discharge Valve, is closed. Why won't 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 "C" SAFW pump. c. AOV-97 10A, 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 rnust 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 Answer: Correct RO it will not prevent a pump start. Interlocked with pump.
MO\'-9629A must be open to start the "C" SAW b. b. MOV-9629A, SAW Pump "C" Suction Valve must be open to provide a suction source to the "C" SAFW pump. Explanation:
Incorrect I a. I "C" SAW pump will start with MOV-9703A open, not a normal alignment but Valve, is normally closed and will while the "C" SAFW pump is running. Valve receives any automatic signal to open I 2008 Ginina NRC Exam Ouestion 45 Plant conditions are as follows: RO 0 0 The unit is at 80% power. The electric plant is in a Normal 50/50 lineup. Annunciator 5-26, Generator Exciter Field Breaker Trip, has just come in. Which one of the following DIRECTLY caused the Generator Exciter Field Breaker to Trip open? a. Turbine Trip Rel'ay 86X. b. Turbine Trip Relay 86A3U. c. Generator Overvoltage (GOV). d. Overexcitation Protection (OXP).
I1 2008 Ginna NRC Exam Incorrect
' Incorrect
- c. d. There are Generator differential current and ground trips, but no Generator Overvoltage trip.
OXP shifts the voltage regulator from auto (AC) to manual (DC), but has no RO Catep2QI.y:
Answer: Tier 2 /Group 1 Qnesltiorr sowrca2 New b. Turbine Trip Relay 86/BU. Cogmitiveteve&
M/F Explanation:
DfQIk*Levttl:
4 the Exciter Field Breaker and Trip Relay 86X of a number of breakers including the Exciter Field Breaker. I direct trip to the Exciter Field Breaker. 062 AC Electrical Distribution K4.02 - Knowledge of ac distribution system design feature(s) and/or interlock(s) which provide for the following: Circuit breaker pgs. 15, 16,21,22,23 AR-J-26, Generator Exciter I 2008 Ginna NRC Exam RO Question 46 Plant conditions are as follows: 0 0 0 0 The unit is at 90% power. The electric plant is in a 100/0 lineup.
Instrument Bus "1C" is being supplied by Inverter "1B". The 125 VDC supply from DC distribuiion panel 1B has been interrupted.
How will the plant respond? Static Transfer Switch 1B . . . a. b. C. d. will automatically transfer to the Constant Voltage Transformer, and will automatically transfer back to the "1B" Inverter when 125 VDC is rlzstored.
must be manually transferred to the Constant Voltage Transformer, but will automatically transfer back to the "1B" Inverter when 125 VDC is restored.
will automatically transfer to the Constant Voltage Transformer, but must be manually transferred back to the "1B" Inverter when 125 VDC is restored.
must be manually transferred to the Constant Voltage Transformer, and must be manually transferred back to the "1B" Inverter when 125 VDC is restored.
I 2008 Ginna NRC Exam Incorrect Incorrect Answer: ~~ a. b. Must be manually transferred back. Automatically transfers to alt P/S and must be manually transferred back. c. will automatically transfer to the Constant Voltage Transformer, but must be manually transferred back to the "1B" Inverter when 125 VDC is restored.
Correct I c. Incorrect I d. Explanation:
This is the proper operation of the 1B Static Transfer Switch. Automaticallv transfers to alt P/S. RO Tabid Ref-wt Que&- *&tory: 1WFR 55 Content: I I LP R0901C, Instrumenl Bus Ref-- None & DC Power Supply System Used on Last (2) NRC Exams - No Ex- C063.0067 pwvidd Pgs. 26,27 durinfgExCura!
55.41(a)(7)
I 55.43 Used on Audil Exam - No Bank # I RO2008GinnaNRC I Qn esh# I 46 I Rev.2 I Level: RO I 2008 Ginna NRC Exam Question 47 Plant conditions are as follows:
0 0 0 The unit is at 100% power. The electric plant is in a Normal 50/50 lineup. Due to a severe ground there is a complete Loss of "B" DC MCC. How will the Reactor Trip breakers respond?
- 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.
- 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.
RO 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 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:
RO Correct Per P-10 and ER-ELEC.2. will be tripped by its undervoltage coil. will be tripped by its shunt coil. ical connections between the Reactor Protection P- 10, Instrument Failurc Reference Manual 41 2008 Ginna NRC Exam RO Ouestion 48 Plant conditions are as follows: 0 0 0 0 0 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. While checking on the automatic start clf the "A" D/G and fault on SST-18, the A0 reported MCC "H' is deenergized due to its feeder breaker being open. The A0 reports an acrid smell in the area of the feeder breaker but no fire. 1. What is the impact of MCC "H' being deenergized?
and 2. What action(s) is/are required to mitigate the consequences of MCC "H' being deenergized?
- a. 1. There is no power to the "A" DIG 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. This crosstie alignment has been considered and no operability concerns exist.
- b. 1. There is no power to the "A" D/G Fuel Oil Transfer Pump. 2. Lineup a temporary pump to fill the "A" DJG Fuel Oil Day Tank. The "A" and "B" D/G Fuel Oil Transfer Systems can not be cross-connected or it will make both D/Gs inoperable.
- c. 1. There is no power to the "A" DIG 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. DIG Air Start Systems can not be cross-connected or it will make both D/Gs inoperable.
- 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 Di2y Tank using the "B" D/G Fuel Oil Transfer Pump. This crosstie alignment has been cons idered and no operability concerns exist.
2008 Ginna NRC Exam Answer: Incorrect Incorrect Incorrect Correct RO a. b. There is power to the "A" DIG Air Start Compressor it comes from MCC J. With MCC H deenergized thlzre is no power 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. There is power to the "A" D/lG Air Start Compressor it comes from MCC J. With MCC H deenergized there is no power to the "A" DIG Fuel Oil Transfer PumD. X-conn ODS are allowed Der T-27.6. c. d. d. 1. There is no power to the "A" DIG Fuel Oil Trans*er 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.
ExDlanation:
relationship) between the Diesel Generator System and the given interrelated system:
- a. 480V electrical System or operations on the ED/G system; and (b) based on those predictions, 11 2008 Ginna NRC Exam RO Question 49 Plant conditions are as follows:
0 0 0 0 0 0 0 The plant is at 2% power conducting a unit startup per 0-1.2, Plant Startup from Hot Shutdown To Full Load.
"A" and "B" MDAFW pumps are running to maintain S/G water levels at 52%. AOV-5738, "A" S/G Blowdown Isolation Valve key switch is in "AUX'. AOV-5737, "B" S/G Blowdown Isolation Valve key switch is in "AUX'. S/G Blowdown Valves AOV-5737 / 57.38 / 5735 / 5736 "Close - Remote" switch is in "Remote".
S/G Blowdowns are in progress for both S/Gs to maintain S/G chemistry.
Chemistry is sampling both S/Gs. The detector for R-19, Steam Generator Blowdown Process Radiation Monitor fails high. What is the expected plant condition and plant personnel response for the given conditions? (Assume all ITS, TRM and ODCM requirements are met.) a. b. C. d. S/G Blowdown valves, AOV-5737
/ 573 8 are closed, to reopen the S/G Blowdown valves place AOV-5738/5737, A/B S/G Blowdown Isolation Valve key switches to "DEFEAT".
S/G Blowdown valves, AOV-5737
/ 5738 are open, immediately place S/G Blowdown Valves AOV-5737 / 5738 / 5735 / 5736 "Close
.- Remote" switch is in "Close". S/G Sample valves, AOV-5735
/ 5736 are closed, the only way to reopen the sample valves is to clear the close signal coming from R-19.
S/G Sample valves, AOV-5735
/ 5736 are open, when the chemist is done sampling and secures the lineup, the S/G Sample valves will close.
2008 Ginna NRC Exam Answer: RO d. S/G Sample valves, AOV-5735
/ 5736 are open, when the chemist is done sampling, the S/G Sample valves will close. Explanation:
Incorrect Incorrect Incorrect Correct - a. - b. - C. - d. 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. S/G Blowdown valves, AOV-5737 / 5738 will be closed regardless of the switch position of AOV-573817, A/EI S/G Blowdown Isolation Valve key switches.
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. Clearing the high signal from R-19 is not required to open the sample valves. 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 RemotldClose Switch Predict the effect(:;)
of a loss or malfunction of the following component(s) and/or instrumentation on the Steam Generator Blowdown System:
A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of Blowdown System 2008 Ginna NRC Exam RO Question 50 Plant conditions occurred as follows: 0 0 Due to a Loss of Coolant Accident (LOCA) which was followed by significant fuel failure, radiation levels throughout the plant are: trending up. 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 Al;m comes in.
0815 - R-45, CR PRM High Alium comes in, From the following choices, what is the FIRS? time that BOTH Trains of CREATS system will be in the Emergency mode? a. 0804 b. 0807 c. 0813 d. 0816 I 2008 Ginna NRC Exam Incorrect RO go into the Emergency mode. Indication only.
CREATs goes into the Emergency mode on R-45 or 46 not on b. Answer: C. 0813 Explanation:
I Incorrect I a. 1 Indication only. May choose if unclear on which PRM alarm causes CREATs to I I I I R-1. I As per P-9 and AR-E- 11. Takes only R45 or R-46 to be in High alarm for both 2008 Giniia NRC Exam RO Ouestion 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. d. Preferred Auxiliary Feedwater Pump Oil. Coolers Safety Injection Pump Outboard Thrust Bearing Housing Oil Coolers 2008 Ginna NRC Exam Answer: Correct Incorrect Incorrect
Incorrect
- a. Residual Heat Removal Pump Room Coolers
- a. Non-critical load.
- b. Critical load. c. Critical load.
- d. Critical load.
Explanation:
! 2008 Ginna NRC Exam Question 52 Plant conditions are as follows: RO 0 0 0 The unit is at 100% power. Due to issues associated with the Service Water (SW) pumps AP-SW.2, Loss of Service Water has been entered. "C" SW pump is the only SW Pump running. Operations personnel are monitoring plant equipment.
- 1. What is the expected 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 2. Align Alternate D/G Cooling to the "A" D/G. temperatures remain relatively steady.
- b. 1. Condensate Pump and Condensate Booster Pump motor temperatures slowly rise. 2. Align Alternate D/G Cooling to the "A" DIG. 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 2. Perform a Load Reduction. temperatures remain relatively steady.
2008 Giniia NRC Exam Answer: a. b. c. d. RO Right plant response but, with "C" SW pump as the only SW Pump running, AP-SW.2 directs lining up Alternate DIG Cooling per ER-DG.2 to the "B" D/G. 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. SW does not supply cooling water to the CB pumps therefore they should stay relatively the same temperature.
Right plant response and AP- SW.2 step 5 RNO directs a power reduction to stabilize eauiument temr>eratures.
- d. 1. Condensate Pump motor temperatures slowly rise, while Condensate Booster Pump motor temperatures remain relatively steady. 2. Perform a Load Reduction.
Explanation:
Incorrect Incorrect Incorrect Correct or operations on the SWS; and (b) based on those predictions, use the consequences of those ll 2008 Ginna NRC Exam RO Question 53 Plant conditions are as follows: 0 0 0 0 0 0 The unit is at 100% power. The Service and Instrument Air headers are split.
T-21, Periodic Operation of Instrument Air Compressors "A" and "B" is being performed.
"A" and "B" Instrument Air Compressors are running.
"C" Instrument Air Compressor is runnmg unloaded.
Instrument Air header pressure then starts to trend down.
Which one of the following is the correct response per T-21, for the given conditions?
- a. b. C. d. "C" Instrument Air Compressor will automatically reload when the Instrument Air header pressure reaches 105 psig. The Control Room Operator must push the "LOAD' button on the MCB (back panel) by the "C" Instrument Air Compressor, when the Instrument Air header pressure reaches 105 psig. 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. 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 header pressure reaches 105 psig.
2008 Ginina 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 .4ir Compressor, when the Instrument Air header pressure reaches 105 psig. Explanation:
md Service Air System litions, describe the design features of the instrumentation and/or processes
- a. Instrument Air Compressors K4.01 - Knowledge of IAS design featiire(s) and/or interlock(s) which provide for the following:
ManuaVautomatic transfers of control I 2008 Ginina NRC Exam RO Ouestion 54 Plant conditions are as follows: 0 0 0 0 0 The unit is at 50% power. "C" Instrument Air Compressor (IAC) is running.
"A" and "B" Instrument Air Compressors are in Auto. Service and Instrument Air headers are cross-connected per T-lC, Instrument Aidservice Air Cross Connect Power to Bus 15 is lost due to a fault. How will the Control Room Instrument Air (IA) header pressure gauge, PI-2086 respond and why? When IA header pressure lowers to . . . a. 105 psig the "A" IAC will automatically start and load.
If IA pressure rises to 125 psig, "A" IAC will unload. b. 105 psig the "B" IAC will automatically start and load. If IA pressure rises to 125 psig, "B" IAC will unload. c. 105 psig the "A" IAC will automatically start and load. If IA pressure rises to 130 psig, "A" IAC will unload. d. 105 psig the "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. 105 psig the "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 405 psig. Constant speed - comp runs loadinghnloading 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 nsig. 14 I Incorrect I d. I "B" IAC will not start it is powered from Bus 15, which is dead.
2008 Ginna NRC Exam RO Ouestion 55 Plant conditions are as follows: 0 0 0 0 The unit is in Mode 6. Shutdown Containment Purge is runnin<g to support refueling operations.
Core Alterations are in progress.
All pool levels are normal.
Which one of the following would require the suspension of Core Alterations in accordance with Technical Specifications?
- a. The Containment Equipment hatch is in place with (6) equally spaced bolts. b. "A" MCB DC Distribution Panel is isolated to perform a clean and inspect inside the Distribution Panel. 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 all of the oil out of the motor.
2008 Ginna NRC Exam Answer: Techafcal 1 ITS 3.9.3,3.9.4 and Bases I R.&IWMM l2dem: mvided I Failure CI andCVI Logic I during Exam: m I - __ - - , - ___ #: b. "A" MCB DC Distribution Panel is isoliited to perform a clean and inspect inside the Distribution Panel.
None PWR Lndustry Common Exam Bank Explanation:
Incorrect Correct - a. - b. RO Allowed per ITS Bases 3.9.3. as long as (4) equally spaced bolts are in place the LCO is met. With Shutdown Containment Purge running there must be (2) trains of CVI Operable to close the penetrations.
With "A" MCB 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 CR-2006-005236.
as one of the two personnel air lock doors water level
>23' above the top of the I reactor vessel flange only one RHR pump/Hx must be operable and in operation.
1.12 Given a set of plant conditions for the Containment and Containment Isolation System, perform the following in accordance with (Technical Specifications, TS Bases, TRM, COLR, PTLR, ODCM): b. Descritbe the basis of any (LCO) and/or Safetv Limit. 55 I Rev.4 1 Level: RO Isolation System d- r 4@#&$wm!:
1 Bank 3 3.9 relationships between the containment system and the following I svstems: Containment isolatiodcontairiment integritv AR-L-4, Safeguard DC I Used on Last (2) NRC ESxams - No IJsed on Audit Exam - No I 2008 Ginna NRC Exam RO Ouestion 56 Which one of the following represents the conditions of the steam entering the PRT from a leaking PORV if pressurizer pressure is 1385 psig and PRT pressure is 5 psig? (Assume an ideal thermodynamic process) a. Saturated steam 225-235 OF. b. Superheated steam 240-250 OF. c. Superheated steam 260-270 OF. d. Saturated steam 275-285 OF.
2008 Ginna NRC Exam Answer: a. b. c. d. RO This is the value if it is determined that the temperature will correspond to the saturation pressure for a PRT pressure of 5 psig plus 15 psi to get 20 psia in the steam tables.
This is the correct value if the line above the 1400 psia line is used on the Mollier Diagram If the Mollier Diagram is used to determine the temperature, the applicant could start with the intersection of 1400 psia and the saturation line.
A reasonable range of enthalpy at this intersection would be 1172-1 175 btu/lbm. Following a constant enthalpy of 1172 btdlbm to the point where it intersects 20 psia (given PRT pressure of 5 psig plus 15 psia) will yield a temperature almost exactly half- way between 240°F and 280°F. Using the Steam Tables would yield a calculated value of 260.1 OF for an enthalpy of 1 172 btdlbm. If the Mollier Diagram is used to determine the temperature, the applicant could start with the intersection of 1400 pia and the saturation line.
A reasonable range of enthalpy at this intersection would be 1172-1 175 btdlbm. If this value is then referenced in the steam table as a saturated gas it will give the temperature as Saturated steam 275-285 OF. c. Superheated steam 260-270 OF. Explanation:
Incorrect Incorrect Correct Incorrect K1.05 - Knowledge of the physical connections and/or cause-effect relationships between the RCS and the following systems: PRT I 2008 Ginna NRC Exam RO Question 57 Plant conditions are as follows: 0 0 0 A unit Startup is in progress.
The Reactor is at 6% power. Main Control Board indications show N'-35, Intermediate Range Detector, has just failed to 1.OE-3 amps. How will the plant respond?
- a. The reactor has tripped, Source Range indications will automatically become available.
- b. The reactor is still at 6% power, N-35 must be bypassed prior to raising power greater than P-10. c. The reactor has tripped, manual action i:; required for Source Range indications to become available.
- d. The reactor is still at 6% power, as long as N-36 remains Operable, all controls will function normally.
11 2008 Ginna NRC Exam Incorrect Incorrect Correct Incorrect RO 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 (2/2 IR 4x10-11 amps) won't be met. The reactor has tripped due to N-35 failing to the top of the IR scale. 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) won't be met. The reactor has tripped due tc) N-35 failing to the top of the IR scale. b. c. d. Answer: c. The reactor has tripped, manual action is required for Source Range indications to become available.
Explanation:
2008 Ginna NRC Exam RO Question 58 Plant conditions are as follows: 0 0 0 0 The reactor has tripped due to a Loss of Coolant Accident. Containment Pressure - 5.5 psig and slowly trending up CET Temperature - 380°F and stable RCS pressure - 500 psig and stable Using the provided Fig - 1 .O, what is the Subcooling Margin in the RCS using the above parameters?
- a. - 80°F Subcooling
- b. 0°F Subcooling
- c. + 35°F Subcooling
- d. + 65°F Subcooling 11 2008 Ginina NRC Exam Correct Answer: values are used. Subcooling Margin derived if' 500 psig RCS press and adverse containment values are used, which are the correct values to use. b. b. 0°F Subcooling Incorrect Explanation: values are used. Subcooling Margin derived if 500 psig RCS press and normal containment values are used. d. RO I Incorrect I a. I Subcooling Margin derived if' 380 psig RCS press and adverse containment I I Incorrect I c. I Subcooling Margin derived if 380 psig RCS press and normal containment I
11 2008 Ginna NRC Exam RO Question 59: Plant conditions are as follows: 0 0 0 Fuel movement is underway in the Containment and Auxiliary Building. Containment Purge is running to support Core Alterations.
It is discovered that the sample pump that supplies R-lOA, Containment Iodine is broken and will not operate.
Which ONE of the following describes how, if at all, fuel movement is affected?
- a. No effect. Refueling operations may continue.
- b. Refueling operations may only continue as long as R-1 1 and R-12 are Operable.
- c. Immediately suspend all movement of irradiated fuel assemblies in Containment and Core Alterations. Refueling operations may only continue after the sample pump is repairedlreplaced and all required testing is completed satisfactorily.
- d. Immediately suspend all movement of irradiated fuel assemblies in Containment and Core Alterations. Refueling operations may continue when Refueling integrity is satisfied.
\I 2008 Ginna NRC Exam Incorrect Incorrect RO a. The pump that supplies R-10A also supplies R-11 and R-12. R-1 1 and R-12 are inoperable, refueling activities must be suspended.
May chose this answer because R- 10A is not a Rad Monitor that will isolate Cnmt Purge. The pump that supplies R- 10A also supplies R- 1 1 and R- 12. R- 1 1 and R- 12 are inoperable, refueling activities must be suspended.
May choose this answer because R-1 1 and 12 will isolde Cnmt Purge but can't due to broken sample Dumn b. Answer: Incorrect Correct d. Immediately suspend all movement of inradiated fuel assemblies in Containment and Core Alterations. Refueling operations may cclntinue when Refueling integrity is satisfied.
- c. This is the correct action but if the Cnmt is isolated it is not required to hold up refueling until the sample pump is repairedheplaced. Refueling may continue when refueling integrity is satisfied per 0-15.1,O-15.2 and ITS 3.9.3. With Containment Purge running and with the sample pump not working (the pump that supplies R-1OA also supplies R-11 and R-12) neither R-11 nor R-12 can provide an isolation signal to close the Cnmt Purge valves therefore per ITS 3.3.5 and 3.9.3 all movement of irradiated fuel assemblies in Containment and Core Alterations must be suspended immediately. Refueling may continue when refueling integrity is satisfied per 0-15.1,O-15.2 and ITS 3.9.3. d. Explanation:
perform the following in accordance with (Technical Specifications, TS Bases, TRM, COLR, FTLR, ODCM):
- a. Identify action statements of less than one hour.
2008 Ginna NRC Exam RO Ouestion 60 Plant conditions occurred as follows: 0 0 0 0 0 0 Operator actions were performed.
The unit was operating at 100% power. Rod control is in Manual. All other Control Systems are in their normal alignment.
One of the Turbine Control Valves disc separated from its stem and failed completely shut. During the transient Tavg spiked to 586°F. Which one of the following describes the proper plant response for these given conditions?
- a. b. C. d. All Steam Dumps will snap open and then the Steam Dumps will throttle close until Tavg is approximately equal to Tref. Four Steam Dumps will snap open and then the Steam Dumps will throttle close until Tavg is approximately equal to Tref. Four Steam Dumps will snap open and tlien the Steam Dumps will throttle close until Tavg is approximately 4°F higher than Tref. All Steam Dumps will snap open and then the Steam Dumps will throttle close until Tavg is approximately 4°F higher than Tref.
I 2008 Ginna NKC Exam Incorrect RO a. This would be the correct response if Rods were in Auto, with rods in Manual there is a 4°F dead band.
1 Answer: Incorrect Incorrect Correct d. All Steam Dumps will snap open and then the Steam Dumps will throttle close until Tavg is approximately 4°F higher than Tref.
- b. C. d. Due to the initial high delta T (>11"F) all the Dump valves will open, with rods in Manual there is a 4°F dead band.
Due to the initial high delta T (>11"F) all the Dump valves will open.
Due to the initial high delta T (>ll°F) all the Dump valves will open, with rods in Manual there is a 4°F dead band.
Explanation:
11 2008 Ginna NRC Exam RO Ouestion 61 Plant conditions are as follows: The unit is at 55% power. All control systems are in their normal at power alignment.
Alarm 1-27, Rotor Eccentrity or Vibration Alarm is lit. Turbine Bearing Vibrations are as follows:
Bearing 1 - 1.2 mils 2 - 1.7 mils 3 - 1.0 mils 4 - 2.7 mils 5 - 4.8 mils 6 - 5.0 mils 7 - 5.5 mils 8 - 6.0 mils 9 - 11.0 mils The correct INTIAL operator response is to: a. b. c. d. Reduce turbine load to stabilize vibration.
Trip the turbine, and perform immediate operator actions for E-0. Trip the turbine, verify power above 1% and verify control rods are driving in to reduce power. Adjust generator hydrogen temp or turbine lube oil temp or exciter cooling to stabilize vibrations.
I 2008 Ginna NRC Exam RO Answer: Incorrect Incorrect Incorrect Correct d. Adjust generator hydrogen temperature
,3r turbine lube oil temp or exciter cooling to stabilize vibrations.
- a. b. c. This would be the correct response if the high vibrations
(>7 mils) were on bearings 1-8. 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. This would be the correct response per AP-TURB.3, Turbine Vibration RNO step 1 if any turbine vibration was >14 mils and power was less than 50 % (CP-9). This is the correct response per AP-TURB.3, Turbine Vibration RNO step 3. d. Explanation: conditions to determine the applicable procedure, and from the procedure determine the appropriate EXPECTED ACTIONS or RESPONSE NOT OBTAINED instructions to implement. (AP-TURB .3). t 2.2.44 - Ability to interpret control room indications to verify the status d how operator actions and Used on Audit 51 2008 Ginna NRC Exam RO Question 62 Plant conditions are as follows: 0 0 0 0 The unit is at 90% power. All systems are in their normal alignment.
Auxiliary Building (AB) Ventilation IMS Switch is in " FILTER IN'. "C" Gas Decay Tank (GDT) is being released.
- 1. Which one of the following is the correct plant response?
and 2. What are the operator actions for that plant response?
- a. 1. If R-13, Auxiliary Building Particulatc:
Monitor, goes into high alarm, "C" Gas Decay Tank 2. Verify the GDT release AOV to the plant vent closes. release is automatically secured.
Ensure 1F AB Exhaust fan is no longer running. Ensure lA, 1B and 1C Intermediate Building Exhaust fans are no longer running.
- b. 1. If R-13, Auxiliary Building Particulate Monitor, goes into high alarm, "C" Gas Decay Tank 2. Verify the GDT release AOV to the plant vent closes. release is automatically secured.
Ensure lA, lB, 1C and 1F AB fans are no longer running.
Ensure lA, 1B and 1C Intermediate EIuilding Exhaust fans are no longer running. c. 1. If R-14, Auxiliary Building Gas Monitor, goes into high alarm, "C" Gas Decay Tank release
- 2. Verify the GDT release AOV to the plant vent closes. is automatically secured.
Ensure 1F AB Exhaust fan is no longer running.
Ensure lA, 1B and 1C Intermediate Building Exhaust fans are no longer running.
- d. 1. If R-14, Auxiliary Building Gas Monitor, goes into high alarm, "C" Gas Decay Tank release
- 2. Verify the GDT release AOV to the plant vent closes. is automatically secured. Ensure lA, lB, 1C and 1F AB fans are no longer running.
Ensure lA, 1B and 1C Intermediate Ehilding Exhaust fans are no longer running.
2008 Ginna NRC Exam RO Answer: c. 1. If R-14. Auxiliary Building Gas Monitor, goes into high alarm, "C" Gas Decay Tank release is automatically secured.
Ensure 1F AB Exhaust fan is no longer running. Ensure lA, 1B and 1C Intermediate Eiuilding Exhaust fans are no longer running.
- 2. Verify the GDT release AOV to the plant vent closes. Explanation:
Incorrect Incorrect Correct Incorrect - a. - b. C. - d. 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. 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. With a high alarm on R- 14 arid the AB 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. lA, 1B and 1C Intermediate Building fans receive trip signals.
With a high alarm on R-14, R.CV-14 (the GDT release AOV to the plant vent) 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. tions, describe the design features of the oring System, to include set points, interlocks, and the related automatic action(s) for the following components, I instrumentation ar.d/or processes.
- c. R-13, R-14 Cat4tgWy:
f Tier 2 / Group 2 Ques4itsorr souree: New Cogdthqlevelt I CIA IXffkafQ Levah 3
, 2008 Ginna NRC Exam RO Question 63 Plant conditions occurred as follows:
0 0 0 0 0 0 While operating at rated power, a major steam leak developed downstream of the MSIVs.
The unit tripped, an automatic Safety Injection (SI) occurred and the MSIVs automatically closed. All systems operated as designed. RCS pressure has recovered and ARVs are controlling Tavg.
The Control Room Team is performing E-0, Reactor Trip or Safety Injection.
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 EjectorlExhaust Radiation Monitor c. R Condenser Air Ejector Radiation Monitor
- d. R Steam Generator Blowdown Radiation Monitor 2008 Ginina NRC Exam Answer: a. R Main Steam Line Radiation Monitor ExDlanation
- RO I Correct I a. I Still available and with flow th the ARV will be the first RM to indicate the 1 (to prevent exceeding design limits) as,sociated with operating the 14 2008 Giniia NKC Exam RO Ouestion 64 Plant conditions are as follows: 0 0 The unit is at 100% power. "B" and "C" Service Water pumps are rmning. "A" and "D" Service Water pumps are selected.
The normal supply breaker to Bus 17 fails open.
How will the plant respond? 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 ortly "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 se,n,onds after the "B" D/G breaker closes.
2008 Ginna NKC Exam Answer: Incorrect Incorrect RO b. c. 17 seconds is if there was a S signal concurrent with an undervoltage condition.
There is no immediate restart There is for CS if it was already running and 17 seconds is if there was a SI siaal concurrent with an undervoltage condition.
- a. "B" Service Water pump will trip and orily "D" Service Water pump will start 40 seconds after the "B" D/G breaker closes.
Explanation:
On an undervoltage the running SW pump will trip and only the selected SW I Correct 1 a* I DumD will start for that train 40 seconds after "B" D/G breaker closes.
1 Incorrect I d. I "B" Service Water pump will trip and not restart because it is not selected.
2008 Giniia 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. 27 1-0 Rly Rm Computer Rm Auto Halon What is the expected condition of the Halon sys tem 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 acixated and Mux room has actuated.
I 2008 Ginria NRC Exam Correct Incorrect Incorrect Incorrect Answer: a. b. c. d. If the system had actuated, would have the following alarms: First Alarm, Second Alarm and Flow Alann. With only the first alarm in the Halon system will not actuate. With only the first alarm in the Halon system will not actuate. With only the first alarm in the Halon system will not actuate. a. Halon system has not actuated.
Exdanation
- RO 2008 Ginria NKC Exam RO Ouestion 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.
I 2008 Ginria NRC Exam Incorrect Incorrect Incorrect Correct RO a. b. c. d. Stem states definition of Night Order, Night Orders are maintained as long as they are applicable or until they are removed by the GS-Shift Operations.
Night Orders are maintained its long as they are applicable or until they are removed by the GS-Shift Operations. Stem states definition of Night Order. Per CNG-OP-1 .O 1-200 1, Conmunications and Briefings per section 5.3 B and D. Answer: d. Night Order, Until removed by the GS-Shift Operations or conditions are no longer applicable.
Explanation:
es and responsibilities for the control room 2.1.15 - Knowledge of administrative r management directives, such as standir Operations memos, etc. Communications and Briefings per section 5.3 2008 Ginna NKC Exam RO Question 67 During the implementation of E-0, Reactor Trip or Safety Injection, which one of the following communications is correct, in accordance with CNG-HU- 1.01- 1001 Human Performance Tools and Verification Practices?
- a. b. C. d. CRS: Bob, Bob: Ready.
CRS: Start an Aux Feed Water Pump. Bob: Start an Aux Feed Water Pump. CRS: That is correct. CRS: Bob, start an Aux Feed Water Pump. Bob: Start an Aux Feed Water Pump. CRS: That is correct. CRS: Bob. Bob makes eye contact with the CRS. CRS: Start "Bravo" Aux Feed Water Pump. Bob: Start an Aux Feed Water Pump. CRS: That is wrong. Start "Bravo" Aux Feed Water Pump. Bob: Start "Bravo" Aux Feed Water Pump. CRS: That is correct. CRS: Bob, start "Bravo" Aux Feed Water Pump. Bob: Start an Aux Feed Water Pump. CRS: That is incorrect. Start "Bravo" Aux Feed Water Pump. Bob: Start "Bravo" Aux Feed Water Purnp. CRS: That is correct.
I 2008 Ginnia NRC Exam Answer: c. CRS: Bob. Bob makes eye contact with the CRS. CRS: Start "Bravo" Aux Feed Water Pump.
Bob: Start an Aux Feed Water Pump. CRS: That is wrong.
Start "Bravo" Aux Feed Water Pump.
Bob: Start "Bravo" Aux Feed Water Pump. CRS: That is correct. Explanation
- Incorrect Incorrect Correct Incorrect - a. b. - - C. d. - RO Does not specify which AFW pump to start. Order should not be put out this way and receiver should not allow order to continue without clarification.
The CRS should get Bobs attention first then deliver his message. Also the message does not specify which AFW pump to start. Order should not be put out this way and receiver should not allow order to continue without clarification.
CRS identifies message was repeated incorrectly and says "wrong" as per CNG- HU-1.01-1001 section 5.7.B.3.e then redelivers the message and ensures it is understood correctlv.
The CRS should get Bobs attention first then deliver his message. Per CNG-HU-1.01-1001 section 5.7.B.3.e, rnust use "wrong not "that is incorrect".
2008 Ginna NRC Exam RO Ouestion 68 Which ONE (1) of the following describes the lUIINIMUM 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 0 b. 1 1 C. 2 d. 2 J. 0 0 1 Answer: Incorrect Incorrect Correct Incorrect
May choose if its believed as long as any (1)
SR is operable and working in the control room area the Refueling requirements are met. 21110 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. This is correct Der ITS 3.9.2 and 0-15.1. 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 11 2008 Ginna NRC Exam RO Question 69 Which one of the following jobs would REOUIRE an Isolated Work 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) . . . a. AC circuit where the maximum voltage is 40 volts AC. b. DC circuit where the maximum voltage is 55 volts DC.
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.
2008 Ginna NRC Exam Answer: Incorrect Correct b. DC circuit where the maximum voltage is 55 volts DC.
- a. b. Per A-1401 a hold is required for
> 50 volts (AC OR DC). Per A-1401 a hold is reauired for
> 50 volts (AC OR DC). Explanation:
Incorrect RO temperature.
Per A-1401 a hold is required for > 50 psig hydraulic pressure and/or > 120°F temDerature.
- d. I Incorrect I c. I Per A-1401 a hold is required for
> 50 psig hydraulic pressure and/or > 120°F 1 2008 Ginna NRC Exam RO Question 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 volume is 275,000 gallons. b. Chemistry reports, Spent Fuel Pool boron concentration is 2400 ppm and there are fuel assemblies in the Spent Fuel Pool. C. During the roll up of the Turbine Generator, the CO reports "A' Loop Tavg is 545"F, "B" Loop Tavg is 535°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 Answer: Incorrect Incorrect Correct Incorrect
- c. During the roll up of the Turbine Generator, the CO reports "A" Loop Tavg is 545"F, "B" Loop Tavg is 535°F and both are trending up slowly.
- a. b. C. d. RWST level is not applicable in Mode 5 per ITS 3.5.4. (Less than a one hour LCO.) Spent Fuel Pool boron concentration minimum limit is 2300 ppm per ITS 3.7.12. (Less than a one hour LCO.) When in Mode 1, BOTH RCS Tavgs must be > 540°F per ITS 3.4.2. (Less than a one hour LCO.) 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.) Explanation:
RO it conditions for the Reactor Coolant System, am source: New Aty tevelt 3 2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
0-1.2, Plant Startup from Hot Shutdown to Full LDad 2008 Ginna NRC Exam RO Question 71 Plant conditions occurred as follows:
0 0 0 0 0 The plant is operating at 90% power. The HCO notes that R-29, Containment High Range monitor indication, rapidly rises to almost full scale and then it lowers back to zero.
One minute later R-30, Containment High Range monitor does the same thing.
No Control Room alarms came in during this period. The HCO reports this to the CRS. Which ONE of the below is correct for this indication?
- a. Write a Condition Report on R-29 and R.-30 and declare them Inoperable per Technical Specifications.
- b. Initiate S-12.2, Operator Action in the Event of Significant Increase in Leakage. c. This is an expected indication, it's an automatic electronic source check. d. Enter AP-RCS. 1, Reactor Coolant Leak.
I 2008 Ginria NRC Exam Answer: c. Explanation:
No action required, this is an automatic electronic source check. Incorrect RO d. Possible indication of a leak i:n the RCS but with no other indications entry into AP-RCS.l is not required. not correct for R-29 and R-30 as this is a every 17.1 minutes.
may lead operators to look for leaks; however, since there are no other indications of leakage entry into S-12.2 would not be Correct - C. required.
Per the first note and caution in S-14.3, Operation of Containment High Range Area Monitors R-29, R-30, &'HEN the monitor is operating normally, THEN the system performs an Electronic:
Check Source (ECS) test every 17.1 minutes. and during the ECS test, all alarms are muted; that is, their operation is disabled until the completion of the test. During this six-second period there is no warning of a high-radiation condition.
2008 Ginna NRC Exam RO Ouestion 72 Plant conditions are as follows: The Reactor is at 2% power. A containment entry is underway to look for a leak identified during the startup.
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 Acid leak coming from the reactor cavity area and going into the "A" sump. They want permission to enter the reactor cavity area and "A" sump to determine the extent of the Boric Acid leak. The contractor RP tech says that he has ii portable radiation monitoring device with him that will cover the expected doses, and they axe both wearing all the required dosimitry. What is the correct response in accordance with A-3, Containment Vessel Access Requirements?
- a. b. c. d. They may not enter either of the areas at this time.
They may enter the "A" sump, but not the reactor cavity area. They may enter the reactor cavity area, but not the "A" sump. As long as the RP tech stays with the mechanic, they can enter both areas.
2008 Ginna NRC Exam Answer: RO a. They may not enter either of the areas at this time.
Explanation:
however Drocedurallv not allowed.
I 2008 Ginna NRC Exam Question 73 Plant conditions are as follows: 0 The Control Room staff is responding to an Orange path on Containment per ER-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 CoreCooling - Red What is the correct action to be taken and why? a. b. C. d. RO Immediately transition to FR-C. 1, Response To Inadequate Core Cooling because efforts need to be made to ensure the fuel cladding remains, intact. Immediately transition to FR-H. 1, Response To Loss of Heat Secondary Sink, because efforts need to be made to ensure the Reactor Coolant System remains intact.
Complete FR-2.1, Response To High containment Pressure, because the Orange path is now a Red 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.
Complete FR-Z. 1, Response To High Containment Pressure, because the Orange path is now a Red path and efforts need to be made to ensure Containment, the last barrier to the public, remains intact, then transition to FR-H. 1, Response To Loss of Secondary Heat Sink.
2008 Ginna NRC Exam Answer: RO a. Immediately transition to FR-C.l, Response To Inadequate Core Cooling because efforts need to be made to ensure the fuel cladding remains intact.
Explanation:
then Loss of Secondarv Heat Sink.
I 2008 Ginnia NRC Exam RO Ouestion 74 Plant conditions are as follows: 0 0 The plant is in a Site Area Emergency.
Due to degrading plant conditions an eniry into containment must b ext 15 minutes to prevent a severe radiation release to the public from occurring and escalating the site to a General Emergency.
RP has determined the volunteer will receive 3500 mrem (TEDE) for the evolution.
0 What is the MINIMUM authorization required to approve the expected exposure in accordance with EPlP 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 made in the d. Emergency Coordinator 11 2008 Ginna NRC Exam Incorrect Incorrect Correct RO a. b. c. Radiation Protection Manager authorization is required. Possible choice due to time issue. Radiation Protection Manager authorization is required. Possible choice due to time issue. Required per EPIP 2-8, Voluntary Acceptance of Emergency Radiation Exposure pg.
- 2. Radiation Protection Manager can authorize up to (4) rem (TEDE). Answer: c. Radiation Protection Manager Explanation:
I Incorrect I d. I Emergency Coordinator approval required for XI rem (TEDE). 2.4.37 - Knowledge of the lines of autk the emergency plan.
11 2008 Ginna NRC Exam Question 75 Plant conditions are as follows: 0 0 The plant is in a General Emergency.
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 communications to the Shift Manager.
- 2. Sound the alarm and make announcements as necessary.
- 3. Advise 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 RO I 2008 Ginna NRC Exam 1 Correct 1 d. RO STA per EPk 5-7, Emergency Organization..
- 6 is the responsibility of the Emergency Coordinator.
Per EPIP 5-7, Emergency Organization pg 33. Answer: d. 2,4,5 Explanation:
1 Incorrect 1 Incorrect Incorrect I # 1 is the responsibility of the C/R Communicator.
- 6 is the responsibility of tht: Emergency Coordinator per EPIP 5-7, Emergency Organization.
- 1 is the responsibility of the C/R Communicator.
- 3 is the responsibility of the ties in emergency plan Organization pg. 26,29,30,33
!I 2008 Ginna NRC Exam SRO Question 76 Plant conditions occurred at the following times:
1330 - While opkrating at rated power, the Following alarms came in: A-6, CONT Spray Pump Cooling Water Out Lo Flow A-7(15), 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, Motor Off RCP CCWP A-22, CCW Pump Discharg2 Lo Pressure 0 0 1331 - Standby CCW 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 and counts are trending up slowly.
Based on the information given, which of the following is/are the correct action(s) to be taken FIRST at 1333? a. b. C. d. Direct entry into AP-CCW. 1, Leak into Component Cooling Loop and verify that the CCW surge tank vent valve has automatically isolated. 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. 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. 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-754M754B).
2008 Ginna NRC Exam Answer: SRO 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:
with no CCW pumps running, tripping the unit and M per Ap-CCW.2 step la RNO, with no CCW nit and RCPs are the priority.
150 degrees F is an alarm ipply temperature to the RCPs (A-8 and A-16). Ah no CCW pumps running tripping the unit and orrect because the AP directs tripping only the procedure determine the appropriate EXPECTED ACTIONS or AA2.10 - Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When AP-ccw.2, Loss of cc during Power Operation 1 Used on Audit Exam - No I 2008 Ginna NRC Exam SRO Question 77 The control room has just been informed by the system engineer that non-quality parts 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. It was discovered these parts were sent by mistake wilh the correct part numbers but were made of substandard material.
Which one of the following applies?
The CCW pumps have passed all surveillances and testing. Declare both CCW pumps "Operable but Degraded".
Immediately initiate action for Engineering to perform an "Operability Determination". Declare both CCW pumps "Inoperable". Immediately enter LCO 3.0.3 due to no other Tech Spec applies and perform shutdown when allciwed by Tech Specs.
Declare both CCW pumps "Inoperable".
Immediately initiate action to restore one CCW train to Operable status within (1) hour. If action not completed after (1) hour be in Mode 3 in (6) hours and Mode 4 in (12) hours when allowed by Tech Specs.
I 2008 Ginina NRC Exam Incorrect Incorrect SRO c. d. There is an ITS for both CCW trains inop. Entry into LCO 3.0.3 is not required.
ITS 3.7.7 does not allow (1) hour to restore a train. Answer: b. Declare both CCW pumps "Operable but Degraded".
Immediately initiate action for Engineering to perform an "Operability Iletermination".
Explanation:
Incorrect Correct a. - b. At a minimum a safety determination should be done, not "no action required".
Even though it passed all its testing and surveillances it is still degraded due to the wrong parts being installed.
Engineering would perform an Operability Determination to verify the pumps could perform their safety furictions 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 Inor>. related equipment.
Determinations/Functionality Assessments pg.
5 S 3.7.7 condition D
2008 Ginina NRC Exam SRO Ouestion 78 Plant conditions occurred as follows: 0 0 The unit was operating at 20% power. An RCS leak has caused Pressurizer pressure to lower to 1850 psig. Power remains near 10% and both Reactor trip breakers still indicate closed.
The operators are performing Step 1 of 13-0, Reactor Trip or Safety Injection. Pressurizer level is 10% and stable. Which ONE of the following describes the comct direction to give the crew? a. Continue with E-0 and manually initiate SI. b. Continue with 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.1, Response to Nuclear Power GeneratiodATWS and DO NOT manually initiate SI.
2008 Ginina NRC Exam SRO Answer: d. Transition to FR-S. 1, Response to Nuclear Power GeneratiodATWS and DO NOT manually a. b. c. d. initiate SI. Explanation:
E-0 steps/actions no longer apply, a crew transition to FR-S.l 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.
The crew must immediately transition to FR-S.l to mitigate the ATWS, E-0 no longer applies while in FR-S.l 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. FX-S. 1 has no instructions/RIVO for manually initiating SI. May chose to perform this action based on IPzr pressure being within 100 psig of the SI set point. Must transition per E-0 step 1 d RNO. No guidance is given in any RNO or procedure step to initial SI, only to verify SI equipment alignment if running. Incorrect Incorrect Incorrect Correct 2008 Ginna NKC Exam SRO Ouestion 79 Plant conditions occurred as follows 0 0 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.
Just before the fire was reported as being extinguished there were numerous alarms, the reactor tripped and there was a complete loss of power to the "B" DC Train. What procedure is entered to restore power to the "B"' DC system and how will it be accomplished?
- a. ER-ELEC.2, Recovery from Loss of A or B DC Train. The TSC Battery will be cross tied to the "B" DC Train and the TSC Diesel will supply the TSC Battery Chargers.
- b. ER-FIRE.2, Alternate Shutdown for Cable Tunnel Fire.
The "B" DC Train Battery chargers will be back fed from the TSC Diesel through Bus 15 and the Bus 15-16 cross-tie.
- c. ER-ELEC.2, Recovery from Loss of A or B DC Train. 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. ER-FIRE.2, Alternate Shutdown for Cable Tunnel Fire.
The TSC Battery will be cross tied to the "B" DC Train and the TSC Diesel will supply the TSC Battery Chargers.
I 2008 Gin na NRC Exam Incorrect Incorrect Incorrect Answer: a. b. c. SRO d. ER-FIRE.2, Alternate Shutdown for Cable Tunnel Fire.
The TSC Battery will be cross tied to the "B" DC Train and the TSC Diesel will supply the TSC Battery Chargers.
Explanation:
Correct d 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. EEL-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. EF:-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. ER-FIRE.2, Alternate Shutdown for Cable Tunnel Fire provides guidance in Att. 8 section 2, to provide long term DC power. The actions are correct per ER- FIRE.2. - Alternative Shutdown 2008 Ginina NRC Exam SRO Ouestion 80 Plant conditions occurred as follows: 0 A Reactor Coolant Leak has been identified in the Auxiliary Building.
0 Efforts to enter the area to isolate the leak have been unsuccessful.
0 The Control Room team has worked their wfay through the EOPs and are about to leave ECA- 1.2, LOCA Outside Containment.
0 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 Coolimt, to continue 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.
I 2008 Ginina 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 Incorrect Incorrect Correct L a. b. - C. d. - 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 recoverv actions.
Per step 7 RNO, of ECA-1.2, if the leak is NOT isolated you are to go to ECA- 1.1 but while it is prudent to continue to look for the leak, ECA- 1.1 is going to address the loss of iriventory, to make the RWST last as long as possible by minimizing its depletion and makeup to the RWST.
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. 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 EMERGENCY COOLANT RECIRCULATION, for further recovery actions since there will be no inventory in the sump.
ECA- 1.2, LOCA OUTS CONTAINMENT pg. 9 2008 Ginna NRC Exam SRO Question 81 Plant conditions are as follows: 0 0 0 0 0 0 0 0 0 0 0 0 The unit tripped from rated power and 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.
"B" 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 slowly 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 I, 2008 Ginitla NRC Exam Incorrect
- a. Correct b. Incorrect c. Incorrect d.
SRO 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. With S/G level and pressure trending down E-2 is the correct procedure to mitigate the given plant conditions.
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. Has all the classic signs of a LOCA and with Rad alarms in various areas it maybe mistaken for a coolant leak.
J Answer: b. E-2, Faulted Steam Generator Isolation Explanation:
it and equipment conditions, evaluate the I 2008 Ginina NRC Exam SRO Question 82 Plant conditions occurred as follows:
0 0 0 0 0 0 The plant is in a Refueling outage.
Core Alterations were in progress.
Fuel movements were taking place in Containment and the Auxiliary Building.
The Refueling SRO reported one of the spent fuel assemblies dropped on to the core and damaged several fuel assemblies.
R-2, Containment Area Monitor is in slim and reading off scale high.
R-29/30, Containment Radiation Monitors are reading 125 lUhr 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 I 2008 Giniia NRC Exam SRO Answer: b. Alert Explanation:
Meets the re uirements of 5.3.1 but conditions are given for an Alert.
Meets the re uirements of 2.3.2 but only applicable in Modes 1-4 not in Mode 6. May select GE due to dropped fuel and rad levels. Incorrect EAL call at this time. Meets rad re uirements for 4.1.6, but 4.1.6 is only applies in Modes 1-4. Correct b. Re uired erEAL2.4.2.
Incorrect
- d. ency action level thresholds and Evaluation and
,I 2008 Gin na NRC Exam SRO Question 83 Plant conditions are as follows:
0 0 0 The reactor is currently at 100% power. The unit has been operating with a Steain Generator Tube Leak (SGTL) of 60 Gallon per Day (GPD) in the "B" S/G for the last three months. Currently doing four hour leak determinations.
PPCS alarm R-47G 2 75 GPD just alarmed. A review of leak trend shows the following:
o 1300 - leak started increasing above 60 GPD o 1301 - 175 GPD o 1302 - 65 GPD o 1310 - 135 GPD o 1311- 75GPD o 1320- 85 GPD o 1330- 90GPD o 1345 - 95 GPD and steady (current time) o All radiation monitors operable imd 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.l, Steam Generator Tube Leak and increase monitoring the "B" S/G to one hour intervals for leakage.
- b. Remain in AP-SG.1, 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-TIJRB.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 Giniia NKC Exam SRO Answer: c. Commence a Load Reduction per AP-TTJRB.5, Rapid Load Reduction because power must be Incorrect reduced to less than 50 % power in the next hour. a. Explanation:
Incorrect
- b. Correct + 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. 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. This is correct if during evaluatiodexecution 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 power to 50% w/I (1) hour. This is correct only if during evaluatiodexecution 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
<150 GPD since leak initiation (due to spike at 1301 - 175 GPD). procedure determi ne the appropriate EXPECTED ACTIONS or Tube Leak pgs. 3-10 Generator Tube Leak 2008 Giniia NRC Exam SRO Question 84 Plant conditions are as follows: 0 0 0 The unit is at rated power.
A liquid radwaste release is in progress. R-18, Waste Liquid Radiation Monitor
'Warning Alarm comes in quickly followed by the High Alarm. Which one of the following describes the action required?
In accordance with the annunciator procedure verify . . . a. b. C. d. RCV-018 is closed, contact an A0 to resample the tank; and refer to EPIP 1- 16, Radioactive Liquid Release to Lake Ontario or Deer Creek.
the tank is recirculating, reverify the lineup is correct, contact an A0 to resample the tank; and refer to EPIP 1 - 1, Unusual Event.
the tank is recirculating, perform a flush of R-18, and refer to EPIP1-0, Ginna Station Event Evaluation and Classification.
RCV-018 is closed, submit an A-52.12 for R-18, refer to the ODCM for operability requirements and contact an A0 to resample the tank.
2008 Ginria NRC Exam SRO Answer: a. RCV-018 is closed, contact an A0 to resample the tank; and refer to EPIP 1- 16, Radioactive Liquid Release to Lake Ontario or Deer Creek.
Exdanation:
Correct Incorrect Incorrect Incorrect - a. b. - C. d. All required per AR-RMS- 18., R- 18 Waste Liquid. Suppose to verify RCV-018 is closed, tank won't 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 inop. Refer to EPIP 1-0 or 1-16 not 1-1. Suppose to verify RCV-018 is closed, tank won't be in recirc as the high alarm also trips the pump.
Referring to EPIP1-0, Ginna Station Event Evalu&on and Classification is not required by the ARP. A-52.12 submittal not required due to R-18 operating correctly and should sample first to prove R-18 is hop. No ODCM entry required.
associated with the waste disposal system, evaluate plant conditions AA2.05 - Ability to determine and interpret the following as they apply 2008 Giniia NRC Exam SRO Question 85 Plant conditions occurred as follows:
0 0 0 The unit was at 80% power when a Loss of Coolant Accident (LOCA) occurred.
The Control Room Team has performed the applicable EOPs and are currently performing E-1, Loss of Reactor or Secondary Coolant. FR-Z. 1, Response To High Containment Pressure is now entered due to a valid Red Path for Containment pressure. What procedure will govern the use of Containment Sprays and why? a. FR-Z. 1, Response To High Containment Pressure, allows maximum available heat removal system capability in order to reduce containment pressure.
- b. E-1, Loss of Reactor or Secondary Coolant, because of a less restrictive criteria, which permits reduced spray pump operation depending on containment pressure and number of emergency fan coolers operating.
- c. FR-Z. 1, Response To High Containment Pressure, because of a less restrictive criteria, which permits reduced spray pump operation depending on containment pressure and number of emergency fan coolers operating.
- d. E-1, Loss of Reactor or Secondary Coolant, allows maximum available heat removal system capability in order to reduce containment pressure.
2008 Ginria NRC Exam SRO Answer: b. E- , Loss o Reactor or Secondary Coolant, because of a less restrictive criteria, w ich permits reduced spray pump operation depending on containment pressure and number of emergency fan coolers operating.
Explanation:
Incorrect
- a. Correct b. Incorrect
- c. Incorrect
- d. This is correct for the procedure and the reason if entry to FR-Z.l was NOT from E- 1 or ECA- 1.1. Since entry was from E- 1, E- 1 is the guiding document for the use of Cnmt Sprays. In the procedure for FR-Z. 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.
FR-Z. 1 allows maximum flow of Cnmt Sprays but since entry was from E- 1 FR- Z. 1 is not the controlling document. Correct procedure per guidance given in FR-Z. 1, but the incorrect reason.
E- 1 tries to conserve the RWST for as long as possible and has a less restrictive criteria, which permits reduced spray pump operation depending on containment 2008 Giniia NRC Exam SRO Ouestion 86 Plant conditions are as follows: The unit has tripped from rated power 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 ECCS systems are running as expec1:ed.
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-878A, SI to RCS injection valve?
and 2. Which ONE of the following lists the correct actions and procedure transitions due to the LOCA and the SI rupture? a. 1. SI Line to RCS Loop "A" - SI flow on FI-925 and pressure on PI-923 would remain stable. SI Line to RCS Loop "B" - SI flow on FI-924 would rise and SI pressure on PI-922 would lower. 2. E-1 to FR-C.2 to E-1 to ES-1.2 to ES-1.3
- b. 1. SI Line to RCS Loop "A" - SI flow on FI-925 would rise and SI pressure on PI-923 would lower. SI Line to RCS Loop "B" - SI flow on FI-924 and pressure on PI-922 would remain stable. 2. FR-C.2 to E-0 to E-1 to ECA-1.1 c. 1. SI Line to RCS Loop "A" - SI flow on FI-925 and pressure on PI-923 would remain stable. 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
- d. 1. SI Line to RCS Loop "A" - SI flow on FI-925 would rise and SI pressure on PI-923 would lower. SI Line to RCS Loop "B" - SI flow on FI-924 and pressure PI-922 would remain stable. 2. E-1 to FR-C.2 to E-1 to ES-1.2 to ES-1.3 2008 Ginna NRC Exam Answer: a. b. SRO 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. monitoring starts, then go to FR-12.2 then back to E- 1, ES- 1.2 and ES- 1.3. ECA- 1.1 will be entered if the leak can't be stopped. Any transition to ECA-1.1 will only happen after ES-1.3 is entered. 1. This would be correct if MOV-8'78A 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. 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 met to go to ECA- 1.1, have SW, CCW, RHR loops 2. Transition out of E-0 to E- 1 prior to start of CSFST monitoring. Once in E- 1 CSFST a. 1. SI Line to RCS Loop "A" - SI flow on FI-925 and pressure on PI-923 would remain stable. SI Line to RCS Loop "B" - SI flow on FI-924 would rise and SI pressure on PI-922 would lower. 2. E-1 to FR-C.2 to E-1 to ES-1.2 to ESS-1.3 Explanation:
-- 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-1 but none of the requirements are met to go to ECA-1.1, have SW, CCW, RHR loops all available and there is a leak ir, the AB but not a coolant leak. Correct Incorrect Incorrect Incorrect L I c. I 1. MOV-878A is a normally closed valve that gets SI flow from the "A" SI pump and delivers it all available and there is a leak ip the AB but not a coolant leak.
I 2008 Ginria NRC Exam SRO Ouestion 87 Plant conditions are as follows: 0 0 The unit has been operating at 100% power for two weeks following a refueling Outage. Engineering has called to inform you of an error that was made when the Pressurizer Safety Valve setpoints were adjusted.
The error was just discovered and Engineering has determined 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 t'alve lift setpoint?
- a. b. C. d. 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.
- 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.
- 1. Restore valve to Operable status within 30 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.
- 1. Restore valve to Operable status withi:n 30 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.
SRO 2008 Ginina NRC Exam Answer: a. 1. Restore valve to Operable statue 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 trm sients except for the RCP locked rotor accident.
Explanation:
Correct Incorrect Incorrect Incorrect - a. - b. C. d. 1. Right time per LCO 3.4.10 action A. 1 2. Per the bases for LCO 3.4. LO: The limit protected by this Specification is the reactor coolant pressure boundary (RCPB) SL of 110% of design pressure for all transients except locked rotor accidents which has an allowed limit of 120% of design pressure.
hoperability of one or more valves could result in exceeding the SL if a trans .ent were to occur.
The consequences of exceeding the ASME pressure limit could include damage to one or more RCS components, increased leakage, or additional stress analysis being required prior to resumption of reaci.or operation.
- 1. Right time per LCO 3.4.10 action A.l 2. Sheared shaft is not the exception given in the bases.
- 1. Only 15 minutes is allowed per LCO 3.4.10 action A.l 2. Sheared shaft is not the exception given in the bases.
- 1. Only 15 minutes is allowed! per LCO 3.4.10 action A. 1 2. Per the bases for LCO 3.4.:10: The limit protected by this Specification is the reactor coolant pressure boundary (RCPB) SL of 110% of design pressure for all transients except locked rotor accidents which has an allowed limit of 120% of design pressure. (Technical Specifications, TS Bases, TRM, COLR, PTLR, ODCM): a. Identify action statements of less than one hour.
- b. Describe the 2.2.40 - Ability to apply technical spec! fications for a system.
2008 Ginria NRC Exam Question 88 Plant conditions are as follows: SRO 0 0 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 note in ITS 3.1.1 required action D.
1 that says, "The inoperable channel may be bypassed for 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", is used to support the I&C surveillance testing on Channel "3" OP-delta T. 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. b. C. d. 1. I&C has (2) hours to fix and retest Channel "3" OP-delta T before the train must be 2. Ensures that the design limit departure:
from nucleate boiling ratio (DNBR) is met. declared inoperable.
- 1. Immediately declare Channel "3" OP-delta T inoperable.
- 2. Ensures that the design limit departure from nucleate boiling ratio (DNBR) is met. 1. I&C has (2) hours to fix and retest Ch;mel"3" OP-delta T before the train must be 2. Ensures that protection is provided to ensure the integrity of the fuel (Le., no fuel declared inoperable. pellet melting and less than 1% cladding failure).
- 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 Ginnia NRC Exam Incorrect Answer: 2. This is the ITS bases for Or-delta T trip set point. 1. The channel no longer meets the surveillance requirements and is therefore
- b. 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).
- d. Explanation:
- 2. This is the ITS bases for Ol?-delta T trip set point. 1. The channel no longer meets the surveillance requirements and is therefore SRO 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.
Incorrect Correct C. inop 2. This is the ITS bases for Or-delta T trip set point.
- 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.
inop. 2. This is the ITS bases for Ol?-delta T trip set point.
2008 Giniia NKC Exam Ouestion 89 Plant conditions are as follows: SRO 0 0 0 The unit has experienced a large break L,oss of Coolant Accident (LOCA). The Control Room team has properly implemented the EOPs as required.
The plant is in Cold Leg Recirculation with the following conditions:
o o o o o o o o "A" RHR pump is running and "B" RHR pump is available.
All of the Containment Recirc Ems have failed to start and won't run. "B" CCW pump is running and "A" CCW pump is 00s. "C" SI pump is running with "A" and "B" SI pumps available.
"A" CS pump is running and "B" CS pump is available.
Total RHR flow is 1500 gpm and stable. Containment Pressure is 48 psig and stable. RHR Suction Temperature is 285°F. The "B" CCW pump has just tripped due to an issue with the breaker and cannot be restarted.
How will the plant respond and what actions will need to be taken based on plant response?
- a. b. C. d. "A' RHR pump will begin to show signs of cavitation, per ES- 1.3, Cold Leg Recirculation start another CS pump to provide more flow through the RHR pump and to lower containment pressure. RHR suction temperature will begin to rise, per ECA- 1.1, Loss of Emergency Coolant Recirculation, start the "B" RHR pump and raise RHR flow.
"A" RHR pump will begin to show signs, of cavitation, per ECA- 1.1, Loss of Emergency Coolant Recirculation, lower RHR flow to correct the RHR pump cavitation issue. RHR suction temperature will begin to rise, secure the running CS pump per ES-1.3, Cold Leg Recirculation due to limitations on the CS pump.
2008 Ginna NRC Exam Answer: Incorrect SRO a. d. RHR suction temperature will begin to rise, secure the running CS pump per ES-1.3, Cold Leg Recirculation due to limitations on the C\S pump. Explanation:
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. ES-1.3 calls for the running CS pump to be secured due to RHR suction temp rising.
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 With 48 psig in Cnmt and RHR lined up to the B sump there will be NO indications of cavitation but ii is plausible with loss of CCW for the student to think RHR will cavitate.
The action to correct the cavitation is similar to the actions taken when the RCS loops are drained and RHR cavitation occurs. 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. A2.07 - Ability to (a) predict the impacts of the following 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 spray pump suction when in recirculation mode, possibly caused by Att 28.0, Att Cnmt Spray 2008 Ginria NRC Exam SRO Question 90 Plant conditions are as follows: 0 0 0 0 0 The plant is in Mode
- 3. Tavg is 547°F and stable. RCS pressure is 2235 psig and stable. STP 12.2, Emergency Diesel Generator "B", monthly surveillance test is underway.
"B" D/G has been loaded per the surveillance procedure for about 30 minutes. At this time, all of Off-site power is lost coincid.ent with a large break Loss of Coolant Accident.
What is the expected plant response if all equipinent operates as designed and what actions must be directed in response to the loss of Off-site power coincident with the LOCA? a. Initially, the voltage and frequency of Emergency Diesel Generator "B" will be high 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. Initially, the voltage and frequency of Emergency Diesel Generator "B" will be high. Per STP-0-12.2, adjust voltage as required to achieve 480 volts.
When load sequencing is completed, place the UNITPARALLEL switch to UNIT and adjust frequency to 60.0 HZ. c. Initially, the Emergency Diesel Generator "B" output breakers to Buses 16 and 17 will open.
Per AP-ELEC.14/16 and AP-ELEC.17/18, place the UNITPARALLEL switch to UNIT first, and then close the DIG supply breakers to Buses 16 and 17. Then adjust voltage as required to achieve 480 volts and adjust frequency to 60.0 HZ. d. Initially, the Emergency Diesel Generator "B" output breakers to Buses 16 and 17 will open. 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.
2008 Ginria NRC Exam Incorrect Correct Incorrect Incorrect SRO 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 1
- he UNITFARALLEL switch be placed in UNIT. As per Att. 2 of STP-0-12.2, Emergency Diesel Generator "B". Breakers will not open, entry into AP ELECT.14116 or 17/18 is not required. Breakers will not open, entry into AP ELECT.14/16 or 17/18 is not required.
- b. c. d. Answer: b. Initially, the voltage and frequency of Emergency Diesel Generator "B" will be high.
Per STP-0-12.2, adjust voltage as required to achieve 480 volts. When load sequencing is completed, place the UNITFARALLEL switch to UNIT and adjust frequency to 60.0 HZ. Explanation:
indamental principle, performance test, limits for the Diesel Generator System or component, or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of STP 12.2, Emergenc!
2008 Ginnia NRC Exam Question 91 Plant conditions are as follows: 0 0 0 The unit is at 90% power.
All control systems in there normal aligrunent, and no equipment is out of service. The following annunciators come in: o F-28, Pressurizer High Level Chime1 Alert 87% o F-4, Pressurizer Level Deviation
-5 NORMAL +5 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 Control 2. Enter AP-RCS.
1, Reactor Coolant Leak. Valve, causing HCV- 142 to throttle closed.
- d. 1. LT-428 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.
2008 Ginria NRC Exam Answer: Incorrect Correct SRO c. d. 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.
1 is not required. The controlling channel, LT-4.28 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. 1 will provide guidance to cope with the instrument failure. d. 1. LT-428 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. Explanation:
Incorrect Incorrect - a. - b. Steam space leaks will result 1.n 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. 1 is needed but if it were a leak it would be the correct AP to enter. The controlling channel, LT-4.28 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. iat a loss or malfunction in the Pressurizer Level ertation will have on related plant system(s) and/or e impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use e malfunctions or operations: Failure of PZR level instrument - rocedures to correct, control, or mitigate the consequences of Level Channels pgs.
7,8.9 ER-INST. 1, Reactor Protection Bistable Defeat after Instrumentation Loo 2008 Ginria NRC Exam SRO Question 92 Plant conditions occurred as follows:
0 0 0 0 The unit is at 80% power. All control systems in their normal alignment.
PI-429, Pressurizer Pressure transmitter
- ailed last shift and its required Technical Specification actions have been completlzd while awaiting repairs.
PI-449, Pressurizer Pressure instrument (output signal is interrupted due to a ground and fails low.
What is the plant response and what procedure is entered in response to plant conditions?
- a. Low Pressurizer pressure Safety Injection, Enter E-0, Reactor Trip or Safety Injection.
- b. OP Delta T runback with Rod Stop channel alert, enter AP-TURB.2, Turbine Load Reduction.
- c. Low Pressurizer pressure Reactor trip, Enter E-0, Reactor Trip or Safety Injection.
- d. OT Delta T runback with Rod Stop channel alert, enter AP-TURB.2, Turbine Load Reduction.
2008 Ginnia NRC Exam Incorrect SRO a. No SI signal, SI signals (2/3 L,OGIC) come from PI-429,430,431. Correct Drocedure to enter based on SI. Answer: c. Low Pressurizer pressure Reactor trip, Enter E-0, Reactor Trip or Safety Injection..
Explanation: alert however there will also tie a Reactor Trir, which reauires entrv into E-0.
erations.
- a. Real A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those 2008 Giniia NRC Exam SRO Question 93 Liquid Radwaste discharges are governed by Technical Specifications section 5.5.4, Radioactive Effluent Controls Program which conforms to (1) for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents (2) The program shall be contained in the C3) and shall be implemented by procedures.
- a. 1. lOCFR50
- 3. ODCM c. l.lOCFR100
- 3. ODCM 2008 Ginna NRC Exam Incorrect Answer: a. Exposure is ALARA, < 25 mRem TEDE per year is the limit for exposure due to all site releases and from uranium cycle sources, per 1.3 of the ODCM. The Drogram is contained within the ODCM not the TRM. SRO Correct Incorrect
- b. 1. 1OCFR50 2. as low as reasonably achievable
- 3. ODCM b. As per ITS section 5.5.4: This program conforms to 10 CFR 50.36a for the control of radioactive effluenfs and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable.
The program shall be contained in the ODCIM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded.
10 CFR 100 are the accident limits which is incorrect but plausible. Exposure is ALARA, < 25 mRem TEDE per year is the limit for exposure due to all site releases and from uranium cyde sources, per 1.3 of the ODCM. c. ExDlanation
- Incorrect The program is contained within the ODCM not the TRM. 10 CFR 100 are the accident limits which is incorrect but plausible.
- d. , ODCM): a. Describe the basis of Radioactive Effluent 2008 Ginria NRC Exam SRO Question 94 The following conditions exist:
0 0 0 0 0 The plant is in mode 4. It is Labor Day, dayshift.
The shift crew composition is at minimu.m shift manning due to the Holiday.
The CO becomes seriously ill and must be taken to the hospital.
There are four hours left until shift change. As the Shift Manager, 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 three hours. d. Shift turnover occurs before action is required. Action should be taken to find a replacement, but is not required.
2008 Ginria NRC Exam Incorrect Correct Incorrect
Incorrect SRO a. b. c. d. ITS requires that immediate alstion 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 />. ITS requires that immediate atstion 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 />. 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 />. 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 />. Answer: b. Immediate action must be taken to obtain a replacement reactor operator within a maximum of two hours.
Explanation: lanual, Operations Section Duties, Shift 2008 Ginria NRC Exam SRO Ouestion 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 f'x Physics Testing are in effect. 0 Plant conditions are as follows:
o Pressurizer pressure - 22 10 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 within 30 minutes.
2008 Ginria NRC Exam Incorrect Incorrect Answer: a. ITS 3.1.8 Action B. 1 requires the Rx trip breakers to be opened immediately if thermal power is not within th.e limit (limit is e or = to 5% RTP). With the requirement to lower power less than the limits lends credibility.
Tavg is allowed to be as low as 530°F during Physics Testing so the limit is not b. c. Immediately open the Reactor trip breakers.
Correct Incorrect Explanation:
-- violated however the time allowed to restore the parameter isthe same as listed in 3.4.2, RCS Minimum Temp for Criticality. As per ITS 3.1.8 Action B. 1 P:x trip breakers to be opened immediately if thermal power is not within th.e limit (limit is e or = to 5% RTP). Pzr pressure is lower than normal but within the required band. The time allowed to restore the parameter is the same as listed in 3.4.3, RCS Press and Temp c. d. SRO 2008 Ginria NRC Exam Ouestion 96 Plant conditions are as follows:
0 0 0 0 The unit is at rated power.
You are standing watch as the CRS. It is about 1900 on a Tuesday. You have just been requested to review a Condition Report (CR) that requires corrective maintenance that is for the loss of the "Pl' Diesel Generator which has placed the unit in a (7) day shutdown LCO.
The CR was forwarded to you because the Shift Manager (SM) is in a meeting. 0 What are your actions and when can the maintenance start?
- a. b. C. d. You can perform an initial review however the SM must approve.
Then per CNG-MN-4.01-1001, Work Order Execution and Closure Process, once the maintenance work package is completely written and approved the corrective work can start.
You can perform an initial review however the SM must approve.
Then per CNG-MN-4.01-1002, Work Order Screening and Prioritization, the corrective work can start immediately and the work package can be put together and approved while the work is being done. You as the CRS can complete the review. Then per CNG-MN-4.01-1001, Work Order Execution and Closure Process, the corrective work can start immediately and the work package can be put together and approved while the work is being done. You as the CRS can complete the review Then per CNG-MN-4.01- 1002, Work Order Screening and Prioritization, once the maintenance work package is completely written and approved the corrective work can start.
2008 Ginna NRC Exam SRO Answer: d. You as the CRS can complete the review Then per CNG-MN-4.01- 1002, Work Order Screening and Prioritization, once the maintenance work package is completely written and approved the corrective work can start Explanation:
Incorrect Incorrect Incorrect Correct - a. - b. C. d. SM approval is not required. CNG-MN-4.01-1002, Work Order Screening and Prioritization allows any SRCl 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 screlxing however the work is Pri-2.
SM approval is not required. CNG-MN-4.01-1002, Work Order Screening and Prioritization allows any SRCl to review the CR if the SM is unavailable.
As a 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
-- Main&nance screening however the work is Pri-2.
The CRS can review the CR in the absence of the SM. As a priority-2 work package must be completed b'efore work begins per, CNG-MN-4.01-1002, Work Order Screening and Prioritiz.ation.
2008 Ginira NRC Exam SRO Ouestion 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. RCSIPressurizer Pressure - 1850 psig arLd lowering.
Both S/G Pressures - 500 psig and lowering.
Both S/G Water Levels - 6% Narrow Rznge and slowly lowering.
Both MSIV's are closed.
Both MW's are tripped. Both MDAFW pumps are running and delivering -220 gpm each.
TDAFW pump is running. CTMT Pressure is 0.3 psig and stable. As the CRS, what procedures will be utilized to mitigate this event and what major action will be directed to mitigate the impact on the reactor?
- a. b. C. d. E-2, Faulted Steam Generator Isolation, then ECA-2.1, Uncontrolled Depressurization of Both Steam Generators. Isolate the TDAFW pump and Reduce AFW Flow to 50 gpm to each Steam Generator to minimize RCS cooldown.
E-1, Loss of Reactor or Secondary Coolimt, then ECA-2.1, Uncontrolled Depressurization of Both Steam Generators. Isolate the TDAFW pump and Reduce PFW Flow to 50 gpm to each Steam Generator to minimize RCS cooldown.
E- 1, Loss of Reactor or Secondary Coolimt, then ECA-2.1, Uncontrolled Depressurization of Both Steam Generators.
Control AFW Flow to maintain narrow I'ange level between 7% and 50% in both Steam Generators to ensure maintenance of the secondary heat sink.
E-2, Faulted Steam Generator Isolation, then ECA-2.1, Uncontrolled Depressurization of Both Steam Generators.
Control AFW Flow to maintain narrow mnge level between 7% and 50% in both Steam Generators to ensure maintenance of the secondary heat sink.
2008 Giniia NRC Exam Answer: SRO a. E-2, Faulted Steam Generator Isolation, then ECA-2.1, Uncontrolled Depressurization of Both Steam Generators.
Isolate the TDAFW pump and Reduce A.FW Flow to 50 gpm to each Steam Generator to minimize RCS cooldown.
Explanation:
Correct Incorrect Incorrect Incorrect - a. - b. C. - d. - 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 lo wering (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 TDAFP Steam supply and close the pump flow control valves then reduce Feed Flow to 50 gprn in each S/G due to the cooldown rate being
> 1 OO'Fkr. Procedure routing is incorrect.
'I'he 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 cooldo wn. The action given is correct. 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 cooldo wn. The action given would also result in continued cooldown. 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.
2008 Ginna NRC Exam Ouestion 98 YOU as the Shift Manager, are authorizing a Gas Decay Tank Release. The release must be initiated within (1) no additions to the tank since the sample was drawn. hours of the tank sample time with If the release is not initiated within the required time limit, authorize the release. (2) is required to a. b. C. d. 1. 12 2. Chemistry Supervisor permission
- 1. 12 2. resampling
- 1. 24 2. Chemistry Supervisor permission 1.24 2. resampling SRO 2008 Ginna NRC Exam Incorrect SRO require resampling.
The SM or others may choose to do so but is not required.
As required per CH-RETS-GDT-REL, Gas Decay Tank Release limitation 7.1 c. Answer: Incorrect
- a. 1.12 2. Chemistry Supervisors Permission 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 />. This was correct prior to the xecent 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 or others may choose to do so but is not required.
- d. Explanation: 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 1:ank. (Chemistry) Supervisor's permission is within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. change. The procedure does not 1 RO2008GinnaNRC I @ie& on#: 1 98 I Rev.4 I Level: SRO lntrol Administrative Procedures )ilities of the following positions with respect to I CH-RETS-GDT-REL, Gas I 2008 Ginina NKC Exam SRO Question 99 Plant conditions occurred as follows:
0 0 0 The unit was operating at 100% power with a mini-purge in progress.
A reactor trip occurred coincident with
- i loss of off-site power. 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 R/hr. o R14onalarm.
o R14A7 is reading 2 uci/cc. o Meteorological conditions are: e:* 33 ft temp 65 degrees E; +:* 250 fi temp 66 degrees F 4 Wind direction 135 degrees Q 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 Incorrect Incorrect SRO a. b. Correct if using att.
2 instead of att.1. Correct if wind direction used is 325 degrees (180 degrees out from 135 degrees) and usinn att.
- 1. Answer: c. evacuation of ERPA W-1. Explanation:
Correct Incorrect
- c. d. Correct PARS per EPP-2.1 and using att.
- 1. Correct if wind direction used is 325 degrees (180 degrees out from 135 degrees) - I I I and if using att. 2 instead of att. 1. I n, Implementation, & Notification ons required at each of the four emergency Recommendations pgs. 3,7,8 2008 Giniia NRC Exam SRO Question 100 Plant conditions are as follows:
rn rn e rn e rn rn e rn e e The unit has experienced a Reactor Trip and Safety Injection due to a Loss of Coolant Accident (LOCA).
RCS pressure is 800 psig. Containment pressure is 10 psig and slowly rising. No RCPs are running. (4) CETs are reading 1250°F and the reinaining CETs are reading 680°F. RVLIS level is 45%. All S/G narrow range levels are off-scale low. Unable to start the MDAFW pumps and the TDAFW pump. All SI pumps have tripped on overload. MOV-896B, RWST outlet to SI and CS pumps, was found closed and is now open.
The Control Room Staff is performing El, Loss of Reactor or Secondary Coolant. Given these plant conditions, which ONE of the following 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.l, 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 Answer: Correct Incorrect Incorrect Incorrect SRO a. 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. It is reasonable to believe that the SI pumps would 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.l is not the correct procedure to implement at this time. 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 cooling. 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.
- b. c. d. a. Transition to FR-H. 1, Response to Loss Of Secondary Heat Sink, attempt to start SAFW pumps. Exdanation
- procedure determine the appropriate EXPECTED ACTIONS or F-0.2 and 3 (both pg. 2)