ML081690630
| ML081690630 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/24/2008 |
| From: | NRC Region 1 |
| To: | Calvert Cliffs, Constellation Energy Group |
| Shared Package | |
| ML073040307 | List:
|
| References | |
| TAC U01633 | |
| Download: ML081690630 (134) | |
Text
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 1
ID: Q50399 Points: 1.00 Which of the indications listed below is the ONLY indication we will ALWAYS get for a reactor trip (other than DSS) when all systems are functioning normally?
A.
Matrix relay status lights - out.
B.
Protection Channel Trip Alarm.
C.
Red Trip light on one trip unit.
D.
CEDS NO CONTR VOLT Answer:
A Answer Explanation:
For any RPS Trip the Matrix relay status lights must be out, as this is how the TCB UV coils are denergized and the SHunt trip energized.
A protection Channel Trip Alarm will be in for most automatic trips, but if a manual trip is inserted using the PB on 1 C05 or 1 C15 below 14%, you will not have a protection channel trip alarm Red Trip Light on one trip unit, only if you have had a trip signal for that unit's sensors.
For manual trip this will not occur, subject to discussion above about protection channel trip alarm.
CEDS NO CONTR VOL alarm is in when you loose DC voltage for CED control movement, not trip path related KA Number:
41 007EA205 Comments:
Bank Question Q18653 References, ALM Manual for 1 c05-Page 9-1 0, page 73, also RPS lesson plans LOI-058-1-2 ( Part 1) slides 39, 50, 62-67, 69,71 OPERATIONS Page: 1 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam SRO Importance:
KA Number:
Comments:
2 ID: Q50402 Points: 1.00 3.5 2.2.21 Modified from LOR Q37769 Unit-1 is in Mode 5. The Service water system is aligned for reduced load. 11 Service water Pump has been returned from maintenance. A breaker operability check has been performed, but no STP has been completed. 12 Service Pump handswitch is in Pull-To-Lock.
Which pump(s) can be credited for the Minimum Essential Equipment List (MEEL)?
A.
Both 11 and 12 Service Water Pumps B.
11 Service Water Pump only C.
12 Service Water Pump only D.
Neither pump can be credited.
Answer:
A Answer Explanation:
Per NO-1 -1 03 definition of available - IF the SSC can be placed in service in a functional or operable state by manual or automatic actuation it is available, or if it can be made ready for use within a short enough time to meet the intended use even if is not operable per technical specifications. SO both 1 1 & 12 Service water pumps can be made ready for use within a short period of time 1
References:
NO-1 -1 03 page 7 I
24 March 2008 OPERATIONS Page: 2 of 37
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 3
ID: (220393 Points: 1.00 A Unit-1 plant cooldown is in progress with the following conditions:
-Plant was shutdown 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> ago following an extended full power run
-Shutdown cooling is in service using 11 LPSl pump
-RCS temperature is 180 O F
-RCS pressure is 120 PSlA with a bubble in the pressurizer
-A component cooling leak has developed which will render both SDC heat exchangers unavailable Which of the following options should be taken to control RCS temperature?
A.
Allow RCS to heat up, then control RCS temperature by bleeding steam from the Steam generators Verify RCS pressure is less than 170 PSlG and align a Containment Spray pump for shutdown cooling Start a HPSl pump and open the PORVs to provide core cooling via RCS blowdown to containment B.
C.
D.
Start a charging pump and open the PORVs to provide core cooling via RCS blowdown to containment Answer:
A Answer Explanation:
Allow RCS to heat up, then control RCS temperature by bleeding steam from the Steam generators-correct, per AOP-3B.
Verify RCS pressure is less than 170 PSlG and align a Containment Spray pump for shutdown cooling-incorrect, this alignment still relies on the SDC heat exchangers are required for heat removal.
Start a HPSl pump and open the PORVs to provide core cooling via RCS blowdown to containment--incorrect, this results in needless containment contamination when S/Gs are available.
Start a charging pump and open the PORVs to provide core cooling via RCS blowdown to containment-incorrect, in addition to contaminating containment, this will not provide adequate cooling until greater than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown.
OPERATIONS Page: 3 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam Comments:
Bank question (220393 Used 7/2002 NRC exam
References:
AOP-36, pages 43-60 4
ID: (250407 Points: 1.00 U-1 is operating at 100% power when a loss of #11 125 volt DC bus occurs. Which of the following sets of statments are correct for these conditions:
A.
1 1 A and 1 1 B RCP breakers are tripped locally, 12A and 12B are secured from the Control Room, No feedwater is available, RCS heat input must be reduced
- 6.
11 A and 12A RCP breakers are tripped locally, 1 1 B and 12B are secured from the Control Room, No feedwater is available, RCS heat input must be reduced C.
11 A and 11 B RCP breakers are tripped locally, 12A and 12B are secured from the Control Room, to protect them from possible damage D.
1 1 A and 12A RCP breakers are tripped locally, 11 B and 12B are secured from the Control Room, to protect them from possible damage Answer:
D Answer Explanation:
D is correct per AOP-7J XI. A.1.c, d.--Unit-1 rev. 19, and basis.
OPERATIONS Page: 4 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam Question 4 Info I Question TvDe:
I Status:
MultiDle Choice I
Active Nn No 1.oo 5
3.7 I
4.1 1
42058AA201 Modified from Q 39067 Reference AOP-7J XI. page 59-61 and AOP7J Basis page page 18 OPERATOR ACTIONS FOR LOSS OF 120 VOLT DC BUS Page: 5 of 37 24 March 2008 OPERATIONS
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 5
ID: Q50409 Points: 1.00 U-1 is operating at 100% power when an event occurs and the following Alarms are noted:
0 0
CNDSR HOTWELL LVL CONDS PPS DISCH PRESS LO The appropriate AOP is entered and actions taken. A Reactor trip occurs and EOP-0 was entered and the proper Optimal recovery procedure is now being implemented when the following indications are noted:
0 MOTOR SYS NO FLOW TURB SYS NO FLOW 0
11 S/G e -380 inches 0
12 S/G - 300 inches CET temperature 562 "F Tcold rises from 550°F to 558°F in 30 seconds Which of the following is correct for the conditions given:
A.
Initiate Once-through core cooling because 11 S/G is less than -350 inches B.
Initiate Once-through core cooling because both S/G are less than - 300 inches with NO main or aux feed C.
D.
Initiate Once-through core cooling because CETs are greater than 560°F Initiate Once-through core cooling because Tcold has risen 5°F uncontrollably Answer:
D Answer Explanation:
A is incorrect because it is only one S/G. Both must be less that -350".
B is incorrect because level is greater than -350.
C is correct per Step J.2 C is incorrect because it is not a requirement for initiation of OTCC although it is best to initiate OTCC prior to this temperature to ensure its success in cooling the core.
D. Initiate Once-through core cooling because Tcold has risen 5°F uncontrollably -
correct per step J.2 of EOP Basis: OTCC
References:
EOP-3 rev. 2 step J.2 Initiate OTCC if both S/Gs are less than -350" or Tcold rises uncontrollably 5 degrees F or greater.
Page: 6 of 37 24 March 2008 OPERATIONS
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam I Question 5 Info I
Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Comdete:
~
Multiple Choice Active No No 1.oo 3
RO Importance:
SRO Importance:
KA Number:
I Comments:
3.5 3.6 2446 New
References:
EOP-3 pages 22 -24 and EOP-3 basis pages 31 -33 6
ID: (250493 Points: 1.00 Upon receiving a Gaseous Waste Discharge (0-RE-2191) high rad alarm,(l) what automatic action@) occur, and (2) what immediate followup action is needed?
A.
(1) Shuts waste gas discharge CVs, O-WGS-2191 and 21 92; (2)manually shut waste gas discharge header flow control valve, O-WGS-2191 -PCV.
B.
(1) Shuts waste gas discharge CVs, 0-WGS-2191 and 2192; (2) Monitor WGST for reduction in pressure.
C.
(1) Shuts waste gas discharge header flow control valve, 0-WGS-2191 -PCV; (2) purge waste gas discharge header.
D.
(1) Shuts waste gas discharge header flow control valve, O-WGS-2191-PCV;(2) manually shut waste gas discharge CVs, 0-WGS-2191 and 2192.
Answer:
A Answer Explanation:
Per alarm actions for D-1.1 O-WGS-2191-PCV must be shut as soon as possible to prevent lifting the Waste Gas discharge header relief from going to the waste gas surge tank. ( ALM Manual 1C-22 Window D-l,l)
OPERATIONS Page: 7 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam Cross Reference Number: -
1 Topic:
I KA Number:
Comments:
Multiple Choice Active No No 1.oo 3
2.00 Q50493 Upon receiving a Gaseous Waste Discharge (0-RE-21 91 )
high rad alarm what automatic action occurs an 2.6 3.4 42060AA204 Modified from Bank question LOI-077-1
References:
ALM manual for 1 C22 pages 102-1 03 Basis: Gaseous Waste Discharge High Rad Alarm Automatic Action OPERATIONS Page: 8 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 7
ID: Q50403 Points: 1.00 Each answer lists two activities. Choose the answer where BOTH of the activities would be considered a NO-1-103 HIGHER RISK EVOLUTION. (Fuel is in the vessel.) Consider each activity separately.
A.
- 1. RCP seal replacement requiring reduced inventory.
- 2. Steam generator replacement.
B.
- 1. RCP seal replacement requiring reduced inventory.
- 2. Refueling operations.
C.
- 1. S/G nozzle dam installation.
- 2. Performing LLRT on the common SDC suction piping containment penetration.
D.
- 2. Refueling operations.
Answer:
C Answer Explanation:
Higher risk is defined as a plant configuration or condition during shutdown where the plant is more susceptible to an event causing the loss of a key safety function. If a contingency plan cannot provide comparable equipmenVrneasures to the original Defense-in-Depth then the evolution is a Higher Risk Evolution. Typically, our higher risk evolutions are anything which puts us in reduced inventory and anything which secures all of SDC (i.e. LLRT or common suction header maintenance).
A is incorrect because Steam Generator replacement is not higher risk B is incorrect because refueling operations are not higher risk.
C is correct because nozzle dam installation requires reduced inventory and LLRT on the common SDC suction piping containment penetration requires securing all of SDC.
D is incorrect because refueling ins not higher risk 24 March 2008 OPERATIONS Page: 9 of 37
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam Each answer lists two activities. Choose the answer wh 8
ID: Q50496 Points: 1.00 Which one of the following conditions would require the implementation of EOP-8?
A.
Reactivity Control safety function cannot be met in EOP-0 due to no power available to CEA indications.
B.
Reactor trips on S/G low level, and the EOP-0 flowchart recommends EOP-6 implementation.
C.
EOP-5 is implemented and the intermediate Safety Function Acceptance Criteria is not being met.
D.
The EOP-0 flowchart recommends implementing both EOP-2 and EOP-6.
Answer:
C Answer Explanation:
Reactivity Control is incorrect, EOP-0 accepts this condition for not meeting Reactivity.
Trip on S/G Low level, but flowchart recommends EOP-6 is incorrect, a single event diagnosis is possible.
Intermediate acceptance criteria not being met is correct, EOP-8 would be implemented if the Intermediate Safety Function is not met.
Flow chart recommends 2 EOPs. Optimal recovery procedure for EOP-5 incudes the effec of a loss of Offsite power (EOP-2)
References EOP-8 basis, I l l Entry Conditions), EOP-5 basis 24 March 2008 OPERATIONS Page: 10 of 37
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam Question 8 Info Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
Svstem ID:
User-Defined ID:
Cross Reference Number:
Topic:
RO Importance:
SRO Importance:
KA Number:
Comments:
No Nn 2
I implementation of EOP-85 3.5 4.0 44E09EA22 Modified from bank question 25083 References :EOP-5 page 7, EOP-0 pages 19-23.
Lesson Plan LOI-201-8-8 Slides 23 -26 OPERATIONS Page: 11 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 9
ID: Q50432 Points: 1.00 Unit 2 is operating at 100% power when the following are noted:
0 0
0 0
0 0
22B RCP Seal TEMP HI PRESS Alarm RCP CBO Temp HI Alarm 228 Middle Seal Pressure = - 1050 PSlA 22B Upper Seal Pressure = - 1040 PSlA VCT Pressure = 50 PSIG 22B Seal Bleed-off temperature = 185°F 22B Seal bleed-off flow = Zero Which of the following directions should be given to the CRO and RO?
A.
Commence an expeditious plant shutdown per OP-3, when the Rx is shutdown secure 228 RCP B.
Implement AOP-2A1 trend the remaining seals, contact the System Manager immediately C.
Trip Unit 2 Reactor, implement reactivity portion of EOP-0 plaque, secure 228 RCP, complete EOP actions D.
Trip Unit 2 Reactor, secure 22B RCP, complete EOP actions Answer:
B Answer Explanation:
Implement AOP-2A, contact the System Manager immediately is correct per ALM manual Trip the reactor is action for seal bleed off > 200°F Expeditious shutdown is for 2 failed seals, the Alm manual does not count the vapor seal as one of the 2 seals, even though with zero flow it appears that the vapor seal has failed.
If a trip is required then, the rx is tripped, reactivity is performed then the pump is tripped Reference Alarm Manual 2C06 - Window E-51 OPERATIONS Page: 12 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam
References:
Alarm Manual 1 C06 pages 96-99 OPERATIONS Page: 13 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 10 ID: Q50404 Points: 1.00 A large break LOCA has occurred on Unit-2 and all RCPs have been tripped. The RO is attempting to verify subcooled natural circulation and reports the following:
Pressurizer Pressure is 150 PSlA being maintained by HPSl & LPSl flow RCS Subcooling based on CETs is 5°F Which one of the following set of conditions is the minimum needed to ensure adequate core cooling?
A.
HPSl and LPSl flow appropriate for current RCS pressure AND Thot - 425°F B.
HPSl and LPSl flow appropriate for current RCS pressure AND Thot - 405°F C.
HPSl and LPSl flow appropriate for current RCS pressure AND Thot - 388°F D.
HPSl and LPSl flow appropriate for current RCS pressure AND Thot - 360°F Answer:
B Answer Explanation:
Need to recognize that with CETs at 5°F subcooling, subcooled natural circulation is not being met.
Per EOP-5 Block Step IV. N 2, for verifying subcooled natural circulation, if natural circulation subcooling is not being met, then need to ensure no more than 50" superheat to ensure adequate core cooling.
Since RCS pressure is 150 PSlA the minimum conditions for providing at less than 50°F superheat HPSl and LPSl flow appropriate for current RCS pressure AND Thot - 405°F - Correct would give e 50°F superheat (Sat temp for 150 PSlA = 358.4"F) 360°F would provide e 50°F but the question asked the minimum conditions to give < 50" superheat 388°F would provide e 50°F but the question asked the minimum conditions to give c 50" superheat 425°F would not provide c 50°F OPERATIONS Page: 14 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam I
Reference:
EOP-5, page 40, EOP-5 basis pages 49-52 I
OPERATIONS Page: 15 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 11 ID: (250450 Points: 1.00 Using provided reference(s):
U-1 is at power with PT-102B out of service, the affected RPS bistables were bypassed to remove the tripped condition. During the shift PT-102D began to act erratically resulting in its associated RPS bistables tripped. (a.)What is the effect on RPS immediately after PT-102D bistables tripped, and (b)what actions are required to continue operation at power ?
A.
(a.) The RPS is in a 1 of 2 logic condition to trip. (b.) Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of declaring PT-1020 inoperable, restore either PT-102B or PT-102D to operable status and maintain the RPS functional bistables associated with the remaining PT out of service in a tripped condition.
B.
(a.) The RPS is in a 2 of 3 logic condition to trip. (b.)Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of declaring PT-102B inoperable, the affected RPS bistables applicable to PT-1026 are tripped if unable to restore to operable status.
C.
(a.) The RPS is in a 1 of 2 logic condition to trip. (b.) Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of declaring PT-102D inoperable, bypass the affected RPS bistables associated with PT-102D and then remove the bypass keys from the functional RPS bistables affected by PT-102D to trip them.
D.
(a) The RPS is in a 2 of 3 logic condition to trip. (b) Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of declaring PT-102B inoperable, restore either PT-1026 or PT-102D to operable status and maintain the RPS functional bistables associated with the remaining PT out of service in tripped condition.
Answer:
A Answer Explanation:
Need to understand that with trip units bypassed you are in 2 of three logic, and when the other channel fails you are in 1 of two logic condition With one channel out of service, the RPS is in a two of three logic, when the second channel is tripped you are in a one of two logic to trip. Per technical specification 3.3.8 2 need restore to operable within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
24 March 2008 OPERATIONS Page: 16 of 37
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EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam Topic:
RO Importance:
SRO Importance:
KA Number:
Comments:
U-1 is in Mode 5 for a maintenance outage. ESFAS sensor cabinet ZF (1 2.3 3.5 2221 Modified from (217459
References:
Tech Spec 3.3.4-1 through 3.3.4-4 And 01-34 Appendix A page 1 24 March 2008 OPERATIONS Page: 18 of 37
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 13 ID: Q50453 Points: 1.00 Given a large steam rupture inside containment in each case, (a) which condition would result in the highest containment temperature? and (b.) which equipment would need to be started to mitigate this consequence?
A.
(a.) failure of CIS Channel B to actuate, (b.) Open IA-2080-MOV
- 6.
(a.) failure of SlAS Channel A to actuate, (b.) start one(1) Containment Spray Pump C.
(a.) failure of CSAS Channel B to actuate, (b) Open one(1) Containmen Spray cv D.
(a.) failure of SGlS Channel A to actuate, (b.) Shut one(1) Main Feed Isolation Valve Answer:
B Answer Explanation:
failure of SlAS Channel A to actuate--is correct. One train of containment coolers would fail to operate, and one train of containment spray would fail to operate (spray pump would not start).
Failure of CIS channel B would not appreciably change containment parameters unless an instrument air leak also existed.
Failure of CSAS channel B to actuate would result in only a spray train failure (one spray valve would remain shut) but all containment coolers would operate.
Failure of SGlS channel A to operate is incorrect, each channel operates all required equipment.
OPERATIONS Page: 19 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam Question 13 info Question Type:
Status:
Alwavs select on test?
Authorized for practice?
Points:
Time to Complete:
System ID:
User-Defined ID:
Cross Reference Number:
Topic:
RO Importance:
SRO Importance:
KA Number:
Comments:
No No 5
3.00 50453 Q50453 EVALUATE plant conditions and/or parameters and DETERMINE the following:
- a.
4.3 4.7 3201 3K303 Modified from Q 20347 Used on 7/2002 NRC exam,
References:
LD-58, EOp-5 basis page 32-35 ESFAS signal status 24 March 2008 OPERATIONS Page: 20 of 37
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 14 ID: (250455 Points: 1.00 Unit 2 is operating at 100% power during the month of August. Conditions are as follows:
Outside Air Temperature ( 102°F)
Bay Temperature 82°F Alarm "TURB BLDG SRW HDR PRESS LO" has been intermittently alarming. Which of the following is an appropriate action to take for this alarm?
A.
Determine that the alarm be "Blue Dotted" B.
Determine that the alarm be "Black Dotted" C.
Determine that the alarm be "Yellow Dotted" D.
Determine that the alarm be "Red Dotted" Answer:
A Answer Explanation:
Per CNG-OP-1.01 and ALM manua 1 C-13 K22 possible cause, this alarm should be blue dotted.
Since the alarm is a nuisance alarm a blue dot would indicate that it is locked in.
Black dot would not be used since the there is no maintenance being performed that causes this alarm.
Red dot is for a tagging activity Yellow dot is for one or more inputs out of service 24 March 2008 OPERATIONS Page: 21 of 37
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam Question Twe:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
Difficulty:
User-Defined ID:
Topic:
RO Importance:
SRO Importance:
KA Number:
Comments:
MultiDle Choice I
Active No No 1.oo 3 -
Q nn d.VV 50455 SRO - Given conditions, indications, and/or parameter values associated with inoperable SRW alarms, 3.0 3.3 2243 NEW Reference CNG-OP-1.01-2003 page 5 and Alarm Manual for 1 C-13 page 39 OPERATIONS Page: 22 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 15 ID: Q50456 Points: 1.00 Authorized for practice?
Points:
Time to Comtiete:
Using provided reference:
No 1.oo 3
Unit 1 was operating at 100% power when a large Loss of Coolant Accident (LOCA) occured.
EOP-5 has been implemented. Hydrogen concentration has risen to 5% and it is desired to start the Hydrogen Recombiners. The following conditions exist:
I up1L';
SRO Importance:
KA Number:
Comments:
RO Importance:
CNTMT TEMP Pre-accident = 90°F A CSAS has just occured indications associated wiih the Hydrogen recombiner 3.4 3.8 35028A201 NEW Which of the following is the appropriate recombiner power?
A.
57 Kw B.
60 KW C.
63 KW D.
65 KW Answer:
B Answer Explanation:
Per the graph of 01-41A with a Cntmt temp of 225°F assume saturation conditions =
Press of 4 psig which gives a KW of 60 KW I Alwavs select on test?
I No I
1 Reference 01-41 A page 5 and Figure 1 OPERATIONS Page: 23 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 16 ID: Q50458 Points: 1.00 SRO Importance:
KA Number:
Comments:
Glven the following conditions:
4.3 21 39 Bank question
References:
Oi-35 pages 56-57, and Table 1 page 3 Unit 1 is in Mode 6 Fuel Handling is in progress Containment Purge is in operation You are the OWC and a request has been made to do a functional test of the following Radiation Monitors one channel at a time. Which of the following should you NOT aprove?
A.
Fuel Handling Area Monitor (Rl-5420)
- 6.
Wide Range Noble Gas Monitor (RIC-5415)
C.
Containment Area Radiation Monitor ( RI-5316)
D.
Containment IC1 Area Monitor (RI-7008)
Answer:
C Answer Explanation:
Since RI-5316 has an auto action to secure purge on two of 2 of 4 channels actuating, a conservative decision would be to not allow this testing even though he would be testing one channel at a time.
24 March 2008 OPERATIONS Page: 24 of 37
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 17 ID: (350459 Points: 1.00 Using provided reference(s):
A tornado on site results in a Loss of Offsite Power and damage to 11 CST. Both units were tripped at 1600 on 413. All other systems and equipment operated as expected.
Based on the following CST inventories taken at 1700, approximately how long can U-2 remain in Hot Standby?
11 CST - Punctured by tornado debris, no useable level 12 CST - 29' 21 CST - 21.5' A.
0500 on 414
- 6.
1100 on 4/6 C.
0900 on 415 D.
2300 on 414 Answer:
C 24 March 2008 OPERATIONS Page: 25 of 37
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam Status:
Multiple Choice Active N O No 1.oo 3
3.00 50459 Q50459 Time to remain in hotstandby, 12 CSTunavailable SRO-201-2-1-10 9 0 L.V 3.1 21 25 Modified from Q26566
Reference:
are EOP attachment 9 ( 5 pages)
The available CST volume available to U-2 is -308,000 gallons once calculated using the EOP Attachment (9) for U-2. Looking at the graph for Makeup water required to maintain Hot Standby, a time of -40 hours is determined, or 4/5 at 0900.
Answer A is incorrect since it utilizes the same input parameters but uses the U-1 EOP Attachment (9) to perform the calculation rather than the U-2 Attachments, resulting in a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowance.
Answer C is incorrect if, during the calculation on the U-2 Attachment (9), the 12 CST volume is not divided by 2, yielding -66 hours.
Answer D is incorrect if, during the calculation on the U-1 Attachment (9), the 12 CST volume is not divided by 2, yielding -30 hours.
OPERATIONS Page: 26 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 18 ID: Q50462 Points: 1.00 During movement of irradiated fuel, a 30 gpm leak in the refueling cavity hatch seal requires that fuel handling cease. The refueling machine operator has just removed a fuel assembly from the core and is indexed over the upender. The transfer carriage is in the refueling cavity and vertical.
What actions should the FHS direct?
A.
Immediately secure the refueling machine and evacuate containment.
B.
Send the carriage to the spent fuel pool, return the fuel assembly to its previous core location.
C.
Place the fuel assembly in the deep pocket, beside the upender and shut the transfer tube gate valve.
D.
Place the fuel assembly in the upender carriage, send it to the spent fuel pool and shut the transfer tube gate valve.
Answer:
D Answer Explanation:
D is correct per AOP 6E 24 March 2008 OPE RAT1 ONS Page: 27 of 37
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 19 ID: (245548 Points: 1.00 Using Provided references:
An MO was generated to work a deficiency on 13 ARN pump. The deficiency is a clouded oil sight glass.The pump is still functional. It cannot be worked by FIN and must be planned and scheduled. Operations is concerned about the deficiency and it has operator compensatory actions associated to it, however it requires the13 AFW pump to be declared inoperable and removed from service to perform the work. What priority and schedule should this MO be?
A.
4 -White, Schedule as resources allow with the normal process B.
2-Yellow, Schedule at earliest opportunity within T-3 C.
3 - Orange, schedule at next available system week with 13 week matrix D.
1 - Red, Begin immediately and work around the clock Answer:
C Answer Explanation:
Per CNG-MN-4.01 -1 002, attachment 1, Online prioritization matirx, Since this is elective maintenance Orange, schedule at next available system week with 13 week matrix is correct Reference CNG-MN-4.01 attachment 1.
24 March 2008 OPERATIONS Page: 28 of 37
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 20 ID: Q50469 Points: 1.00 During an outage on Unit one, it is necessary to perform a task in the Auxiliary Building. A point source in the Auxiliary Building is reading 500 mrem/hr at a distance of two (2) feet. Two options exist to complete the task near this radiation source.
KA Number:
Comments:
Option 1 : Operator A can perform the task in thirty (30) minutes working at a distance of four (4) feet from the point source.
221 8 New Question Reference RP-1-10 page 45, Attachment 2 pages 1-4 Option 2: Operator B & C, who have been trained in the use of a special extension tool can perform the same task in seventy-five (75) minutes at a distance of eight (8) feet from the point source.
Which of the following options is preferable and consistent with CCNPP ALARA practices?
A.
Option 1 since Operator A s exposure is 62.50 mrem B.
Option 1 since operator A.s exposure is 31.25 mrem C.
Option 2 since the exposure is 78.1 2 mrem per person D.
Option 2 since the exposure is 31.25 mrem per person Answer:
A Always select on test?
No Authorized for practice?
No Points:
1.oo 24 March 2008 OPERATIONS Page: 29 of 37
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 21 ID: (225069 Points: 1.00 A reactor trip has occurred from full power on Unit-2. The following conditions exist:
-Reactivity Control is complete.
-Pressurizer level has stabilized at 120".
-No automatic ESFAS actuations have occurred.
-RCS pressure is 171 0 psia and slowly decreasing.
-Both SG levels are -1 50" and decreasing.
-SG pressures are 785 psia
-Tcold is 51 6 degrees F and decreasing Which of the following operator actions is required?
A.
Manually initiate SIAS, trip 2 RCPs and shut the MSIVs.
- 8.
Manually initiate SIAS, SGlS and trip all RCPs.
C.
Manually initiate SIAS, CIS and AFAS.
D.
Block SIAS, throttle AFW flow and shut the MSIVs.
Answer:
A Answer Explanation:
D is correct, SIAS should have been initiated by 1725 psia, per EOP-0, 2 RCPs are tripped after verifying SIAS.
A is incorrect, RCS pressure is high enough to support 2 RCPs running per Attachment 1 and SGlS is not required to initiate above 685 psia S/G pressure.
B is incorrect, AFAS setpoints are not challenged and there is no information to support initiating CIS.
C is incorrect, SIAS should not be blocked in EOP-0; although, not stated, it is it is inferred that the conditions are shortly after the trip. Also, with S/G levels dropping throttling AFW should not be accomplished at this point.
Basis: RX TRIP.
OPERATIONS Page: 30 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam Question 21 Table-Item Links A / 0 Trainina Proqram Licensed Operator Requal Training (LOR)
Operations Procedure References (from Nucleis)
EOP EOP-04-1 EXCESS STEAM DEMAND EVENT Svstem Desiqnations Emergency Operating Procedures (EOPs)
OPE RAT1 ONS Page: 31 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 22 ID: (250470 Points: 1.00 A fault has occurred on P-13000-2, resulting in a U-2 reactor trip. During EOP-0, the 2B DG experienced a start failure. Given the following additional plant conditions, what Optimal Recovery Procedure should be implemented?
Boration in progress with no CEA indication RCS pressure 1890 psia and lowering Pzr Level 130 inches and slowly lowering RCS Tcold 520°F and lowering RCS Subcooling is 107 O F 21 SG Pressure 835 psia and steady 22 SG Pressure 705 psia and lowering 21 SG Level (-)lo5 inches and slowly rising 22 SG Level (-)180 inches and lowering Containment Environment and Rad Levels External to Containment are met A.
- 6.
EOP-2 C.
EOP-4 D.
EOP-5 Answer:
C Answer Explanation:
Based on EOP-0 diagnostic flow chart, Core and RCS Heat Removal would not be met, and subcooled would be high, along with 22 S/G pressure lowering and 22 S/G level lowering. This would lead to the conclusion that an excess steam demand event is in progress.
OPERATIONS Page: 32 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam I Question 22 Info Authorized for practice?
Points:
Time to Complete:
Difficultv:
Multiple Choice Active No 50470 Q50470 3 7 4.3 2421 Modified from 245 References : EOP-0 pages 19-23 Provide diaanostic flow chart OPERATIONS Page: 33 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 23 ID: Q50463 Points: 1.00 Always select on test?
Authorized for practice?
Points:
Difficultv:
Time to Complete:
Unit 1 is operating at 50% power pending repairs on 11 Condensate Pump. 11 Condensate Pump repairs are complete and it is desired to return it to service. Which of the following describes the required sequence of operations when restoring 11 Condensate pump to service? Refer to the No No 1.oo 2
3.00 following :
1 -CD-126, 1 1 1-CD-104, 11 1 -CD-106, 1 1 A.
- 8.
C.
D.
COND PP VENT VLV COND PP SUCTION VLV COND PP DISCH VLV Open 1 -CD-126, Throttle Open 1 -CD-104, then fully open 1 -CD-104, then fully open 1 -CD-106, then start 11 Condensate pump Open 1 -CD-126, Throttle Open 1 -CD-104, then fully open 1 -CD-104, then start 11 COND PP, then open 1-CD-106 Open 1 -CD-126, then fully open 1 -CD-104, then fully open 1 -CD-106, then start 11 Condensate pump Open 1 -CD-126, then fully open 1 -CD-l04, then start 11 Condensate pump, then fully open 1 -CD-l06, Answer:
A Answer Explanation:
1 -CD-104 should be throttled open first to check for effects on the operating pumps then it is fully opened, the discharge valve is fully opened before the pump is started. REF 01-11A sect 6.20 restoring a condensate pump after maintenance.
I User-Defined ID:
lQ50463
, V."
1 1 imhnr.
I 3 3 3 /I KA hUIIIUuI.
GG I - t Comments:
New I
Reference:
Ol-1 1 A pages 64-65 OPERATIONS Page: 34 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 24 ID: Q20602 Points: 1.00 KA Number:
Comments:
Unit 2 is in Mode 6 with refueling in progress and Containment Purge in service. A momentary loss of power causes the operating Main Exhaust Fan to trip.
What is the most likely effect on containment parameters?
Containment refueling pool level changes Containment pressure rises 1 to 2 PSIG Containment area radiation monitors (RE-531 6-A through -D) indicate higher Containment temperature rises 5 to 10 degrees F A.
- 6.
C.
D.
2.1.41 Bank Question Used 7/2002 NRC exam
References:
01-36, page 5 Answer:
A Answer Explanation:
Refueling pool level changes--correct per 01-36 general precaution F. The Main Exhaust Fan tripping would cause Containment Purge to secure. This would change conatinment pressure by several tenths PSIG, with the transfer tube gate valve open, pool level will change accordingly due to the differential pressure between the SFP area and containment.
Containment temperature rises 5 to 10 degrees--incorrect, depending on weather, and status of plant heating to Purge, temperature could fall.
Containment pressure rises 1 to 2 PSIG--incorrect, containment pressure will change, but experience indicates, the change will be less than.5 PSIG.
Area radiation monitors (RE-531 6A-D) indicate higher--incorrect, the area monitors would not change in Purge is lost.
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam 25 ID: Q50499 Points: 1.00 Unit 1 and 2 are operating at 100% power with the following complement of Licensed Operators and Senior Operators:
SM(1)
Senior Licensed Operator CRS(2)
Senior Licensed Operators CRO(4)
Licensed Operators 0
STA/OWC(l)
Senior Licensed Operator At approximately 0000 one of the Licensed CROs becomes sick and must go home. Which of the following is required to meet the staffing requirements of NO-1 -200?
A.
Immediately get a relief within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
B.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> take action to obtain a relief within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
C.
OWC must assume the duties of the sick CRO to meet minimum staffing.
D.
No action is required since we meet minimum staffing.
Answer:
D Answer Explanation:
Per NO-1 -200 the shift manager can authorize operating at less than the table complement of NO-1-200 as long as we meet the minimum requirements of 10 CFR 50.54 which requires 3 Llcensed Operators 24 March 2008 OPERATIONS Page: 36 of 37
EXAMINATION ANSWER KEY CCNPP 2008 NRC SRO Exam References for this question are; NO-1 -200 section 5.1 Table page 24 a 10 CFR 50.54(m) )2-)i)
Technical Specifications pages 5.2.2,5.2-3 and 5.2-4 OPERATIONS Page: 37 of 37 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 1
ID: Q50230 Points: 1.00 Unit 1 was operating at 100% power MOC when an event occured. The appropriate AOP was entered, appropriate actions were taken and the reactor was manually tripped. No other actions have been taken. The following conditions now exists:
- 1. Pressurizer pressure is1 724 PSIA and lowering
- 2.
RCS Tcold is 530°F and steady
- 3. S/G Press is -880 PSlG on both S/Gs
- 4.
Pressurizer level is 1 8 5 and rising
- 5. All CHG pumps are operating
- 6.
Letdown is isolated
- 7. CNTMT Pressure is 1.7 PSlG and slowly rising Which of the following action and reasoning is correct for the conditions given:
A.
TRIP 11A & 12B RCPs to minimize heat input into the RCS
- 6.
TRIP 11 6 & 12B RCPs to minimize coolant inventory loss from the RCS C.
TRIP 11A & 12B RCPs to minimize coolant inventory loss from the RCS D.
TRIP 11B & 12A RCPs to minimize heat input into the RCS Answer:
C Answer Explanation:
Choice C is correct based on EOP-5 Basis. The EOP basis says that the RCP trip strategy ensures RCPs are secured for a small break LOCA (the hot leg case being more restrictive), while at the same time allowing two or more RCPs to remain running in the event of a non-LOCA. The incentive for stopping all RCPs during a LOCA is to minimize coolant inventory loss from the RCS. Further, it states that if RCS pressure drops to 1725 PSIA, as a result of the event, then trip RCPs so that either of the following pairs of RCPs remain running : 11A and 12B (21A and 22B)
RCPs, or 11B and 12A (21B and 22A) RCPs, and to trip all RCPs if CIS has actuated, Component Cooling flow can not be verified to the RCPs, or if RCS temperature and pressure are less than the minimum pump operating limits.
THe conditions given support the conclusion that the trip strategy should be implemented.
Distractor A is incorrect since it states an incorrect basis for the trip two leave two strategy, the strategy is not based on minimizing heat input into the reactor.
Distractor B is incorrect since it lists and incorrect pair of RCPs to trip Distractor D is incorrect since it lists and incorrect Basis for the trip two leave two strategy OPERATIONS Page: 1 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM I upc;.
RO Importance:
SRO Importance:
KA Number:
Comments:
[Question 1 Info 1
appropriate conditions and parameter values, 4.2 4.6 42008AK304 New Question Reference EOP-5 Basis page 27 & 28 ( Basis for step 1V.E EOP-5 Unit 1 page 11 Question Type:
I Multiple Choice Status:
I Active Always select on test?
Authorized for Practice?
I No 1
I No 24 March 2008 OPERATIONS Page: 2 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 2
ID: Q50231 Points: 1.00 Unit 2 was operating at 100% power when the following conditions were noted:
- 1.
- 2.
- 3.
- 4.
Letdown is at minimum
- 5.
Pressurizer level is 195" and slowly lowering RCS Tavg is 570°F and steady 21 & 22 CHG pumps are operating Pressurizer pressure is 21 00 PSlA and slowly lowering The appropriate AOP was entered and a reactor trip was manually initiated and EOP-0 was entered. The appropriate optimal EOP has been entered and now the following conditions exists:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
21 SG Level is - 115"and steady 22 S/G level is - 90" and steady 23 AFW pump is operating feeding both S/G Pressurizer pressure is 1340 PSlA and slowly lowering 21 & 23 HPSl pumps are running Tcold is 526°F and steady No process Radiation Monitors are in alarm Which of the following is correct based on the conditions listed above A.
Heat removal is adequate based on 22 S/G level only B.
Heat removal is adequate based on 21 or 22 S/G C.
Heat removal is inadequate based on 21 & 22 S/G levels D.
Heat removal is inadequate based on 21 S/G only Answer:
C Answer Explanation:
Distractor A is incorrect since 22 S/G level is -90" which is below the top of the tube bundle (-72"). Per the EOP-5 basis fpr Step IV. L on page 45. the safety analyse for small break LOCA assumes the S?G tubes are covered during recovery to permit adequate HPSl flow..
Adequate RCS heat removal will be maintained as long as at least one S/G has feedwater capability so its level can be maintained and has steaming capability so energy can be removed from the S/G. The S/Gs are checked to ensure either main or auxiliary feedwater is maintaining adequate S/G water level.
Maintaining at least one S/G as a heat sink available for RCS heat removal and cooldown is especially important in the case of a small break LOCA where RCS coolant leaking from the rupture is insufficient to remove the decay heat being produced. The Safety Analysis for Small Break LOCA assumes that the S/G tubes are covered during recovery to permit adequate HPSl flow. In addition, maintaining S/G water level above the top of the U-tubes provides sufficient static pressure head to prevent migration of containment radioactivity to the S/G secondary side.
OPERATIONS Page: 3 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 24 March 2008 OPERATIONS Page: 4 of 97
EXAMINATION ANSWER KEY CCNPP2008 NRC RO EXAM 3
ID: Q50232 Points: 1.00 Unit 1 has been in a Station Blackout for the last hour. Power has just been restored to 11 4KV Bus via high line 5051. The crew is evaluating restoring CCW and restarting 11A RCP. 11A RCP temperatures were hotter than 1 lB, 12A and 12B RCP temperatures by 5°F. Given 11A RCP lower seal temperature reached 284°F and Controlled Bleed-off (CBO) temperature of 260"F, which one of the following actions is acceptable?
A.
CCW flow can be reestablished but must be throttled since 11 A RCP lower seal temperature was 284°F B.
CCW flow can be reestablished to the RCPs by simply opening the CNMNT isolation valves since CBO flow remained less than 280°F C.
After CCW flow has been reestablished, restart one of the other RCPs (all conditions met) since their CBO remained less than 260°F D.
After CCW flow has been reestablished, 11A RCP can be restarted (all conditions met) since CBO remained less than 280°F.
Answer:
A Answer Explanation:
B. is incorrect, since lower seal temperature reached 284"F, CCW must be throttled on reinitiation.
A. is correct per EOP-7.
C. & D. are incorrect because with CBO temperature exceeding 250"F, the seals must be rebuilt.
NO-1-200 recommends that if CCW can be restored it should, even though you may not be able to run RCPs Based on AOp7C block step VI. E.4 on pg 30 I Modified from bank question 201237SOl OPERATIONS Page: 5 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 4
ID: (250250 Points: 1.00 Unit 1 is operating at 100% power with the following conditions:
0 0
12 Charging Pump is running.
11 & 13 Charging Pump hand switches are in NORMAL.
Backup Charging Pump Selector Switch is in the 13-1 1 position.
11 KV Bus normal feeder breaker trips and 1A D/G starts, energizes 11 4KV Bus and successfully sequences its loads on the Bus. Shortly thereafter the following occurs:
12 Charging Pump trips and no operator actions are taken.
SELECT the statement that best describes the response of the Chemical and Volume Control System (CVCS) to this event.
A.
Letdown flow will lower to and remain at -30 GPM due to lowering pressurizer level.
B.
Letdown flow will stabilize at a lower value until a backup charging pump is started, then return to the normal value.
C.
Letdown flow will bypass the in-service CVCS ion exchanger due to high temperature downstream of the Letdown Heat Exchanger D.
Letdown will isolate due to high temperature downstream of the Regenerative Heat Exchanger Answer:
D OPERATIONS Page: 6 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Question 4 Info Multiple Choice Active No No 1.oo Time to Complete:
13 Difficulty:
12.00 Reference RCS Lesson Plan Alarm Manual for 1 C07 F-01 ( Pg 6), F-05 (Pg014), F-06 Points: 1.00 5
ID: Q20569 Which condition would cause a SDC loop to be inoperable?
A.
- 6.
C.
D.
Placing the standby LPSl pump handswitch in Pull-to-Lock Shutting 1 1 LPSl pump Normal Suction Isolation, 1-51-444 Shutting 1 1 Component Cooling Supply Header Isolation, 1 -CC-162 Placing 13 CC pump handswitch in Pull-to-Lock Answer:
C OPERATIONS Page: 7 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Question 5 Info Question Type:
Status:
Always select on test?
Authorized for Practice?
Points:
Time to Complete:
User-Defined ID:
Cross Reference Number:
Topic:
RO Importance:
SRO Importance:
KA Number:
Comments:
Multiole Choice Active No No 3
2.00 20569 Q20569 Which condition will cause a SDC loop to be inoperable?
3.2 Question 5 Table-item Links Svstem Desiqnations Containment Spray Safety Injection System 3.2 42025AK202 Shutting 1 1 Component Cooling Supply Header Isolation, 1 -CC-l62--correct, this isolates 1 1 SDC heat exchanger.
Placing the standby LPSl pump handswitch in Pull-to-Lock-
-incorrect, auto start of a LPSl is not required.
Shutting 1 1 LPSl pump Normal Suction Isolation, 1 -Sl-444--
Incorrect, this vavle is normally shut when aligned for SDC, it is the suction from the RWT.
Placing 13 CC pump handswitch in Pull-to-Lock--incorrect, 13 CC pump being out of service does not render either Vain of CC out of service.
Jsed 7/2002 NRC exam
-oss of decay heat removal-54% contribution to CDF sequence qeferences: Technical Specifications basis for 3.4.7 page 3.4.7-4, 01-36 pg 14-21 OPERATIONS Page: 8 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 6
ID: Q15864 Points: 1.00 With the plant in a normal electrical lineup, a loss of offsite power occurs and the 1 B DG fails to start. What will occur as the CRO attempts to start 13 CCW pump?
A.
Pump fails to start due to its bus alignment B.
C.
Pump starts as the breaker closes with power available to motor Pump fails to start due to loss of 125 VDC control power.
D.
Pump starts when signal received from the shutdown sequencer step timing out.
Answer:
A Status:
I Active n Plan Slide 20 Consider adding the alarms, CCW PPS SIAS AUTO STAFT Question 6 Table-Item Links A / 0 Trainina Proaram License Operator Initial Training (LOIT)
Svstem Desianations Electrical 480V Motor Control Centers Electrical 480V Transformers and Buses 24 March 2008 OPERATIONS Page: 9 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 7
ID: Q50251 Points: 1.00 Given the following conditions:
Unit-1 at 100% power Pressurizer pressure is 2250 PSlA PZR backup and proportional heater control is in AUTO 1 -HS-1 00 (PZR pressure control) in the "Y" position 1 -HS-100-3 (PZR htr cutoff) in the "X+Y" position 1 -PT-1 OOY fails high Select the expected PROPORTIONAL HEATER response. Assume no operator action A.
Proportional heaters will operate at approximately 1/3 higher power than before the failure B.
Proportional heaters will operate at approximately 1/3 lower power level than before the failure C.
Proportional heaters will be at minimum and the red lights will be illuminated D.
Proportional heaters will be at minimum and the green lights will be illuminated Answer:
C Answer Explanation:
Proportional heaters will be at minimum and the red lights will be illuminated--correct, heaters will respond as if RCS pressure were high.
Proportional heaters will operate at approximately 113 higher power than before the failure--
incorrect, power to the heaters lowers on high pressure.
Proportional heaters will operate at approximately 1/3 lower power level than before the failure--
incorrect, pressure difference will be outside the control band, causing minimum power to be sent to the heaters.
Proportional heaters will be at minimum and the green lights will be illuminated--incorrect, greedred lights are function of breaker positions, supply breakers remain shut.
Used 7/2002 NRC exam OPERATIONS Page: 10 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 8
ID: Q44467 Points: 1.00 When a containment entry is required at power, what are Operations' responsibilities concerning lighting in containment?
A.
Operations is responsible for manipulating all the required lighting breakers.
B.
Operations is responsible for only the lighting breakers located inside the containment.
C.
Operations is only responsible for opening/closing breaker 52-1051 l(52-2051 1).
D.
Operations is responsible for none of the containment lighting breakers.
Answer:
C Answer Explanation:
Per NO-1 04, attachment Attachment 2, steps 6. 3 and 5, and attachment 4, Health Physics is responsible for the lighting breakers other than the 69'. Per step A.13, (and attachment 4) the Control Room opens and closes the breakers for 69' lighting.
Page: 11 of 97 24 March 2008 OPERATIONS
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM SRO Importance:
KA Number:
Comments:
I Points:
11.00 I
3.7 231 2 Bank Question References Per NO-1 04, attachment Attachment 2, steps 6. 3 and 5, and attachment 4, 9
ID: Q50252 Points: 1.00 When responding to a SGTR which of the following set of parameters should be used to identify the most affected S/G:
A.
Steam Flow-Feed Flow Mismatch, Main Steam Line RMS B.
S/G Level Trends, S/G blowdown RMS C.
Steam Flow-Feed Flow Mismatch, S/G blowdown RMS D.
S/G Level Trends, post trip bypass feed regulating valve position Answer:
A Answer Explanation:
Choice A is correct per EOP-6 Basis Choice B is incorrect since per EOP-5 basis the blowdown RMS cannot be used since it measures common RMS Choice C is incorrect since it also uses S/G Blowdown monitor which is common Choice D is incorrect since post trip the bypass valve goes to 56%
24 March 2008 OPERATIONS Page: 12 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Question Tvpe:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
Difficulty:
User-Defined ID:
Topic:
RO Importance:
SRO Importance:
KA Number:
Comments:
-~
Multiple Choice Active No
~
No 1.oo n
3.00 Q50252 Steam Flow indicators, determine that a SGTR
'37
- a.
I 3.6 41 038EA113 New Question References : EOP-6 basis for step 1V.J on page 36, Main Steam and Blowdown LP Slide 86, LOI-083-1 OPERATIONS Page: 13 of 97 24 March 2008
I EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Points: 1.00 10 ID: (250253 A manual reactor trip from 100% power was initiated due to an event in progress. Upon entry into the appropriate optimal recovery procedure the following parameters are observed:
11 S/G level is -50 inches and lowering 12 S/G level is - 30 inches and lowering CNTMT pressure is 4.25 psig and rising All electrical busses are energized from their normal power supplies.
Pressurizer level is 160 inches and rising slowly Pressurizer pressure is 2250 psia and rising slowly Tavg is 545°F and rising slowly RCS subcooling is 40°F and lowering slowly Based on these conditions, which of the following has occured?
A.
A steam line rupture on 11 S/G has occured
- 6.
A steam line rupture on 12 S/G has occured C.
A condensate header rupture has occured D.
A feed line rupture has occurred Answer:
D Answer Explanation:
Lowering levels is caused by loss of feedwater to the S/Gs A steam header rupture would result in an excesive cooldown and Subcooling would be increasing. A condensate header rupture would not result in containment pressure increasing.
OPERATIONS Page: 14 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM OPERATIONS Page: 15 of 97 24 March 2008
I KA Number:
Comments:
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 11 ID: (250254 Points: 1.00 41 055EK102 New Question References : EOP-7 Step 1V.K Page 26 EOP-7 Basis for 1V.K. page 30 and 31 A station blackout has occurred on Unit 1. After the appropriate Optimal recovery procedure has been entered, A M
flow is established to 17 & 12 S/Gs and steaming has commenced via the ADVs. The CRS has directed you to verify natural circulation flow. Which of the following groups of parameters/indications indicates that natural circulation flow has been established:
A.
Tcold 525 and constant Thot 580 and constant CET 585 and constant B.
Tcold 535 and constant Thot 585 and constant CET 580 and constant C.
Tcold 535 and lowering Thot 580 and lowering CET 585 and constant D.
Tcold 535 and constant Thot 580 and constant CET 585 and constant Answer:
D Answer Explanation:
D is correct since per EOP-7 Basis CET should be consistent with TH, if TH is constant CET temperatatrue should be constant A is incorrect since the delata t between Th and Tc is higher than 50°F B is incorrect since CET is not consistent with Th it is lower C is incorrect since CET is not consistent with Th
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 12 ID: (250255 Points: 1.00 Upon entry into EOP-2 for LOOP, #23 AFW pump is started due to problems with the steam AFW pumps to establish feedwater flow to #21 and #22 S/Gs with the following flow values:
-- #21 S/G 1 -FIC-4525A indicates 290 GPM
-- #22 S/G 1 -FIC-4535A indicates 300 GPM Based on these flow values which statement below is the best operator response?
A.
Maintain flow values ensuring that RCS cooldown rate is e 100°F per hour.
B.
Reduce AFW flow as the common suction flow limit is exceeded.
C.
Reduce AFW flow to 300 GPM to protect the 2B DG from overloading.
D.
Maintain flow values ensuring as CST level lowers pump cavitation does not occur.
Answer:
C Answer Explanation:
A & B is incorrect because EOP-2 basis states to limit flow to 300 gpm when 23 AFW pp powered from DG to protect DG from overloading and 575 gpm all other times D is incorrect because suction line limit of 1200 gprn is not being violated C is correct because flow limited to 300 gpm when on DG References EOP-2 pages 13 -1 5-Step IV G.2 EOP-2 page 24-Basis for IV.G.2 OPERATIONS Page: 17 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 13 ID: Q50256 Points: 1.00 Unit one is operating at 100% power when the following indications are noted:
Pressurizer pressure is 2250 PSlA Pressurizer level is rising All B/u Htrs are ON AFAS Loss of Power Alarm Actuation SYS loss of Power alarm RAS Actuation Sys tripped alarm SlAS Actuation Sys tripped alarm CSAS Actuation Sys tripped alarm 1 1, 12, & 13 Charging pumps are operating Letdown is at minimum Based on these indications which of the following is correct:
A.
1YO1 has been lost B.
1YO2 has been lost C.
1Y03 has been lost D.
1YO4 has been lost Answer:
A Answer Explanation:
A is correct, Based on the indications listed in AOP -73. All OtheTS are not consistent with the indications of AOP 75 Reference AOP 7J Section V actions for a loss of 1 YO1 -
OPERATIONS Page: 18 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 14 ID: Q50474 Points: 1.00 Unit 1 is operating at 100% power with the following conditions:
0 0
Bay Temperature = 80°F Outside Air Temperature = 100°F The following are noted 0
0 0
0 0
0 TURB BLDG SRW HDR PRESS LO - Alarm 11 SRW HDR PRESS LO-Alarm 12 SRW HDR PRESS LO-Alarm 11 SRW HEAD TK LVL-Alarm 12 SRW HEAD TK LVL-Alarm STEAM LINE DRAIN PANEL - Alarm (a) Which of the following is the most likely cause of these indications? (b) What actions are required?
A.
(a) A IeaWrupture of the Service water header in the Turbine Building, (b) Shut the Turbine Building isolation valves, and ensure SRW pressure returns to > 80 Psig B.
(a) A IeaWrupture of the Service water header in the Turbine Building, (b) Shut the Turbine building isolation valves, trip the reactor and implement EOP-0, C.
(a) A IeaWrupture of 11 or 12 Service water header in the Auxiliary building (b)
Shut the Turbine Building isolation valves and ensure that one header pressure restores to> 80 PSlG D.
(a) A IeaWrupture of 1 1 or 12 Service water header in the Auxiliary building,(b)
Shut the Turbine Building isolation valves,trip the reactor implement EOP-0, Answer:
B Answer Explanation:
(a) A rupture of the Service water system in the Turbine Building, (b) Trip the reactor and turbine, shut the turbine building isolation valves is the correct answer per AOP-7B basis.
The worst case leak scenario would be a IeaWrupture in the turbine building which would empty the SRW system in a short time,. This would render both SRW subsystems inoperable and hinder the safe shutdown of the plant. This would be indicated by the decrease of all SRW header pressures and the lowering of both head tanks. THe proper operator response include the tripping of the reactor and turbine and shutting the turbine building isolation valves OPERATIONS Page: 19 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM KA Number:
Comments:
I Status:
I Active 42062AA202 New Question References AOP 76 basis page 4 Alarm manual for 1 C-13 pages 11, 16, 34 and 42.
Alarm manual for 1 C 03 page 93 Alarm manual for 1T22, page 8 and 9 Points: 1.00 AOP 7D, "Loss of Instrument Air", requires a reactor trip if IA pressure lower to 50 PSIG in MODE
- 1. Which of the following is the reason for this:
15 ID: Q50258 A.
Protect the turbine/generator from damage due to the loss of Service Water cooling B.
Protect the RCS from overfeeding effects due to S/G level control concerns C.
Protect the RCPs from damage due to CCWs failing shut.
D.
Protect the SGFP from damage due to Miniflow valve potential failure Answer:
6 Answer Explanation:
Per the AOP 7D basis, B is the correct answer A is incorrect since the SRW valves do not fail shut until a complete loss of IA occurs C is incorrect since the Containment CCW valves are 50% open at 40 PSIG which supplies sufficient flow D is not correct since the S/G miniflow viilves fail open on loss of air.
24 March 2008 OPERATIONS Page: 20 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM OPERATIONS Page: 21 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 16 ID: Q50259 Points: 1.00 Terrorist have launched an attack against CCNPP involving two planes that have crashed into the Switchyard and the Auxiliary Building severely damaging the Switchyard, Control Room and Switchgear Rooms. The appropriate portion of the Emergency Plan has been implemented. The CRS has contacted you by radio and directed you to locally determine 11 SG level. Which of the following describes how you will accomplish this task:
A.
Obtain a multimeter from the locker in the operations study area and proceed to 27' West PEN room to determine 11 S/G Level.
B.
Obtain a Drucks loop calibrator and related equipment from the NSF Secondary Fire Brigade locker and proceed to 45' West PEN room to determine 11 S/G level.
C.
Obtain a multimeter from the locker in the operations study area and proceed to 45' West PEN room to determine 11 S/G Level D.
Obtain a Drucks loop calibrator and related equipment from the NSF Secondary Fire Brigade locker and proceed to 27' West PEN room to determine 11 S/G level.
Answer:
B Answer Explanation:
Per ERPI 3.0 Revision 40, pg 118 Choice B is correct since it correctly identifies the primary location for the equipment and the correct location for reading the level.
Choice A is incorrect since it identifies an invalid area to locate the equipment and incorrect location to read 11 SG level.
Choice C is incorrect since it identifies an invalid area to locate the equipment but has the correct location to read 11 SG level.
Choice C is incorrect since it identifies the correct area to locate the equipment but has the incorrect location to read 11 SG level.
Page: 22 of 97 24 March 2008 OPERATIONS
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Status:
Always select on test?
Authorized for mactice?
I Question 16 Info 1
Active No No I Question Type:
I Multiple Choice 1
I New Question I
I Reference ERPI. 3.0 Revision 40 tm 118 I
17 ID: Q20628 Points: 1.00 A loss of load transient resulted in a plant trip with PORVs lifting. What would indicate that the quench tank rupture disk has ruptured?
A.
"CNTMT NORMAL SUMP LVL HI" alarm actuates B.
"QUENCH TK TEMP LVL PRESS" alarm clears C.
RCS pressure lowers rapidly.
D.
RCS pressure lowers slowly.
Answer:
A OPERATIONS Page: 23 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Multiple Choice Active No No 1.oo 5
2.00 50260 Q20628 3.7 44E02EA11 "CNTMT NORMAL SUMP LVL HI" alarm actuates--correct.
The sump alarm along with quench tank pressure lowering are indications that the rupture disk ha5 ruptured.
RCS pressure lowers more rapidly RCS pressure lowers less rapidly----Both incorrect, the small range of back pressure associated with the intact or open quench tank would have little effect of PORV relief capacity.
"QUENCH TK TEMP LVL PRESSi' alarm clears--incorrect, level and temperature would remain high if the rupture disk blows.
Used 7/2002 NRC exam
References:
Alarm Response Manual for 1 C10 page 49 and 50 Alarm response manual for 1 CO6page 6 & 7 CFR 55.41.3, 55.41.7 Question 17 Table-Item Links System Desiqnations Reactor Coolant 24 March 2008 OPERATIONS Page: 24 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 18 ID: (250261 Points: 1.00 Given the following conditions:
0 Unit 1 is operating at 100 percent power 11 and 12 DFWCS are in AUTO Which of the following sets of conditions would result in entry to AOP-3G, Feedwater Malfunction? (consider each condition separately)
A.
SGFP Suct Press 220 psig for 20 seconds OR Hotwell Level at 50 inches B.
SGFP Suct Press 260 psig for 20 seconds OR Hotwell Level at 45 inches C.
SGFP Disch Press 1200 psig OR Hotwell Level at 50 inches D.
SGFP Disch Press 1300 psig OR Hotwell Level at 45 inches Answer:
D Answer Explanation:
SGFP Suct Press 220 psig for 20 seconds OR Hotwell Level at 50 inches - Per ALM Manual, the SGFP suction at 220 would give alarm and require implementing AOP 3G, but the H W level at 50" would not SGFP Suct Press 260 psig for 20 seconds OR Hotwell Level at 45 inches-Per ALM the HW level at 45" would result in AOP3G entry but SGFP suction pressure at 260 would not.
SGFP Disch Press 1200 psig OR Hotwell Level at 50 inches, Per ALM neither would result in AOP 3G entry SGFP Disch Press 1300 psig OR Hotwell Level at 45 inches-Per ALM both of these conditions will result in AOP3 G entry OPERATIONS Page: 25 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM References - Alarm Manual for 1 C03 pages 28 and 29,39, 48 24 March 2008 OPERATIONS Page: 26 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 19 ID: (250262 Points: 1.00 Due to continuous CEA withdrawal event, a reactor trip has occurred on Unit-1. Immediately after the reactor trip occurs, MCC 104R feeder breaker trips. While implementing EOP-0 the following indications are noted:
2 stuck CEAs.
11 Boric pumps trips when started Main turbine and generator are tripped.
Pressurizer level indication is 40 inches and slowly rising RCS subcooling is 0 degrees F.
RCS pressure is 1600 psia and dropping.
S/G levels are both -40" and stable.
S/G pressures are both 880 psia.
Containment press. is 2.0 psig and rising.
Containment temp is 21 5 degrees F and rising.
All electrical buses are energized.
So far, no actions (other than the actions for reactivity control) have been taken. Which one of the following groups of safety functions should be reported as "cannot be met"?
A.
Reactivity Control and RCS Pressure/lnventory Control.
B.
RCS Pressure/lnventory Control and Containment Environment.
C.
Core/RCS Heat Removal and RCS Pressure/lnventory Control.
D.
Containment Environment and Reactivity Control.
Answer:
6 Answer Explanation:
Candidate needs to recognize that even with both boric acid pumps not operating ( Loss of MCC 104R loses 12 boric acid pump) there is boric acid flow available via gravity feed valves A is incorrect, Boration is in progress means Reactivity is complete.
B is correct, PRZ level is low, RCS pressure is decreasing and SC is unsat, CNTMT temp. and pressure exceeding limits and increasing.
C is incorrect, HR is complete.
D is incorrect, Boration is in progress means Reactivity is complete.
OPERATIONS Page: 27 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM SRO Importance:
KA Number:
Comments:
3.6 2117 Modified from Q25093 References EOP-0 pages 6 -1 7 AOP 71 page 148 and 149 OPERATIONS Page: 28 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 20 ID: (250264 Points: 1.00 Given the following initial conditions:
0 0
0 0
0 Unit 2 is at 100% power.
All CEAs are fully withdrawn.
CEDS Control System is in OFF Turbine Control is in OPER AUTO 21& 22 DFWCS are in AUTO The following events occur:
0 ONE (1) Reg Group 2 CEA drops to the bottom of the core.
The reactor does NOT trip.
TM/LP Pre-Trip is received on 1 channel The crew enters AOPl B, CEA Malfunction.
Which ONE of the following describes a correct action for the conditions listed above in accordance with AOP 1 B?
A.
Decrease Turbine load by momentarily depressing the "DOWN" Button to restore Tcold within 2°F of program value.
B.
Decrease Turbine load by depressing the Turbine Manual Button, then depress the "DOWN" button to restore Tcold within 2°F of program value.
C.
Decrease Turbine load by depressing the Turbine Manual Button, then depress the "DOWN" button to restore Tcold within 5°F of program value.
D.
Decrease Turbine load by Momentarily depressing the Reference Signal Decrease Button, then depress the "GO" button to restore Tcold within 5°F of program value.
Answer:
B Answer Explanation:
Decrease Turbine load by momentarily depressing the Decrease Button for Manual Turbine since the turbine is in OPER AUTO mode, pressing the DEC button for Turbine MAN will have NO effect.
control to restore Tcold within 2°F of program value. This is not correct Decrease Turbine load by momentarily depressing the Decrease Button for Manual Turbine control to restore Tcold within 5°F of program value. This is not correct since the turbine is in OPER AUTO mode, pressing theDEC button for Turbine MAN will have NO effect, and Tcold should be restored to within 2°F of program by plant procedures. 5" is associated with a rapid downpower.
Decrease Turbine load by Momentarily depressing the DOWN button, then depress the GO button to restore Tcold within 2°F of program value. This is correct since in operator you decrease load by lowering the reference signal then pressing go.
OPERATIONS Page: 29 of 97 24 March 2008
I EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Decrease Turbine load by Momentarily depressing the Reference Signal Decrease Button, then depress the GO button to restore Tcold within 5°F of program value. This is not correct since Tcold should be restored to within 2°F of program by plant procedures.
5" is associated with a rapid downpower.
Question 20 Info Question Type:
Status:
Always select on test?
Authorized for Dractice?
Points:
Time to Complete:
User-Defined ID:
ToDic:
RO Importance:
SRO Importance:
KA Number:
Comments:
Multiple Choice Active No No 1.oo 4
2.00 50264 Q50264 Given a drop rod event determine if turbine actions correct 4.1 4.1 42003AA105 New Question Reference 01-43A page 50 -52 AOP 1 B page 7 section IV. A.2, OP-3 Daae 35 OPERATIONS Page: 30 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 21 ID: Q50265 Points: 1.00 Given the following:
Unit 1 is operating at 100% power.
A transient occurs that requires a rapid downpower. Due to problems with the CVCS system, CEAS are used during the rapid downpower. During the downpower, power is lowered to - 65%
and Group 5 CEAS are lowered to approximately 60" Which ONE of the following describes the correct actions and reasons based on the conditions above A.
AS1 is monitored using Excore Nls which limits are more conservative than the lncore detectors B.
AS1 is monitored using Excore Nls because the DAS must be declared inoperable under these conditions C.
AS1 is monitored using lncore Nls because the Excore detectors are not reliable under these conditions D.
AS1 is monitored using lncore Nls which limits are more conservative than the excore detectors Answer:
A Answer Explanation:
Per AOP 1 B Basis for step V1.C because of the position of GP 5 CEAS BASS is inoperable, with BASS inoperable the AOP directs AS1 monitoring using Excore and it states that these limits are more conservative than those associated with the incores which are normally used for AS1 monitoring 24 March 2008 OPERATIONS Page: 31 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM P-1 6 Basis for IV. C page 14 1 C06 alarm manual page 80-83 Loss of Plant Computer Lesson Plan LOI-202-7HR13 slide OPERATIONS Page: 32 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 22 ID: (250266 Points: 1.00 Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Unit 1 is at 10 - 6% power conducting a S/U after a shutdown to repair a steam leak on 12 S/G instrument line, when a loss of +15 VDC to the Wide Range Flux Trip relays occurs. Which of the following is correct for these conditions:
Multiple Choice Active No No 1.oo A.
SUR TRIP A, B,C,D Enabled alarm on 1C05
- 6.
SPDS indicates High SU rate on CSFI C.
TM/LP signal to CWP inhibited D.
TM/LP Trip is disabled Answer:
A Answer Explanation:
THe flux Trip relays normally trip at 1 E-4% rising and accomplish the following:
Enables TM/LP signal to CWP Removes Zero Power Mode Bypass in RPS to reinstate Low flow and TM LP Trip and Thermal power to Q power calculation Enables Plant Computer (PRimary) PDlL Enables SUR signal to RPS SUR TRIP A, B, C, D enabled alarm.
WHen the+- 15 VDC signal is lost the relays are actuated which gives all of the above indications.
THe SPDS calculates its own SUR from power indication I Question 22 Info Reference RPS Lesson Plan LOI-058-1-2 slides 101 -1 1 also alarm manual 1 C05-Daae 38 OPERATIONS Page: 33 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM ID: Q50267 Points: 1.00 23 Unit 1 is in a refueling outage and is currently performing core alteration when semi-trailer carrying a heavy load breaks down in the Butler Building - 2 feet from the Containment Outage Door (COD). Latest estimate is about 40 minutes to retrieve a tractor to move it. Which one of the following actions are required?
A.
ERPlP 3.0 Attachment 23, Containment Evacuation
- 6.
C.
AOP-GD, Fuel Handling Incident.
Implement AOP-4A, Loss of Containment Integrity/Closure.
D.
Process a containment closure deviation sheet Answer:
6 Answer Explanation:
Implement AOP-4A, Loss of Containment Integrity/Closure is correct per NO-1 -1 14 section 5.7 I Reference Per NO-1 -1 14, pages 7,9 and 23 Question 23 Table-Item Links A / 0 Traininq Proaram Licensed Operator Requal Training (LOR)
OPERATIONS Page: 34 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 24 ID: Q50268 Points: 1.00 Unit 2 was operating at 100% power when a leak in 1 1 Steam Generator Tube Leak occured. The appropriate AOP was entered, the reactor was manually tripped and the appropriate EOP has been entered. At 100% Power the following indications were noted:
11 S/G Pressure 860 PSlA 12 S/G Pressure 860 PSlA Calculated leakage 60 GPM 11 S/G has been isolated and the RCS cooled down to 500°F. Due to problems with the ADVs the temperature is holding at 500" F.
Per the applicable optimal recovery procedure the pressure differential between RCS and the S/G should be minimized. Approximately what pressure does the RCS need to be depressurized to reduce the leak rate to -25 GPM?
A.
1100 PSlA B.
1021 PSlA C.
921 PSlA D.
840 PSlA Answer:
C Answer Explanation:
m l = 60 GPM, m2 = 25 GPM Diff Press1 = 2250 PSI - 860 psi Diff Press 2 = desired RCS pressure - Sat press for 500°F OPERATIONS Page: 35 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM SRO Importance:
KA Number:
Comments:
3.9 42037AK102 New Question I
Reference Steam tables and knowledge of relationship between DP and flow 25 ID: Q50475 Points: 1.00 A Loss of offsite power occured along with a fire in the Unit1 Cable spreading room. The SM has determined that a control room evacuation is necessary and AOP-9 should be implemented.
Which of the following sets of actions are required to be completed within the first 30 minutes of CR Evacuation?
A.
Trip the RCPs AND start the OC Diesel Generator
- 6.
Start the OC Diesel Generator AND Establish Charging flow C.
Trip the RCPs AND Trip MCC-104 load center D.
Establish AFW flow AND Establish Charging flow Answer:
A Answer Explanation:
Trip the RCPs AND start the OC Diesel Generator - correct per AOP9A basis 1V.C and notes Ill C. 2 Start the OC Diesel Generator AND Establish Charging flow - Not correct, Charging flow not required until 60 minutes Trip the RCPs AND Trip MCC-104 load center - Not correct, trip MCC-104 load center does not have a time limit Establish AFW flow AND Trip MCC-104 load center - Not correct, charging flow not required for 60 minutes OPERATIONS Page: 36 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM RO Importance:
3.1 SRO Importance:
4.3 KA Number:
42067AA204 Comments:
New Question Reference AOPSA Basis page 1 AOPSA page 5 26 ID: Q50270 Points: 1.00 A loss of offsite power has occurred and 1A Diesel Generator has failed to start, followed by a complete loss of all feedwater. Once Through Core Cooling (OTCC) was initiated due to a loss of all feedwater. Which of the following is true concerning OTCC.
A.
OTCC will be successful B.
OTCC will be not be successful C.
OTCC will only be successful if 13 CHG pp is aligned to 146 480V Bus D.
OTCC will only be successful if 12 HPSl pump is started Answer:
B Answer Explanation:
PORV 1 -RC-402-ERV will not operate on high RCS pressure, its "manual open" handswitch position will not function to open the PORV--correct, power from MCC-114 is required to allow the PORV to open automatically or manually. With only one PORV available, OTCC will not be successful per attachment 17 even wth all HPSl and Chg pumps.
All other answers are incorrect based on the need to have both PORVS operational for OTCC to be successful OPERATIONS Page: 37 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Question 26 Info Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Comdete:
Difficulty:
Svstem ID:
User-Defined ID:
Cross Reference Number:
Topic:
RO Importance:
SRO Importance:
KA Number:
Comments:
No I
No 1.oo Q50270 Effect of PORVs on OTCC with failure A
3.4 42056AA132 PORV 1 -RC-402-ERV will not operate on high RCS pressure, its "manual open" handswitch position will not function to open the POW--correct, power from MCC-114 is required to allow the PORV to open automatically or manually. (This is a change in operation due to a modification). With only one PORV available, OTCC will not be successful per attachment 17 even with all HPSl and Chg pumps.
All other answers are incorrect based on the need to have both PORVS operational for OTCC to be successful Modified from Q 20589 used on 2002 NRC Exam
References:
EOP Attachments - Attachment 17 AOP-71 pages 18,50 Question 26 Table-Item Links Operations Procedure References (from Nucleis)
EOP EOP-02-1 LOSS OF OFFSITE POWER 24 March 2008 OPERATIONS Page: 38 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 27 ID: (250273 Points: 1.00 Unit one is operating at 100% power with the following conditions:
0 13 SRW Pump tagged out for maintenance A large Loss of Coolant Accident (LOCA) occured on Unit-1. The following conditions are noted:
0 12 SRW PMP - Tripped CNTMT PRESS - 15 PSlG Approximately 30 minutes later it was determined that 12 SRW Pump trip was caused by a blown fuse and has been replaced.
The CRS has directed you to restore SRW.
Which of the following set of actions is correct based on the conditions listed?
A.
Isolate SRW to CACs on 12 SRW SUBSY and start 12 SRW Pump.
- 8.
Isolate SRW to CACs on 12 SRW SUBSY and start 12 SRW Pump, then throttle SRW to 13 & 14 CACs C.
Place 12 SRW Pump in PTL, do not start 12 SRW until Technical support has provided guidance..
D.
Place 12 SRW Pump in PTL, place 1 B D/G OUT BKR in PTL, locally trip 1 B D/G Answer:
A Answer Explanation:
Reference Reference EOP-5 Step IV.G.6 page 18 and basis for this section on page 33 of the basis document Isolate SRW to CACs on 12 SRW SUBSY and start 12 SRW Pump to support 1 B D/G operation - correct per EOP-5 basis allows restarting 12 SRW pump with SRW to 13 & 14 CAS isolated.
Isolate SRW to CACs on 12 SRW SUBSY and start 12 SRW Pump, then throttle SRW to 13 & 14 CACs - incorrect per the basis restoration via throttling ws not evaluated because these asre butterfly valves Place 12 SRW Pump in PTL, do not start 12 SRW until Technical support has provided guidance..- incorrect, EOP-5 allows you to attempt a start of 12 SUSSYS in this condition and later contact TSC for continued operation.
Place 12 SRW Pump in PTL, place 1 B D/G OUT BKR in PTL, locally trip 1 B D/G -
incorrect, these actions are for the case that 12 SRW subsys cannot be restarted.
OPERATIONS Page: 39 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Reference EOP-5 page 18 and EOP-5 Basis Daae 33 OPERATIONS Page: 40 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 28 ID: Q50476 Points: 1.00 Given the following conditions on Unit-2 Pressurizer Pressure = 31 5 PSlA S/G Temperature = 90°F Pressurizer Level = 160 inches 4KV Bus Voltage = 41 30 V 13.8 KV Bus Voltage = 14.2 KV RCS Tcold = 140°F Which of the following conditions would prevent starting RCP 21 A per plant operating procedures A.
A pressurizer level control malfunction causes pressurizer level to rise to 172 inches and stabilizes.
B.
A heatup causes RCS Temperature to rise to 150°F and stabilizes C.
A voltage regulator pertubation causes 4 KV Bus voltage to lower to 41 10 Volts and stablizes.
' D.
An electrical perturbation causes 13 KV Bus voltage to rise to 14.8 KV and stabilizes.
Answer:
A Answer Explanation:
Per 01-1A Section 6.1.B Starting requirements for an RCP, S/G Temp no more than 60°F below RCS temperature, Pressurizer level less than 170 inches, RCS PRessure and Temperature within the limits of Flgurel7, 4KV Buss voltage is greater than 41 00 Volts, and 13.8 KV bus voltage less than or equal tol4.8KV OPERATIONS Page: 41 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Question Twe:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
Difficulty:
User-Defined ID:
Cross Reference Number:
Topic:
RO Importance:
SRO Importance:
KA Number:
Comments:
Active Nn No 1.oo 5
3.00 50476 Q50476 Provided a reference, identify the effect on starting an RCP L. Y 34003K614 New Question-01-1A pages 5-1 3 01-1 A figure 17 NOTE Figure 17 is provided as Reference OPERATIONS Page: 42 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 29 ID: Q50275 Points: 1.00 Which of the following sets of statement are true concerning the CVCS Backpressure Control Valve CV-110 P & CV-11 OQ?
A.
B.
C.
D.
(1 )Letdown backpressure control valves, prevent saturated conditions between the LD Heat Exchanger and the LD Flow control valves to prevent erosion damage (2)Letdown backpressure control valves, close to decrease pressure and open to increase pressure (1 )Letdown backpressure control valves, prevent saturated conditions between the LD Heat Exchanger and the LD Flow control valves to prevent erosion damage (2)Letdown backpressure control valves, open to decrease pressure and close to increase pressure (1)Letdown backpressure control valves, prevent saturated conditions between the regenerative heat exchanger and the Letdown Flow Control Valves to prevent erosion damage (2)Letdown backpressure control valves, close to decrease pressure and open to increase pressure (1 )Letdown backpressure control valves, prevent saturated conditions between the regenerative heat exchanger and the Letdown Flow Control Valves to prevent erosion damage (2)Letdown backpressure control valves, open to decrease pressure and close to increase pressure Answer:
B Answer Explanation:
To prevent flashing of hot liquid to steam between the Letdown Flow Control valves and the Letdown Heat Exchanger, Control letdown system pressure at 460 + 40 psi (NOT/NOP) Prevents erosion damage from the letdown control valve to the inlet of the heat exchanger. Valves open to decrease system pressure and close to increase system pressure 24 March 2008 OPERATIONS Page: 43 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM References CVCS Lesson Plan LOI-041-1-1 (LD) slides 72
-74 24 March 2008 OPERATIONS Page: 44 of 97
I EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 30 ID: (250276 Points: 1.00 Unit 1 is operating at 100% power when the following sequence of events occur Time 0 11 SG Pressure - P1013A, P10136, P1013C, P1013D = 860 PSI 12 SG Pressure - P1023A, P10236, P1023C, P1023D = 860 PSI 1 1 SG Level - LT114A, LT1146, LT114C, LTll4D = 0 inches 12 SG Level - LTl24A, LT1246, LT124C, LTl24D = 0 inches Tlme 1 Min 1 1 SG Pressure - P1013A, P10136, P1013C = 865 PSI, P1013D = 856 PSI 12 SG Pressure - P1023A, P10236, P1023C, P1023D = 740 PSI 11 SG Level - LT114A, LT1146, LTl14C = -180 inches, LTl14D= -120 inches 12 SG Level - LTl24A, LT1246, LT124C = -100 inches, LT124D = -1 10 inches Tlme 2 Min 30 seconds 11 SG Pressure - P1013A, P1013B, P1013C = 805 PSI, P1013D = 800 PSI 12 SG Pressure - P1023A, P10236, P1023C, P1023D = 740 PSI 11 SG Level - LT114A, LTll46, LT114C = -180 inches, LTl14D = -1 00 inches 12 SG Level - LTl24A, LTl246, LT124C = -1 00 inches, LT124D = -1 80 inches Based on these conditions which of the following is true:( Assume NO operator actions)
A.
- 6.
C.
AFW is supplying 11 S/G ONLY AFW is supplying 12 S/G ONLY AFW is isolated to 11 & 12 S/Gs D.
AFW is supplying 11 & 12 S/G Answer:
D Answer Explanation:
AFAS start signal is initiated when EITHER S/G has two of its four wide range level transmitters sensing e -1 70(170 inches from normal level of 0 inches)
Starts AFW after a 20 second time delay to prevent spurious actuation.
If the S/G level rises above -1 7 0 prior to the 20 seconds the AFAS start signal will drop out. However, the sensors will have to reset.
Once initiated AFAS start stays locked in.
AFAS BLOCK Secures AFW flow to the SG that has been identified as RUPTURED by shutting four blocking valves (2 motor and 2 turbine) to the S/G Monitors four pressure channels for each SG.
Differential pressures of sensors (one from each SG) provides input to two bistables which trip at 1 15 psid (TS setpoints are 135 and 130).
When there are 2 of 4 D/P signals from a SG the logic matrix from either SG sends a RUPTURE signal to BOTH actuation logic subsystems (ZA and ZB).
OPERATIONS Page: 45 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM AFAS Block isolates the generator with the lowest pressure.
When the differential pressure condition clears the block valves will Reopen unless the handswitches have been taken to close.
Reference AFAS Lesson plan LOI-0366-1-1 Slides 1-14, 37-39, 60-65 31 ID: (250290 Points: 1.00 Which of the following is the most likely reason for this condition:
"SI PPS RECIRC MOV 659 CLOSED RAS BLOCKED" Alarm is ON A.
MINI FLOW RETURN TO RWT ISOL,1-SI-659 MOV, is shut with an inadvertent RAS present B.
MINI FLOW RETURN TO RWT ISOL MOV, 1 - SI-659 MOV is shut with no RAS present C.
SI PP RECIR LOCKOUT handswitch, 1 -HS-3659A, is in ON and RAS present D.
MINI FLOW RETURN TO RWT ISOL, 1-SI-659-MOV shut and SI PP RECIR LOCKOUT handswitch, 1 -HS-3659A in ON Answer:
B Answer Explanation:
Per ALm Manual MINI FLOW RETURN TO RWT ISOL MOV, 1-SI-659 MOV is shut with no RAS present will give this alarm OPERATIONS Page: 46 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM ractice?
INo I1.on I
stion 1 ToDic:
I Rnacnn i 1 Comments:
I Reference Alarm Manual 1 C-09 page 86 I
32 ID: (250350 Points: 1.00 Using provided references:
U-1 is at 100% power, when one RPS matrix logic channel is declared inoperable. The present time is 1300. When must the unit be in Hot Standby?
A.
1900 today B.
C.
D.
1300 two days from now 1300 three days from now 1900, two days from now Answer:
D Page: 47 of 97 24 March 2008 OPERATIONS
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Question 32 Info Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
User-Defined ID:
Cross Reference Number:
Topic:
RO Importance:
SRO Importance:
KA Number:
Comments:
Active NO No 1.oo 4
3.00 Q50350 (220207 for one RPS matrix logic channel inop R A 3.0 21 32 Modified from (220207
References:
Tech Spec 3.1, 3.2, 3.3 Provide A copy of Tech Spec 3.1, 3.2, 3.3 OPERATIONS Page: 48 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 33 ID: Q50311 Points: 1.00 A LOCA occurred 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago. As a result of the LOCA Containment pressure rose to - 2.8 PSlG and operators verified the appropriate system actuations. RAS has actuated and been verified. HPSl has been throttled to minimum flow with two HPSl pumps running. The following indications are now noted:
- Both HPSl Pumps ammeters indicate - 5 amps
- HPSl flows are indicating 15 GPM through each header What actions should be taken in this condition?
A.
Commence ECCS pump room cooling B.
Stop one of the HPSl pumps and place its handwtich in pull-to-lock.
C.
Re-open the RWT outlet valves and commence filling the RWT.
D.
Implement EOP-8 Answer:
D Answer Explanation:
A is incorrect, because this action will not correct the problem of the HPSl pump cavitating.
B is incorrect, because this action will not prevent the remaining pump from cavitating.
C is incorrect, because the RWT is isolated after RAS.
D is correct. Since HPSl pump performance is not acceptable the HPSl pumps are stopped, with No HPSl EOP-8 is implemented Basis EOP-5 Post RAS throttling OPERATIONS Page: 49 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 34 ID: (350335 Points: 1.00 Given the following data on the Quench lank:
- 1) Pressure is 4 psig
- 2) Temperature is 105°F
- 3) Level is 29 incHES Which of the following is correct:
A.
Pressure is too high B.
Temperature is too high C.
Level is too high D.
All parameters normal Answer:
D Answer Explanation:
Parameters are all below the alarm setpoints and in the normal range for QT parameters Bank Question CRO-5-2-10-05
References:
RCS Lesson Plan 064A1-1 slides 123, 124, 125 Alarm Manual for 1 C06 page 6 & 7 01-1 B REV 15 page 6 OPERATIONS Page: 50 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 35 ID: Q50337 Points: 1.00 Unit 1 is in Mode 1 at 100% power when a loss of Component Cooling occurs. Which of the following resulting condition(s) from this event alone would require a Reactor trip?
A.
B.
CCW Head tank level lowers to 5 inches and stabilizes RCP upper thrust bearing temperature rises to 196°F and stabilizes.
C.
RCP lower seal cavity temperature rises to 205°F and stabilizes.
D.
CCW Header pressure lowers to 60 PSlG and stabilizes.
Answer:
B Question 35 Info Question Type:
1 Multiple Choice I
I Reference AOP7C Daae 7 -1 1 I
OPERATIONS Page: 51 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 36 ID: (250338 Points: 1.00 Unit 2 is operating at 100% power with the Letdown Hx Temperature Controller, 2-TIC-223, in MANUAL. While adjusting 2-TIC-223 the Reactor Operator adjust the output of 2-TIC-223 to 100%. Which of the following could result from this action:
A.
B.
C.
D.
Radiation monitor isolation, 1 -CV-521 -CV shuts UD HX CCW Diff Press High Alarm REGEN HX OUT TEMP HIGH Alarm RCS boron concentration decreases and reactor power increases Answer:
A Answer Explanation:
Raising the output of the TIC to 100% will shut the TCV therefore causing temperature to rise which will cause boron to be sloughed which is a negative effect UD HX CCW Diff Press High Alarm will not happen because this would mean max flow (
Valve wide opn)
REGEN HX OUT TEMP HIGH Alarm. IS not affected by Letdown FLOW RCS boron concentration decreases and reactor power increases ( This would mean increased flow lower temperature)
CVCS Lesson Plan LOI-041-1-1 (LD)- Slides 63-68 1 GO7 Alarm manual page 14 OPERATIONS Page: 52 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 37 ID: Q50339 Points: 1.00 SRO Importance:
KA Number:
Comments:
Unit 1 was operating at 100% Power MOC, with the following conditions:
2.7 3301 OK202 New Question Unit-1 at 100% power Pressurizer pressure is 2250 PSlA PZR backup and proportional heater control is in AUTO 1-HS-100 (PZR pressure control) in the "X" position A loss of 1 YO9 has occured. What affect (if any) will this have on the operation of the Pressurizer Pressure Control System?
A.
Pressurizer Spray Valve will not operate in MANUAL OR AUTO B.
Pressurizer Spray Valve will not operate in AUTO, but will operate in MANUAL C.
All Pressurizer Heaters will be OFF D.
Pressurizer Heaters will not energize on high pressurizer level (+13")
Answer:
A Status:
I Active Always select on test?
I No Authorized for oractice?
I No I
I I Reference-AOP 71 Daae 57 I
OPERATIONS Page: 53 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 38 ID: Q50340 Points: 1.00 SRO Importance:
KA Number:
Comments:
U-1 is in Mode 3 performing a reactor startup per OP-2, "Plant Startup from Hot Standby to Minimum Load". The following initial conditions exists:
0 DFWCS is in AUTO 0
0 ALL TCBs are shut 0
TBV in AUTO with setpoint of 900 PSI Crew is preparing to withdraw shutdown CEAs 4.1 3701 2K304 New Question Reference ESFAS Lesson Plan LOI-048-1-2 Slides 109 -1 1 1, 1 14 -
116 AOP 7J Page 28 Due to an electrical malfunction developing on the CEDM bus the following indications are noted:
4 reactor trip bus UV relay indicator lights energize on the Trip Status Panel above 1 C15 What impact will this have on plant operations?
A.
DFWCS will receive a signal from ESFAS AL ONLY to shift to Post Reactor Trip Mode B.
DFWCS will recieve a signal from ESFAS BL ONLY to shift to Post Reactor Trip Mode C.
DFWCS will receive a signal from ESFAS AL & BL to shift to Post Reactor Trip Mode D.
DFWCS will remain in its present mode and continue to feed the S/Gs Answer :
B Answer Explanation:
DFWCS will recieve a signal from ESFAS BL ONLY to shift to Post Reactor Trip Mode is the correct answer Question 38 Info OPERATIONS Page: 54 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 39 ID: (250341 Points: 1.00 U-1 is in Mode 3 returning from a maintenance outage. ESFAS sensor cabinet ZF (1C93) has been shutdown for cleaning and inspection. (All other channels are energized and signals are not bypassed).
Containment pressure transmitter (1 PT5313B) fails high, which 3 ESFAS subsystems will actuate?
A.
CIS, CVCIS, and CSAS B.
CIS, CVCIS, and SIAS C.
D Question 39 Info 3 ESFAS Subsystems Receiving High Containment 0 P E RAT1 ONS Page: 55 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 40 ID: Q50342 Points: 1.00 A SlAS has occured on Unit 1. Which of the following is a correct statment for this condition:
The CACs can be started in Fast Speed at 1 CO9 AND at the load contactor panel.
The CACs can be shifted to Fast Speed at the load contactor panel ONLY The CACs can be stopped from the load contactor panel ONLY The CACs can be stopped at 1 CO9 and at the load contactor panel.
A.
B.
C.
D.
Answer:
B Answer Explanation:
The CACs can be shifted to Fast Speed at the load contactor panel ONLY Question 40 Info Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
Difficulty:
System ID-User-Defined ID:
Comments:
Multiple Choice Active No No I
With SlAS where can CACs be placed in FAst Speed 3.7 3.5 35022K102 New Question ECCS Lesson Plan Containment Spray & Cooling LOI-052-3-3 slides 56-58, 60-61,65 AOP-SA page 53 24 March 2008 OPERATIONS Page: 56 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 41 ID: Q50343 Points: 1.00 Which of the following combinations of conditions/equipment would maintain the pressure and temperature of the containment within design parameters for a Design Basis LOCA A.
One CAC is OOS, and CS PMP A fails to start and CS PMP B seizes and trips when started B.
13 CAC is 00s and 1A DG fails to start on SlAS C.
11 CS is 00s, 13 SRW pump is 00s. 11 SRW pump fails to start on SlAS and and 14A 480V breaker trips D.
13 CAC is OOS, and CS PMP B fails to start and 1A D/G trips when started on SlAS Answer:
A Answer Explanation:
One CAC is OOS, and CS PMP A fails to start and CS PMP B trips when started - this would leave you with three CACs which will maintain CNTMT temperature/pressure below design 13 CAC is 00s and 1 A DG fails to start on SlAS - this would leave one CAC and one spray pump which would not meet minimum DBA 13 CAC is OOS, and CS PMP B fails to start and 1A D/G trips when started on SlAS -
this would leave No Spray pumps and 1 CAC which would not meet requirments 11 CS is 00s,13 SRW pump is 00s. 11 SRW pump fails to start on SlAS and and 14A 480V breaker trips - this would leave 1 Spray pump and one CAC which is not above minimum OPERATIONS Page: 57 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Modified from Q 20397 References ECCS Lesson Pan LOl-052-3-3 Slides 73-77 Basis: Ensure Design Pressure and Temperature of Containment / UFSAR Chapter 14.20 I Comments:
Points: 1.00 Following a LOCA, instrument air has been isolated to the containment due to a CIS. What effect does this have on the continued use of the Containment Spray System to cool the containment?
42 ID: 050345 A.
Both spray flowpaths are no longer available as the spray header CVs have failed closed on a loss of air.
- 6.
A bypass valve opens to ensure continued use of the Containment Spray System flowpath.
C.
No effect, each spray header CV fails open on a loss of air to ensure the flowpath remains available.
D.
No effect, the spray header CVs have keyswitches that override valves open to ensure the flowpath remains available.
Answer:
C Page: 58 of 97 24 March 2008 OPERATIONS
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Question Tvpe:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
User-Defined ID:
Cross Reference Number:
Topic:
RO Importance:
SRO Importance:
KA Number:
Comments:
Multide Choice Active No No 1.oo 2
2.00 Q50345 What effect does lost of Air have on Containment Spray CVS?
2.7 2.9 35026K202 Bank Question
References:
AOP 7D attachment 1,2, 3 Lesson Plan LOl-052-3-3 Slides 16,21,24 DtWg 60-61 7-8 Sh. 33 Basis: Instrument Air Isolated to Containment Due to CIA 43 ID: (250347 Points: 1.00 Which radiation monitor detects noble gas releases from the Atmospheric Dump Valves?
A.
B.
C.
D.
Condenser Off-Gas Radiation Monitor (RE-1 752A-0)
Wide Range Noble Gas Monitor (RIC-5415)
Main Steam Line Radiation Monitor (RE-5421)
Main Vent Gaseous Monitor (RE-541 5)
Answer:
C Answer Explanation:
Main Steam Line Radiation Monitor (RE-5421, 22)--correct per OM-98 sh 2.
Wide Range Noble Gas Monitor (RlC-5415)--incorrect, monitors Main Vent stack.
Main Vent Gaseous Monitor (RE-541 5)--incorrect,monitors Main Vent stack.
Condenser Off-Gas Radiation Monitor (RE-1 752A-D)--incorrect, these monitor the CAR suctions.
OPERATIONS Page: 59 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
Svstem ID:
User-Defined ID:
Cross Reference Number:
Topic:
RO Importance:
SRO Importance:
KA Number:
Comments:
Multiple Choice Active No No 1.oo 3
2.7 I
34039A109 Bank Question Used 7/2002 NRC exam References Lesson Plan LOI-077-1-2 Slides 66-71 OM-98 sh2.
I OPERATIONS Page: 60 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 44 ID: Q50348 Points: 1.00 Unit 2 is starting up from a refueling outage and has stabilized power at 440 MWE to perform an NI calibration prior to raising power to full power. The following indications are noted:
TBV 2-MS-3946-CV fails open Electrical MWs lowering Tave-Tref Alarm Which of the following actions AND reasons are correct for the conditions given:
A.
Adjust turbine load then insert CEAS, to stop reactor power rise.
- 6.
Adjust turbine load then withdraw CEAS, to restore Tcold to program.
C.
Adjust turbine load then insert CEAs, to maintain power c 5%
D.
Adjust turbine load then withdraw CEAS, to maintain reactor power Answer:
D Answer Explanation:
Adjust turbine load then withdraw CEAS, to maintain reactor powerr-is correct Insert CEAS after turbine load has been adjusted, to stop reactor power rise.is incorrect Insert CEAs to maintain power c 5% - incorrect Withdraw CEAS after turbine load has been adjusted, to restore Tcold to program -
incorrect Question 44 Info Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
Difficulty:
System ID:
User-Defined ID:
Comments:
50348 Q50348 4.1 I
0 P E RAT1 ONS Page: 61 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 45 ID: Q50349 Points: 1.00 Unit 2 is operating at 72% power with only one SGFP running and the following conditions exist:
0 0
0 SGFP suction flow rate is 17,500 gpm SGFP speed is 5175 RPM SGFP bias setting at 5.25 SGFP suction pressure is 255 PSlG What action is required to be taken to allow continued operation?
A.
Stop a Heater Drain Pump to lower SGFP suction flow.
B.
C.
Reduce reactor power to raise SGFP suction pressure.
Lower SGFP speed to within specifications D.
Lower bias setting to 5.0.
Answer:
C Answer Explanation:
Reduce reactor power to raise SGFP suction pressure Question 45 Info Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
Difficultv:
System ID:
User-Defined ID:
Cross Reference Number:
rock:
RO Importance:
SRO Importance:
KA Number:
Comments:
Active No No 1.oo 4
2.00 50349 Q50349 CRO-I 03-2-4-1 2 3.0 r."
J.J 34059A207 Modified from Q24634
References:
01-1 2A page 10 & 11, AOP-3G page 9 Basis: Continued Power Operation above 440 MWe per AOP-36 OPERATIONS Page: 62 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 46 ID: Q50351 Points: 1.00 Always select on test?
Authorized for practice?
Points:
Time to Comdete:
When a SGFP is in Direct Governor Valve control what does the OCS demand RPM indicate?
No No 1.oo 4
A.
Displays % output demand to the HP & LP governor valves of that SGFP.
- 6.
Displays speed demand signal from D W C S to the Lovejoy system for that SGFP C.
Displays % output demand to the HP governor valve ONLY of that SGFP.
D.
Displays speed demand signal from Lovejoy for that SGFP.
Answer:
A I
References:
LOI-045E-1-1 Slide 131 OPERATIONS Page: 63 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 47 ID: (250354 Points: 1.00 Unit 2 was operating at 100% power when a condensate header rupture occurs which requires a reactor trip. After the trip S/G levels are being controlled with #22 AFW pump. Subsequently a loss of Instrument Air occurs. What is the effect on the plant over the next hour ? Assume no operator action taken A.
RCS temperatures will lower due to the operating AFW pump speed rising to the maximum governor setting AND the FCV going to full open B.
RCS temperatures will rise due to the operating AFW pump trips on overspeed.
C.
RCS temperatures will rise due to S/G levels lowering due ONLY to AFW pump Steam Supply valves shutting.
D.
RCS temperatures will lower due to S/G levels rising due ONLY to the flow control valves failing full open.
Answer:
A Question 47 Info Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
System ID:
User-Defined ID:
Cross Reference Number:
Topic:
do Importance:
SRO Importance:
KA Number:
Comments:
1 Multiple Choice Active No I
No 1.oo 3
New Question Reference ANV Lesson Plan L01-036A-1 LP slides 1 17,
118,119,125 OPERATIONS Page: 64 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 48 ID: Q20632 Points: 1.00 Which of the following is a responsibility for the Refueling Control Room Operator (RCRO)?
A.
Documenting any fuel handling problems and maintaining the Refueling Status board B.
Approving temporary changes to core alteration procedures, such as CEA or fuel assembly location, due to malfunctioning refueling equipment C.
Verifying the qualifications of refueling machine, spent fuel handling machine and transfer machine operators prior to commencing core alterations D.
Ensuring all applicable requirements of the technical Specifications and the TRM are met for the evolution in progress Answer:
A Answer Explanation:
Documenting any fuel handling problems and maintaining the Refueling Status board--
correct per NO-1 -200.
Approving temporary changes to core alteration procedures, such as CEA or fuel aasembly location, due to malfunctioning refueling equipment--incorrect, approval process is per NFM procedures.
Verifying the qualifications of refueling machine, spent fuel handling machine and transfer machine operators prior to commencing core alterations--incorrect, this is done by the Fuel Handling Coodinator.
Ensuring all applicable requirements of the technical Specifications and the TRM are met for the evolution in progress--incorrect, this is the responsibility of the CRS, SM and FHS.
OPERATIONS Page: 65 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 49 ID: Q50358 Points: 1.00 RO Importance:
KA Number:
Comments:
SRO Importance:
Unit-1 has experienced a Loss of Offsite Power. Operators have implemented the appropriate Emergency Operating procedure. During plant stabilization a SIAS actuates due to low pressurizer pressure, and currently D/G 1 B is loaded to 3630 KW.
4.1 4.4 36062K102 Modified from Q42248 References : EOP-2 page 38 EOP -2 Basis page 37 Which of the following is correct for these conditions? (Assume NO operator actions)
A.
1 B Diesel Generator ENGINE EXCTR SHUTDOWN alarm due to D/G shutdown B.
1 B DG POT VOLT FREQ LO Alarm due to low frequency C.
1 B DG POT VOLT FREQ LO Alarm due to low voltage D.
1 B Diesel Generator ENGINE EXCTR SHUTDOWN alarm due to exciter shutdown Answer:
B Answer Explanation:
B is correct per EOP-2 step IV.P.1 and basis OPERATIONS Page: 66 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 50 ID: (250359 Points: 1.00 Given the following:
Unit 1 is operating at 100% power A loss of 12 DC bus occurs Which of the following describes the effect of the loss of 12 DC Bus? ( Assume No operator actions)
A.
B.
1 B D/G start solenoids fail open AND SRW CV fails open 1 B D/G control power loses power AND TCBs 1,2,5,6 trip C.
1 B D/G field flash AND control power lose power D.
1 B D/G start solenoids fail open AND TCBs 3, 4, 7, 8 trip Answer:
C Answer Explanation:
A. 1 B D/G field flash AND control power lose power. Correct
- 6. 1 B D/G start solenoids fail open AND SRW CV fails open - Not Correct Start Solenoids fail shut C. 1 B D/G control power loses power AND TCBs 1, 2, 5, 6 trip - Not Correct-TCBs 2,4,7,8 trip D.
start solenoids fail shut 16 D/G start solenoids fail open AND TCBs 3, 4, 7, 8 trip - Not Correct -
24 March 2008 OPERATIONS Page: 67 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 51 ID: (250361 Points: 1.00 Unit 1 was operating at 100% power when a SlAS occured with a loss of 11 4KV BUS. Which of the following statments is correct for these conditions?
A.
B.
1A D/G will trip a on Low -Low lube oil pressure OR High Crankcase pressure 1A D/G will trip a on Lube Oil Temp High-High OR Engine Overspeed C.
D.
1 A D/G will trip on HT Cooling Water Pressure Low OR generator overvoltage 1A D/G will trip a on Low - Low lube oil pressure OR Generator Differential Protection Answer:
D Question 51 Info Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
Difficulty:
System ID:
User-Defined ID:
Cross Reference Number:
Topic:
RO Importance:
SRO ImPortance:
KA Number:
Comments:
Active 1.oo 2.00 Q50361 Q15961 1A D/G Effects of SlAS or UV on trips 4.1 36064K401 Modified from Q15961 Reference Diesel Generator Lesson Plan LOI-024A-1-1 Slides 84 -90 Drawing 61 086 Sheet 19A OPERATIONS Page: 68 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 52 ID: (220392 Points: 1.00 Unit 1 has tripped and EOP-0 is implemented. The Condenser Off-Gas (1 -RE-1 752),
S/G Blowdown Recovery (1 -RIC-4095), S/G Blowdown Recovery (1 -RE-401 4) radiation monitor meter indications are pegged LOW and all lights on their panels are out/dark.
What action should be performed to support the Radiation Levels External to Containment (RLEC) safety function?
A.
Shut the Steam Generator Blowdown Control Valves and report RLEC cannot be met, due to loss of power effects B.
Shut the Steam Generator Blowdown Control Valves and report RLEC is complete C.
Restart the sample pumps and re-evaluate the indications D.
Attempt to clear all RMS alarms and re-evaluate the indications Answer:
A Answer Explanation:
Shut the Steam Generator Blowdown Control Valves and report RLEC cannot be met due to loss of power efects per EOP-0.- Correct Report "Radiation Levels External to Containment is complete" to the CRS-incorrect, the safety function should be reported as "cannot be met, due to loss of power effects".
Restart the sample pumps and re-evaluate the indications--incorrect, pumps cannot be restarted with power unavailable, as indicated by no lights on the panels energized.
Attempt to clear all RMS alarms and re-evaluate the indications--incorrect, alarms and indications cannot be restored with power unavailable, as indicated by no lights on the panels energized.
24 March 2008 OPERATIONS Page: 69 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM I Topic:
2.9 37073A201 Bank Question Used 712002 NRC exam
References:
EOP-0 page 17 EOP-0 basis page 28 NO-1 -201, pages 25-26 53 ID: (250363 Points: 1.00 Unit 1 is at 75% power, when 12 SW Pump trips. The appropriate AOP is entered. When 13 SW is started it seizes and the breaker trips. Which of the following is required for the listed conditions?
A.
Commence a a power reduction Per OP-3, Normal Power Operation, as required B.
C.
D.
Trip the Reactor and Implement EOP-0, Post Trip Immediate Actions Cross-connect SRW through 13 SRW pump suction and discharge Line up the SW system to use the Emergency Return Discharge Header Answer:
C OPERATIONS Page: 70 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM SRO Importance:
KA Number:
Comments:
3.7 3407614201 Modified from CRO-113-2-5-11 References : AOP-7A pages 12, 19 AOP-7A Basis page 10 Action Taken When Unit1 at 75% Power When 12 SW Pump trips and one header operating 54 ID: Q50364 Points: 1.00 Unit one is operating at 100% power when INSTR AIR SYS MALF alarm comes in. The following conditions are noted:
?
Instrument Air Header pressure is 96 psig
?
11 & 12 IA Dryer Malfunction Light is "Bright" Which of the following describes the likely cause of this alarm?
Loss of Power to an IA dryer Standby Air Compressor has picked up Plant Air to I/A X-Conn, 1 -IA-2061 -CV has opened Both dryers are in service due to low IA presure A.
B.
C.
D.
Answer:
A OPERATIONS Page: 71 of 97 24 March 2008
I EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Question 54 info Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
Difficulty:
System ID:
User-Defined ID:
Cross Reference Number:
Tooic:
RO Importance:
SRO Importance:
KA Number:
Comments:
No I
No 1.oo 3
Q50364 References : 1 C-13 Alarm Manual page 48-50 ID: (350365 Points: 1.00 55 Which of the following combination of components must exist to allow resetting CIS from the Control Room?
A.
1 -CC-3832, CC CNTMT Supply Vlv HS must be in Shut and 1 -IA-2080 MOV OVERRIDE HS must be in Override B.
1 -CC-3832, CC CNTMT Supply Vlv, HS must be in Shut and 1 -IA-2080 MOV must be in shut C.
1 -PA-1 040,Plant Air CNTMT Is01 Vlv HS must be in Shut and 1 -1A-2080 MOV OVERRIDE HS must be in Normal D.
1 -CPA-l4lO-CV, CNTMT Purge SUpp Vlv, must be in Shut, and CNTMT Purge EXH Fan must be in OFF Answer:
6 24 March 2008 OPERATIONS Page: 72 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM OPERATIONS Page: 73 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 56 ID: Q50366 Points: 1.00 Given the following:
?
?
An event occurs
?
?
Unit is operating at 100% power.
You are standing next to 1 C-15 and the CRS directs you to manually trip the Reactor You press two (2) Reactor Trip PBs on 1 C-15 Which ONE (1) of the following describes the effect on the plant?
Reactor Trip Switchgear Breakers....
A.
1,2, 5, and 6 OPEN; reactor trip occurs B.
3, 4, 7, and 8 OPEN; reactor trip occurs C.
1, 4 5, and 8 OPEN, reactor trip occurs D.
2, 3, 6 and 7 OPEN; reactor trip occurs Answer:
D Answer Explanation:
2, 3, 6 and 7 OPEN; reactor trip occurs.- Correct for K 2 & 3 from 1 C-15 1, 2, 5, and 6 OPEN; reactor trip occurs.- Incorrect combination & location 3,4, 7, and 8 OPEN; reactor trip occurs.- incorrect combination & location 1, 4 5, and 8 OPEN; reactor trip occurs.-correct combination wrong location Plan LOI-058-1-2 (RPS part 1)
OPERATIONS Page: 74 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 57 ID: Q50368 Points: 1.00 Unit two is in Mode 5 drawing a pressurizer bubble. Which of the following describes the current PZR level response and the reasons A.
When drawing a bubble in Mode 5, 1 -LI-l03 will read higher than 1 -LIC-1 1 OX and 1-LICl lOY, AND when in Mode 1 at NOP/NOT, 1 LI-103 will read approximately the same as 1 -LIC-1 1 OX and 1 -LICl 1 OY B.
When drawing a bubble in Mode 5, 1 -LI-l03 will read lower than 1 -LIC-ll OX and 1 -LICl 1 OY, AND when in Mode 1 at NOP/NOT, 1 LI-103 will read approximately the same as 1 -LIC-1 1 OX and 1 -LE1 1 OY C.
When drawing a bubble in Mode 5, 1 -LI-l03 will read lower than 1 -LIC-ll OX and 1-LICl lOY, AND when in Mode 1 at NOP/NOT, 1LI-103 will read lower than 1 -LIC-1 1 OX and 1 -LICl 1 OY D.
When drawing a bubble in Mode 5, 1 -LI-l03 will read higher than 1 -LE-1 1 OX and 1 -LICl 1 OY, AND when in Mode 1 at NOP/NOT, 1 LI-103 will read lower than 1 -LIC-1 1 OX and 1 -LICl 1 OY Answer:
B Answer Explanation:
When drawing a bubble in Mode 5, 1 -LI-l03 will read lower than 1 -LIC-1 1 OX and 1 -
LlCl 1 OY, AND when in Mode 1 at NOP/NOT, 1 LI-103 will read approximately the same as 1 -LIC-1 1 OX and 1 -LIC11 OY - this is correct because 1-LIC-11 OX and 1 -LICl 1 OY are calibrated for NOP/NOT conditions and as the pressurizer cools the density gets greater causing the DP ( between reference leg and pressurizer) to lessen, given a higher indicated level. LI-103 is calibrated from 1TE-101 and PT-105A and will indicate correctly throughout its range.
OPERATIONS Page: 75 of 97 24 March 2008
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EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM
References:
AOP-7J basis page 16 59 ID: Q50370 Polnts: 1.00 Unit one was operating at 100% power when an event occured. The plant was tripped and EOP-0 was implemented. The appropriate optimal recovery procedure has now been implemented. The following indications are noted:
0 0
SPDS alarm on 1 (2)C06 CSF3 (Core and RCS Heat Removal) block turns red for "CET High" Which of the following is the Minimum conditions required to cause these indications?
A.
2 of 4 CETs in a quadrant exceeded 625" F B.
1 CET in 2 of 4 quadrants exceeded 625" F C.
2 of 4 CETs in a quadrant exceeded 650" F D.
1 CET in 2 of 4 quadrants exceeded 650" F Answer:
C Answer Explanation:
page 2 provides a quadrant display of four highest CETs in each quadrant
- a.
- b.
Yellow alarms for > 625°F Red alarms for > 650°F
- 6.
CSF3 red 2 alarm if 2/4 CETs in a quadrant exceed 650°F
- a.
- b.
SDPS alarm on 1 (2)C03 CSF3 block turns red for "CET High" Page: 77 of 97 24 March 2008 OPERATIONS
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Question Type:
Status:
Always select on test?
Authorized for Dractice?
I Question 59 Info Multiple Choice Active No No RO Importance:
SRO Importance:
KA Number:
Comments:
3.2 3.2 3701 7K101 New Question Reference :SPDS screen last page of Core and RCS heat removal 60 ID: Q50371 Points: 1.00 Which of the following combination of statements concerning the Containment Iodine Removal System is correct?
A.
(1))Each IRU is 100% capacity, with each unit being 99% efficient for removing Iodine, (2) as humidty level approaches 99%, filter efficiency is - 50%
B.
(1))Each IRU is 100 Yo capacity, with each unit being 99% efficient for removing Iodine, (2) as humidity level approaches 99%, filter efficiency is - 90%
C.
(1))Each IRU is 50% capacity, with each unit being 99% efficient for removing Iodine, (2) as humidity level approaches 99%, filter efficiency is - 90%
D.
(1))Each IRU is 50% capacity, with each unit being 99% efficient for removing Iodine, (2) as humidity level approaches 99%, filter efficiency is - 50%
Answer:
C Answer Explanation:
(1))Each IRU is 50% capacity, with each unit being 99% efficient for removing Iodine, (2) as humidity level approaches 99%, filter efficiency is - 90% - Correct OPERATIONS Page: 78 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 61 ID: Q50373 Points: 1.00 Unit-1 is in EOP-1 with feedwater controls in automatic mode (feedwater regulating bypass valves are controlling level) when RCP feeder breaker, 252-1 201, trips. Assume no other operator action is taken. Which of the following secondary plant parameters indicate a loss of RCS flow is occurring?
A.
Lowering feed flow and steam flow with rising S/G pressures B.
Rising steam flow and feed flow with lowering S/G pressures C.
Rising steam flow and feed flow with rising S/G pressures D.
Lowering steam flow and feed flow with lowering SIG pressures Answer:
C Answer Explanation:
Rising steam flow and feed flow with rising S/G pressures--is correct, Tave will increase, causing ADVs to open. This will cause steam flow and feed flow to rise. S/G pressures will rise as Thot increases.
Distractors are possible combinations of secondary plant parameters.
OPERATIONS Page: 79 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Status:
Always select on test?
Authorized for practice?
Points:
Time to Comolete:
1 Topic:
Comments:
Multiple Choice Active No No 1.oo 5
3.00 50373 Determine the core and Dlant Darameters resDonse to a Loss of Flow Accident.
3.5 3.8 34035A102 Bank question used 7/2002 NRC exam
References:
EOP-2 basis page 16,29 -30 Loss of Flow Indicators in control room t
Points: 1.00 62 ID: (250374 Unit 1 is operating at 5070, at EOC. A TBV fails partially open which causes steam flow to increase 5%. In response to rising Rx power, the RO inserts Group 5 CEAs enough to reduce power 5%. With no further operator actions, which best describes the plant's response.
A.
Reactor power will decrease temporarily then return to 50%, S/G Pressure will not change.
B.
Reactor power will decrease to a new lower value, S/G pressure will not change.
C.
Reactor power will decrease temporarily then return to 50%, S/G pressure will be lower.
D.
Reactor power will increase to a new higher value, S/G pressure will be lower.
Answer:
D 24 March 2008 OPERATIONS Page: 80 of 97
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Always select on test?
Authorized for practice?
Points:
No No 1.oo OPERATIONS Page: 81 of 97 24 March 2008
I EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 63 ID: Q50376 Points: 1.OO Unit 1 is operating at 100% power with condensate pumps 1 1,12 and 13 running when 12 condensate pump trips.
What effect will this have on the secondary and what initial steps should be taken to mitigate the consequences?
A.
Reduced feed flow to the S/Gs and lowering levels will result. Bias feed pump speed as required to restore S/G levels.
B.
Lower feed pump suction pressure will result. Verify a condensate booster pump automatically starts.
C.
Cavitation and increased impellar wear will occur on the Condensate pumps.
Reduce power to maintain condensate header flow less than 8,000 GPM.
D.
Lower condensate header pressure will exist. Place hotwell level control in manual and bypass the condensate demins and precoat filters.
Answer:
D Answer Explanation:
Lower condensate header pressure will exist. Place hotwell level control in manual and bypass condensate demineralizers and precoat filters.--is correct per indications and actions in AOP-3G.
Reduced feed flow to the S/Gs and lowering levels will result. Bias feed pump speed as required to maintain S/G levels--is incorrect, S/G levels should be maintained by the feed pumps and the feed reg valves automatically.
Lower feed pump suction pressure will result. Verify a condensate booster pump automatically starts.--is incorrect, suction pressure will lower, but not to the point where the standby CBP starts.
Cavitation and increased impellar wear will occur on the Condensate pumps. Reduce power to maintain condensate header flow less than 8,000 GPM.-- is incorrect, power reduction is not required on loss of 1 condensate pump from 100% power OPERATIONS Page: 82 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Always select on test?
Authorized for practice?
Points:
Question 63 Info
~
~~
No No 1.oo I Question TvDe:
I Multiole Choice I
I Status:
I Active I
I I
References:
AOP-3G basis pages 9-1 1 I
64 ID: (250377 Points: 1.00 Upon receiving a Gaseous Waste Discharge (0-RE-21 91) high rad alarm, what automatic action occurs and immediate followup action is needed?
A.
B.
Shuts waste gas discharge valves, 0-WGS-2191 and -21 92; notify chemistry.
Shuts waste gas discharge valves, 0-WGS-2191 and 21 92; manually shut waste gas discharge header flow control valve, 0-WGS-2191 -PCV.
C.
Shuts waste gas discharge valves, 0-WGS-2191 and -2192; purge the waste gas discharge header.
D.
Shuts waste gas discharge header flow control valve, 0-WGS-2191-PCV; manually shut waste gas discharge valves, 0-WGS-2191 and -2192.
Answer:
B Answer Explanation:
Correct per Alarm manual response 1 C22H. these actions need to be performed by the operator.
OPERATIONS Page: 83 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Question 64 Info Question Type:
Status:
Alwavs select on test?
Authorized for practice?
Points:
Time to Complete:
Difficulty:
User-Defined ID:
Cross Reference Number:
Topic:
RO Importance:
SRO Importance:
KA Number:
Comments:
Multiple Choice Active No 1
2.00 cn477 au3/
I Q50377 CRO-122-1-3-24 What automatic action occurs and followup actions on Gaseous Waste Discharge (0-RE-21 91) High Alarm 3.3 3.5 39071 A409 Modified from Q24720
References:
Alarm manual for 1 C22H PAge 102-1 04 Gaseous Waste Discharge High Rad Alarm Automatic Action 55.41:11 55.43:5 1 65 ID: Q50378 Points: 1.00 A smoke detector for the Unit-1 45' Switch Gear Room malfunctions, causing an alarm.
Which one of the following describes the effect on the system and the appropriate response?
A.
"FIRE PROT PANEL 1 C24B" alarm actuates and after a time delay, Halon system discharges. Reset the fire panel 1 FP430 and restore ventilation in the Switchgear room.
"FIRE PROT PANEL 1 C24B" alarm actuates and immediately results in Halon system discharge. Reset the fire panel 1 FP430 and restore ventilation in the Switchgear room.
B.
C.
"FIRE SYS" alarm actuates and after a Reset the fire panel 1 FP430.
time delay, Halon system discharges.
D.
"FIRE SYS" alarm actuates but does not result in Halon system discharge.
Reset the fire panel 1 FP430 Answer:
D OPERATIONS Page: 84 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM REference : 124B Alarm Manual page 88 & 89 Flre System Lesson Plan ID: Q50381 Points: 1.00 66 In the event of a Control Room evacuation, what means is provided for control of the saltwater pumps?
A.
B.
Remote override transfer valves in the SRW pump room.
Local closure and trip of circuit breakers using the breaker front pushbuttons, C.
Localhemote keyswitches at the pump breakers.
D.
LOCI sequencer override pushbuttons at the ESFAS cabinets.
Answer:
C OPERATIONS Page: 85 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM I
I I References Saltwater Lesson Plan LOI-012-1-2 slides 50 -
I 52 Basis: Control Room Evacuation Means Provided for Control of SW Pumps
References:
KAl : KA2:
OPERATIONS Page: 86 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 67 ID: Q50383 Points: 1.00 Given the following conditions:
I, Unit 2 is at 100% power
,I 23 CCW Pump is 00s.
1205 1232 1259 1324 1343 21 CCW Pump declared INOPERABLE due to a failed surveillance.
22 CCW Pump also declared INOPERABLE due to the results of a Plant Shutdown to Mode 3 commenced.
21 CCW Pump returned to OPERABLE status.
22 CCW Pump returned to OPERABLE status.
common cause failure analysis.
Which ONE (1) of the following describes the Technical Specification requirements for operation of the plant?
Plant conditions...
A.
allowed the plant shutdown to be terminated no earlier than 1324.
B.
allowed the plant shutdown to be terminated no earlier than 1332 C.
require that the Shutdown to Mode 3 is completed by 1832 D.
require that the Shutdown to Mode 3 is completed by 1932 Answer:
A Answer Explanation:
A. allowed the plant shutdown to be terminated no earlier than 1324. - Correct B. allowed the plant shutdown to be terminated no earlier than 1332.- Incorrect C. require that the Shutdown to Mode 3 is completed by 1832. - Incorrect D. require that the Shutdown to Mode 3 is completed by 1932.- Incorrect OPERATIONS Page: 87 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP2008 NRCRO EXAM Always select on test?
Authorized for practice?
Points:
No No 1.oo KA Number:
Comments:
68 ID: Q50385 Points: 1.00 Unit 2 has just completed a refueling outage and is conducting PSTP3," Escalation to Power Test Procedure", at 85% it was determined that Frt is greater than the full power value of T.S 3.2.3.
While reviewing the data a transient occurs and power rises to 90% and is stabilized. Which of the following is required?
21 32 New question Referecne - Technical specifications 1-3.1 through 1-3.1 3 and 3.7.5 -2 through 3.7.5-2 A.
Reduce Thermal Power to less than or equal to 85% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B.
Reduce Thermal Power to less than or equal to 85% within 15 minutes C.
Reduce Thermal Power to less than or equal to 50% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D.
Reduce Thermal Power to less than or equal to 50% within 15 minutes Answer:
B Answer Explanation:
Reduce Thermal Power to less than or equal to 85% within 15 Mins - Correct per T.S.
3.1.8 OPERATIONS Page: 88 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 69 ID: Q50384 Points: 1.00 Unit-2 is in Hot Standby and the latest leakage reports are:
- 0.8 gpm - RCS drain valve weld leakage
- 1.8 gpm - leakage past check valves from the RCS to the SI system
-.05 gpm - primary-to-secondary leakage (.04 gpm 21 S/G,.01 gpm 22 S/G)
- 3.8 gpm - total leakage.
Which of the following Technical Specification leakage limits are exceeded?
A.
Pressure Boundary leakage and Primary to Secondary leakage B.
Pressure Boundary leakage and Unidentified leakage C.
Identified leakage and Unidentified leakage D.
Pressure Boundary leakage and Identified leakage Answer:
B Answer Explanation:
A. is incorrect because primary to secondary leakage is less than T.S. and unidentified is
> T.S.
B. is correct, pressure boundary leakage exists and unidentified is > 1 gpm. I3.8-(1.8+.8=.05)=1.15 gpm}
C. is incorrect because identified leakage is e 10 gpm.
D. is incorrect because identified leakage is c 10 gpm and pressure boundary leakage exists.
OPERATIONS Page: 89 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Points:
Diff icultv:
Time to Complete:
Status:
I Active Alwavs select on test?
I No 1.oo 4
3.00
References:
Technical Specification 3.4.1 3-1 through 3.4-13-3 70 ID: Q50387 Points: 1.00 Unit 2 is performing a startup after a refueling outage. Power is currently 20% and the turbine is in "Hold". The CRO places steam generator blowdown in service at 100 GPM/SG per plant Chemistry recommendations.
Which of the following describes the immediate plant response to this evolution? (Assume no additional operator actions)
A.
Reactor power increases, letdown flow increases, feedwater flow increases.
B.
Reactor power decreases, letdown flow increases, feedwater flow decreases.
C.
Reactor power increases, letdown flow decreases, feedwater flow decreases.
D.
Reactor power decreases, letdown flow decreases, feedwater flow increases.
Answer:
D Answer Explanation:
Reactor power decreases, letdown flow decreases, feedwater flow increases - correct +
MTC at BOC which means power lowers with decreasing temperature.
OPERATIONS Page: 90 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Question 70 Info Question Type:
Status:
Always select on test?
Authorized for practice?
Points:
Time to Complete:
System ID:
User-Defined ID:
Cross Reference Number:
Totic:
RO Imoortance:
SRO Importance:
KA Number:
Comments:
Multiple Choice Active No No I
References : Blow Down System Lesson plan LOI-83-1-0 Slides 93, 96, 97 01-8A REV 38 page 18 71 ID: (250388 Points: 1.00 Given the following:
II A CCNPP employee has returned from working an outage at Ginna NPP.
The dose received at GINNA was 750 millirem.
His TEDE radiation exposure for the year is 1550 millirem.
The remainder of his dose was received at CCNPP.
I,
,I I,
Which ONE (1) of the following describes the MAXIMUM additional dose the employee may receive prior to exceeding his TEDE alara dose goal for the year?
A.
700 millirem B.
1450 millirem C.
1700 millirem D.
2450 millirem Answer:
B Answer Explanation:
1450 millirem = correct 1700 millirem = incorrect, adds dose from Ginna 2450 millirem = incorrect, based on max admin limit of 4000 mr 700 millirem = incorrect, adds Ginna and based on max admin limit of 3000 mr OPERATIONS Page: 91 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Authorized for practice?
No Points:
1.oo Time to Complete:
3 Difficultv:
1.oo I References RP-1-100 pages 18-27 72 ID: Q50389 Points: 1.00 For entry itno a LOCKED HIGH RADIATION AREA which of the following correctly describes requirements that must be met?
A.
B.
C.
D.
A Radiation Work Permit, work approved by GS-RP, Radiation Protection approval for access, Pre Job Brief, dosimetry, pre-entry verification A Radiation Work Permit, work approved by GS-RP, Radiation Protection approval for access, Pre Job Brief, dosimetry, hand held survey instrument A Radiation Work Permit, continuously indicating dose rate meter, Radiation Protection approval for access, Pre Job Brief, dosimetry, pre-entry verification.
A Radiation Work Permit, continuously indicating dose rate meter, Radiation Protection approval for access, Pre Job Brief, dosimetry, hand held survey instrument Answer:
C Answer Explanation :
A Special Work Permit, continuously indicating dose rate meter, Radiation Protection approval, Pre Job Brief, dosimetry, pre-entry verification = correct.
OPERATIONS Page: 92 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 73 ID: Q50390 Points: 1.00 Unit-1 Waste Processing Ventilation Radiation Monitor (1 -RE641 0) is in alarm. All other RMS indications appear normal.
Which of the following would be a likely cause?
A.
A fuel handling event in the spent fuel pool B.
Elevated dose rates in the ECCS pump rooms due to SDC operation C.
Leakage from a Waste Gas Compressor D.
Excessive packing leakage from a Charging pump Answer:
D Answer Explanation:
Excessive packing leakage from a Charging pump--correct per alarm response manual and operator experience A fuel handling event in the spent fuel pool--incorrect, the SFP area monitor and Main Vent RMS indications would also be expected to rise.
Elevated dose rates in the ECCS pump rooms due to SDC operation--incorrect, ECCS pump room RMS would indicate this, WP would would only increase if SDC leakage were present.
Leakage from a Waste Gas Compressor--incorrect, Main Vent and Waste Gas Equipment Room area monitors would indicate this location for leakage.
OPERATIONS Page: 93 of 97 24 March 2008
I EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM Question 73 Info 74 I D Q50395 Points: 1.00 Following a plant transient, all control room annuciators are lost. The appropriate Abnormal and Emergency operating Procedures have been implemented and the CRS has directed appropriate compensatory actions. Which of the following feature(s) aids the control room staff in assessing panel indications to determine how close they are to exceeding limits?
A.
Level indicators with alarm setpoints associated with them have yellow zonebanding ranging from the normal value to the alarm setpoint.
B.
Level indicators with alarm setpoints associated with them have yellow zone banding ranging from the alarm setpoint to the Technical Specification Limit.
C.
Steam Generator level instruments have Orange zonebanding that range from the trip setpoint out to the scale end.
Steam Generator level instruments have Orange zonebanding ranging from the normal indicating range to the alarm setpoint D.
Answer:
B Answer Explanation:
Level indicators with alarm setpoints associated with them have a yellow zoneband ranging from the alarm setpoint to the Technical Specification Limit - Correct per NO 200 Rev 34 pg 73. CNG-OP-1.01 5.2.B.1,2 describes compensatory actions to incude alternate meands for monitoring the affected parameter.
OPERATIONS Page: 94 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM OPERATIONS Page: 95 of 97 24 March 2008
EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM 75 ID: (250398 Points: 1.00 At 6am on a Saturday morning a terrorist attack has resulted in significant damage to the Control Room and Auxiliary Building and all members of the control room staff were killed. Security has secured the terrorist and are attempting to coordinate activities in the Emergency Plan with Operations. In addition to the security personnel, the following onsite personnel are left alive :
Operations Manager (Inactive License)
Principal Plant Operator (Non-Licensed)
Plant Operator Instructor (Active License)
Turbine Building watch (Non-Llcensed)
Outside Watch (Non-Licensed)
Which of the following is correct for the listed conditions concerning coordination of required actions per the ERPIP?.
A.
The Principal Plant Operator is the operator in charge and will go to the Secondary Fire Brigade Locker and assume command of the site.
B.
The Operations Manager is the operator in charge and will go to the Operational Support Center and assume command of the site C.
The Plant Operator Instructor is the operator in charge and will go to the Secondary Fire Brigade Locker and assume command of the site.
D.
The Operations Manager is the operator in charge and will go to the Fire Brigade locker and assume command of the site Answer:
C Answer Explanation:
The Plant Operator Instructor is the operator in charge and will go to the Secondary Fire Brigade Locker and assume command of the site-Correct - Per ERPIP 3.0 Attachment
- 27.
OPERATIONS Page: 96 of 97 24 March 2008
I EXAMINATION ANSWER KEY CCNPP 2008 NRC RO EXAM References Per ERPlP 3.0 Attachment 27 Note.
OPERATIONS Page: 97 of 97 24 March 2008