ML23285A300
| ML23285A300 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/30/2023 |
| From: | Heather Gepford Operations Branch IV |
| To: | Entergy Operations |
| References | |
| IR 2023301 | |
| Download: ML23285A300 (1) | |
Text
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 1 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
(CE/E02) G2.4.16 Importance Rating 3.5 K/A Statement (CE/E02) Reactor Trip, Stabilization, Recovery (G2.4.16) Knowledge of emergency and abnormal operating procedures implementation hierarchy and coordination with other support procedures or guidelines, such as operating procedures, abnormal operating procedures, or severe accident management guidelines.
Proposed Question:
RO 1 Rev:
0 Given:
Circulating Water Pump (CWP) A is unavailable and danger tagged Circulating Water Pumps B, C and D are running Plant tripped due to feedwater heater perturbations Upon the trip, the auto transfer to the Startup Transformers was not successful for the 1B and 2B electrical busses Following the plant trip, the plant is left with ____(1)____ Circulating Water Pump(s) running. The diagnostic flowchart directs the crew to _____(2)_____ Recovery Procedure.
(1)
(2)
A.
one OP-902-006, Loss of Feedwater B.
one OP-902-001, Reactor Trip C.
zero OP-902-001, Reactor Trip D.
zero OP-902-006, Loss of Feedwater
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 2 of 161 Proposed Answer: C Explanation: (Optional)
A. Incorrect. With three CW pumps running and two trip, the remaining CW pump is designed to trip. The EOPs have been revised such that with AFW and /or 100% EFW flow equivalent available, the Reactor Trip Recovery Procedure is entered. Loss of MFW Recovery Procedure would have been correct prior to the EOP revision.
B. Incorrect. With three CW pumps running and two trip, the remaining CW pump is designed to trip. Part 2 is correct.
C. CORRECT: This question is from a W3 event (CR-WF3-2015-3565). With three CW pumps running and two trip, the remaining CW pump is designed to trip. Since CWP A is initially tagged out, the plant is left with zero CW pumps running. The plant is left without Main Feed Pumps due to an eventual loss of Condenser Vacuum (this info is in OP-003-003, Main Feedwater). In this event, the crew diagnosed into the Loss of Main Feedwater Recovery Procedure (OP-902-006). The EOPs have since been revised such that with AFW and /or 100% EFW flow equivalent available, the Reactor Trip Recovery Procedure (OP-902-001) is entered. The applicant must recognize that no optimal decision block has been circled in OP-902-009 Attachment 1 and entry into OP-902-001 Reactor Trip Recovery, is allowed. The guidance for this is located in OI-038-000, EOP Operations/Expectations Guidance Procedure.
D. Incorrect. Part 1 is correct. The EOPs have been revised such that with AFW and /or 100%
EFW flow equivalent available, the Reactor Trip Recovery Procedure is entered. Loss of MFW Recovery Procedure would have been correct prior to the EOP revision Technical Reference(s):
SD-CW page 18, OI-038-000 step 5.5.1 Rev. 21 (Attach if not previously provided)
OP-902-009 Appendix 1 Rev 323 (including version/revision number)
OP-003-033 Rev 328 pages 55 and 56 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE01 objs. 4,6,12 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2017 RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 4,10 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 3 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
008 AK2.07 Importance Rating 3.6 K/A Statement (008AK2.07) Pressurizer Vapor Space Accident: Knowledge of the relationship between (APE 8) PRESSURIZER VAPOR Space Accident and the following systems or components. PZR LCS.
Proposed Question:
RO 2 Rev:
0 Given:
Reactor is tripped Pressurizer Code Safety, RC-318B is stuck partially open Vessel level in the head indicates 90% and slowly lowering SIAS has not occurred Pressurizer level is ____(1)_____ and Pressurizer Level Controller output is
____(2)____.
____(1)____
____(2)____
A.
lowering lowering B.
lowering rising C.
rising lowering D.
rising rising
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 4 of 161 Proposed Answer: D Explanation: (Optional)
A. Incorrect. Plausible for pressurizer level to lower due to a LOCA. Plausible due to PLC output rise or lower based on pressurizer level vs program setpoint.
B. Incorrect. Plausible for pressurizer level to lower due to a LOCA. Plausible due to PLC output rise or lower based on pressurizer level vs. program setpoint.
C. Incorrect. Plausible based on a steam space LOCA level will rise. Plausible due to PLC output rise or lower based on pressurizer level vs. program setpoint.
D. CORRECT: Based on conditions given, steam bubble has moved to the Reactor Head, therefore pressurizer level will rise. PLC output will rise to increase letdown flow to lower pressurizer level.
Technical Reference(s):
TG-OP-902-002 page 144 Rev. 20 (Attach if not previously provided)
SD-PLC pages 12,13 Ref. 12 (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE02 Obj. 8 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 10 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 5 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
009 EA1.07 Importance Rating 3.5 K/A Statement (009EA1.07) Small Break LOCA: Ability to operate and/or monitor the following as they apply to (EPE 9) SMALL-Break LOCA. CCS Proposed Question:
RO 3 Rev:
0 Given:
Reactor power 100%
CFC A, B, D operating Subsequently, the Reactor trips with the following indications:
RCS Pressure is 1500 PSIA and stable RCS TCOLD is 541°F Containment Pressure is 16.9 PSIA and slowly rising SG 1 & 2 Pressures are 970 PSIA and stable Which of the following is the correct alignment for Containment Fan Coolers (CFCs)?
A.
CFCs A, B, C, D in SLOW speed.
B.
CFCs A, B, D ONLY in SLOW speed.
C.
CFCs A, B, C, D in FAST speed.
D.
CFCs A, B, D ONLY in FAST speed.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 6 of 161 Proposed Answer: A Explanation: (Optional)
A. CORRECT: SIAS has occurred due to pressurizer pressure being less than 1684 psia. On a SIAS, all CFC fans will operate in slow speed.
B. Incorrect. The running CFCs will stop and restart in SLOW, and the standby fan will sequence on in SLOW. This answer is plausible if the applicant does not identify that a SIAS has occurred.
C. Incorrect. The running CFCs will stop and restart in SLOW, and the standby fan will sequence on in SLOW. All CFCs starting in FAST speed is plausible because all CFCs swap to FAST speed following a loss of offsite power event.
D. Incorrect. SIAS has occurred due to pressurizer pressure being less than 1684 psia.
On a SIAS, all CFC fans will operate in slow speed. This answer is plausible if the applicant does not identify that CFCs swap to SLOW speed following a SIAS.
Technical Reference(s):
SD-CCS page 10 Revision 9 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-CCS00 Obj. 5 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7
55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 7 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
000011 EK2.03 Importance Rating 4.3 K/A Statement (011EK2.03) Large Break LOCA: Knowledge of the relationship between (EPE 11)
LARGE Break LOCA and the following systems or components. RCS.
Proposed Question:
RO 4 Rev:
0 Given:
Plant is at 100% power when a Large Break LOCA occurred Crew has entered OP-902-002, Loss of Coolant Accident Recovery Procedure As RCS pressure continues to lower, the maximum pressure at which the BOP should expect Safety Injection Tanks (SITs) to start discharging into the RCS is _____(1)_____
psig.
As RCS pressure becomes controlled, the CRS directs the BOP to close SIT outlet valves per OP-902-009, Appendix 14 SIT Isolation and Venting. To close the SIT outlet valves per this procedure, the crew will be required to _____(2)_____.
____(1)____
_______________(2)____________________
A. 670 Place key switch at SIT outlet valve breaker cubicle to bypass B. 670 Reset SIAS C. 1000 Place key switch at SIT outlet valve breaker cubicle to bypass D. 1000 Reset SIAS
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 8 of 161 Proposed Answer: B Explanation: (Optional)
A. Incorrect. Part 1 is correct. SIT outlet valves have a key switch located on its breaker that will override SIT interlocks so that the SIT outlet valve can be closed.
This is not the method directed by OP-902-009, Appendix 14 SIT Isolation and Venting. The key switch method is used during a control room evacuation.
B. CORRECT: Required range of SIT pressure per OP-903-001, TS Surveillance Log, is 600-670 psig. Therefore, the maximum pressure at which a SIT is expected to inject into RCS is 670 psig. OP-902-009, Appendix 14 SIT Isolation and Venting, states that the SIT outlet valve will not close unless SIAS is reset.
C. Incorrect. Part 1 is plausible because the pressure at which OP-902-002 will refer the crew to the Appendix to isolate SITs is 1000 psig but the SITs will not start injecting to the RCS until RCS pressure lowers to 670 psig. The SIT outlet valves have a key switch located on its breaker that will override SIT interlocks so that SIT outlet valve can be closed. This is not the method directed by OP-902-009, Appendix 14 SIT Isolation and Venting. This key switch method is used during a control room evacuation.
D. Incorrect. Part 1 is plausible because the pressure at which OP-902-002 will refer the crew to Appendix to isolate SITs is 1000 psig. Required range of SIT pressure per OP-903-001, TS Surveillance Log, is 600-670 psig. Therefore, the maximum pressure at which a SIT is expected to inject into RCS is 670 psig. Part 2 is correct.
Technical Reference(s):
OP-902-002 page 46 Rev. 21 (Attach if not previously provided)
OP-903-001 page 186 Rev. 102 (including version/revision number)
OP-902-009 pages 121 Rev. 323 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE01 obj. 6 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2018 NRC Exam RO-4 Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 5,10 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 9 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
015 AK1.02 Importance Rating 3.9 K/A Statement (015AK1.02) Reactor Coolant Pump Malfunctions: Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 15) REACTOR COOLANT Pump Malfunctions. Consequences of an RCP failure Proposed Question:
RO 5 Rev:
0 Given:
Plant is at 100% power RCP 1B shaft shears Which of the following are the operational implications due to the sheared shaft on RCP 1B?
A.
Automatic reactor trip due to a Low DNBR trip.
B.
No automatic trip but a manual reactor trip is required.
C.
Automatic reactor trip due to a Steam Generator low flow trip.
D.
Plant shutdown required in accordance with OP-901-212, Rapid Plant Power Reduction.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 10 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. The CPCs (low DNBR) would not trip the Reactor because CPCs detects flow from the RCP speed sensors, which is not affected by a sheared shaft. Plausible because RCP speed is an input to the Low DNBR trip.
B. Incorrect. Plausible if the applicant determines that the reactor will not trip due to speed sensors not able to see a sheared shaft event and is not aware of the purpose of the SG Low Flow Trip.
C. CORRECT: The SG Low Flow Trip provides protection against an RCP sheared shaft event. It monitors RCS flow on the primary side of the SG to trip the reactor on a loss of RCP flow. This trip actuates at 19.0 PSID across the primary side of the SG. This trip is necessary because the CPC-generated DNBR protection uses RCP speed sensors for RCS flow indication and cant see a loss of flow due to a sheared shaft event.
D. Incorrect. Plausible because the OP-901-130, Reactor Coolant Pump Malfunction, requires a rapid plant downpower in accordance with OP-901-212 for high vibration, lube oil emergency and high bearing temperature.
Technical Reference(s):
SD-PPS page 26 and Figure 9 Rev. 23 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPS00 obj. 5 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 6,7 55.43 Comments: Distractor D appears to be "none of the above". Leave as is, valid distractor, only one distractor can be reactor trip is not required. It is last because it is the longest distractor. Change distractor "D" to reference a rapid plant downpower. Changed distractor D to reference a rapid plant downpower. SAT.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 11 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
026 AK3.08 Importance Rating 3.4 K/A Statement (026 AK3.08) Loss of Component Cooling Water: Knowledge of the reasons for the following responses and/or actions as they apply to (APE 26) LOSS OF Component Cooling Water. Verifying CCW adequate surge tank level.
Proposed Question:
RO 6 Rev:
0 Given:
Component Cooling Water (CCW) Surge Tank level is lowering due to a CCW leak The Reactor Coolant Pumps will lose CCW flow when the CCW surge tanks lower to
___(1)____ %.
If CCW flow cannot be restored to the CCW AB header within 10 minutes, CCW should not be restored to prevent damage to the _______(2)______.
(1)
(2)
A.
24 RCP seals B.
24 RCP bearings C.
16 RCP seals D.
16 RCP bearings
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 12 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Part 1 is plausible since 24% is the level that CCW makeup pumps are interlocked to start and stop. This value is also located in OP-901-510, CCW System Malfunction. Part 2 is correct.
B. Incorrect: Part 1 is plausible since 24% is the level that CCW makeup pumps are interlocked to start and stop. This value is also located in OP-901-510, CCW System Malfunction. Part 2 is plausible because RCP upper and lower bearings are supplied with CCW.
C. CORRECT: The CCW AB header isolates at 16% level. The Reactor Coolant Pumps are on the CCW AB header. OP-901-510 caution on page 15 states that If component cooling water is lost to reactor coolant pump seals for > 10 minutes, then restoring component cooling water to reactor coolant pumps may result in seal failure. This question is comprehensive since the applicant must determine that the RCPs lose CCW when the CCW AB header isolates.
D. Incorrect. Part 1 is correct. Part 2 is plausible because RCP upper and lower bearings are supplied with CCW.
Technical Reference(s):
OP-901-510 page 5, 6, and 11 Revision 305 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO51 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 3,10 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 13 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
000027 AA1.01 Importance Rating 3.8 K/A Statement (027 AA1.01) Pressurizer Pressure Control Malfunction: Ability to operate and/or monitor the following as they apply to (APE 27) PRESSURIZER PRESSURE Control System Malfunction. PZR heaters, sprays, and PORVs.
Proposed Question:
RO 7 Rev:
0 Given:
Plant is at 100% power The in-service Pressurizer Pressure Control Channel has failed high OP-901-120, Pressurizer Pressure Control Malfunction, directs the crew to place the pressurizer ___________.
A. spray controller to MAN and adjust output to 0%
B. spray controller to MAN and adjust output to 100%
C. pressure controller to MAN and adjust output to 0%
D. pressure controller to MAN and adjust output to 100%
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 14 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: The in-service Pressurizer Pressure Control Channel failing high will cause the output of the Pressurizer Pressure controller to rise. This controller feeds the Pressurizer Spray controller causing its output to raise therefore opening spray valves. OP-901-120 will direct the crew to take manual control of the spray valve controller and lower output to 0% close the spray valves.
B. Incorrect. Plausible to think that raising the output of the spray controller would cause pressurizer pressure to rise.
C. Incorrect. Plausible because adjusting the output of the pressurizer pressure controller would adjust the spray controller but this action is not fast enough to prevent a reactor trip. Adjusting output lower on the pressure controller works to raise Pressurizer pressure.
D. Incorrect. Plausible because adjusting the output of the pressurizer pressure controller would adjust the spray controller but this action is not fast enough to prevent the plant from tripping on low RCS pressure. Plausible to think that raising the output of the spray controller would cause pressurizer pressure to rise.
Technical Reference(s):
OP-901-120 page 6 Rev. 303 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7,10 55.43 Comments: Discuss - may be too close to event 2 in scenario 3. Event 2 in Scenario 3 is a pressure control channel failing low. This question is written on a pressure control channel failing high. Completely different actions. Leave as is.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 15 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
029 EK1.03 Importance Rating 4.2 K/A Statement (029EK1.03) Anticipated Transient Without Scram: Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (EPE 29) ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS). Addition of negative reactivity.
Proposed Question:
RO 8 Rev:
0 Given:
Reactor power is 1%
A large steam leak upstream of MSIV B prompts the crew to trip the reactor A manual reactor trip using CP-2 pushbuttons was unsuccessful The crew tripped the reactor using the Diverse Reactor Trip System (DRTS)
All CEAs have inserted into the core The DRTS de-energized CEDM cabinets by opening the MG set ____(1)____.
Emergency boration ______(2)______ to maintain shutdown margin.
(1)
(2)
A.
supply breakers IS required B.
supply breakers IS NOT required C.
load contactors IS required D.
load contactors IS NOT required
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 16 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect: DRTS opens the Motor-Generator Output contactors to de-energize CEDMCS.
Second part is correct.
B. Incorrect: DRTS opens the Motor-Generator Output contactors to de-energize CEDMCS. OP-902-000, Standard Post Trip Action does not direct the operator to emergency borate when all CEAs insert into the core however, OP-901-103, Emergency Boration directs the operators to initiate emergency boration in response to an uncontrolled cooldown.
C. CORRECT: DRTS opens the Motor-Generator Output contactors to de-energize CEDMCS.
The applicant must recognize that an uncontrolled cooldown is in progress and therefore emergency boration is required. OP-901-103, Emergency Boration directs the operators to initiate emergency boration in response to an uncontrolled cooldown.
D. Incorrect: First part is correct. OP-902-000, Standard Post Trip Action does not direct the operator to emergency borate when all CEAs insert into the core however, OP-901-103, Emergency Boration directs the operators to initiate emergency boration in response to an uncontrolled cooldown.
Technical Reference(s):
OP-901-103 pages 2,3 Rev. 5 (Attach if not previously provided)
SD-ATS page 9 Rev. 5 (including version/revision number)
OP-902-000 page 5 Rev. 17 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO10 obj. 1,1 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2015 RO NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 10 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 17 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
038 EA2.15 Importance Rating 4.0 K/A Statement (038EA2.15) Steam Generator Tube Rupture: Ability to determine and/or interpret the following as they apply to (EPE 38) STEAM GENERATOR Tube Rupture. RCS pressure Proposed Question:
RO 9 Rev:
0 Given:
RCS depressurization is being performed IAW OP-902-007, Steam Generator Tube Rupture, due to a rupture on SG 2 All RCPs are secured CET Temp is 510 ºF THOT Loop 1 and 2 is 506 ºF TCOLD Loop 1 and 2 is 495 ºF The CRS has placed a lower limit of 30ºF on Subcool Margin Determine the minimum value of RCS pressure that supports the requested RCS Subcool Margin.
A.
745 psia B.
850 psia C.
931 psia D.
963 psia
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 18 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect: This value is the saturation pressure for the existing CET temperature.
This distractor would be chosen if 30 ºF subcooled is not factored into the answer.
B. Incorrect. Value associated with Cold leg temperatures. CET temperature should be used to determine subcool margin when on natural circulation.
C. Incorrect. Value associated with Hot Leg temperature. CET temperature should be used to determine subcool margin when on natural circulation.
D. CORRECT: Value associated with CET temperature. OI-038-000 has guidance to use CET temperatures on natural circulation. The saturation pressure for 540 ºF (510
ºF + 30 ºF) is 963 psia.
Technical Reference(s):
OI-038-000 page 15 Rev. 21 (Attach if not previously provided)
Steam Tables (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE01 obj. 4 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2018 NRC RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 14 55.43 Comments: Discuss - is distractor A assuming student will confuse pressure with temperature? Yes, and agree it is not a good distractor. Changed distractor A to 745 psia. Changed the explanation for distractor A to This value is the saturation pressure for the existing CET temperature. This distractor would be chosen if 30 ºF subcooled is not factored into the answer. Added the calculation required to get the right answer to distractor D.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 19 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
CE E05EK3.07 Importance Rating 3.7 K/A Statement (CE EO5EK3.07) Steam Line Rupture: Knowledge of the reasons for the following responses and/or actions as they apply to (CE E05) EXCESS STEAM DEMAND.
Operating RCPs within operating limits Proposed Question:
RO 10 Rev:
0 OP-902-004, Excess Steam Demand Recovery Procedure, states to verify no more than two Reactor Coolant Pumps running if Tcold is less than a maximum of ___(1)___ °F to
__________(2)___________.
(1)
(2)
A.
380 prevent generating excessive core uplift forces B.
380 aid in stabilizing Reactor Coolant System temperature after Steam Generator dryout C.
230 prevent generating excessive core uplift forces D.
230 aid in stabilizing Reactor Coolant System temperature after Steam Generator dryout
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 20 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: Per OP-902-004, Tc < 380 requires 1 RCP in each loop to be secured. TG-OP-902-004 states that the PT limit curve specifies that one RCP should be tripped although OP-902-004 directs the crew to secure one RCP in each loop for even flow between the loops.
The reason for this step identified in the Tech Guide is to prevent a core uplift problem.
B. Incorrect. The temperature is correct. The basis is incorrect per TG-OP-902-004; however, it is plausible that elimination of heat addition to the RCS would aid in stabilizing RCS temperature since Waterfords ADVs are not sufficient size to prevent needing to have a minimum EFW flow to aid in RCS temperature stabilization.
C. Incorrect. The temperature is incorrect. The temperature of 230°F is the minimum temperature for three pump configuration per OP-001-002. The basis is correct per TG-OP-902-004. 230°F the wrong answer because the stem is asking what does OP-902-004 state in the procedure.
D. Incorrect. The temperature is incorrect. The temperature of 230°F is the minimum temperature for three pump configuration per OP-001-002. The basis is incorrect per OP-902-004; however, it is plausible that elimination of heat addition to the RCS would aid in stabilizing RCS temperature since Waterfords ADVs are not sufficient size to prevent needing to have a minimum EFW flow to aid in RCS temperature stabilization. 230°F the wrong answer because the stem is asking what does OP-902-004 state in the procedure.
Technical Reference(s):
TGOP-902-004 page 28 Rev. 308 (Attach if not previously provided)
OP-902-004 page 9 Revision 17 (including version/revision number)
OP-001-002 page 4 Rev. 28 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE04 obj. 7 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2017 NRC RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 55.43 Comments: Since 230 is less than 380, why is C wrong? Changed the stem to what does OP-902-004 state in the procedure. That makes 230°F the wrong answer. Added how 230°F is the wrong answer to explanation C and D.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 21 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
054 G2.1.20 Importance Rating 4.6 K/A Statement (054) Loss of Main Feedwater: (G2.1.20) CONDUCT OF OPERATIONS: Ability to interpret and execute procedure steps.
Proposed Question:
RO 11 Rev:
0 Given:
The reactor is tripped due to an Inadvertent Main Steam Isolation Signal (MSIS)
Emergency Feedwater (EFW) Pump A is danger tagged out An EFAS-1 and EFAS-2 have occurred A subsequent loss of ____(1)____ would require entry into OP-902-006, Loss of Feedwater Recovery Procedure. Upon entry into OP-902-006, the crew will be required to secure ____(2)____.
(1)
(2)
A. EFW Pump B all Reactor Coolant Pumps B. EFW Pump AB all Reactor Coolant Pumps C. EFW Pump AB one Reactor Coolant Pump in each loop D. EFW Pump B one Reactor Coolant Pump in each loop
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 22 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. EFW Pump AB supplies 100% capacity to the Steam Generators, therefore, the crew will not be required to enter OP-902-006 if EFW Pump AB is the only EFW Pump running. The applicant must interpret and execute the step in the Reactor Trip Recovery procedure that requires 100% feedwater flow. EFW Pump B would be a plausible answer if the applicant determines that EFW Pump B has a greater capacity than EFW Pump AB. Part 2 is correct.
B. CORRECT: The inadvertent MSIS in the stem eliminated FW sources from MFW pumps and the AFW pump. The EFW motor driven pumps (EFW Pumps A and B) are 50% capacity. EFW Pump AB is 100% capacity. With the loss of EFW Pump AB, the Steam Generators no longer have 100% capacity feedwater flow and no longer meet the criteria in the Reactor Trip Recovery procedure. The diagnostic flow chart will direct the crew to enter OP-902-006, Loss of Feedwater Recovery Procedure.
Upon entry into OP-902-006, the crew will be directed to secure all RCPs.
C. Incorrect. Part 1 is correct. Part 2 is plausible because the old revision of OP-902-006 had a step to secure one RCP in each loop if 100% emergency feedwater flow was available to the Steam Generators.
D. Incorrect. EFW Pump AB supplies 100% capacity to the Steam Generators, therefore, the crew will not be required to enter OP-902-006 if EFW Pump AB is the only EFW Pump running. The applicant must determine that OP-902-006 entry is required. EFW Pump B would be a plausible answer if the applicant determines that EFW Pump B has a greater capacity than EFW Pump AB. Part 2 is plausible because the old revision of OP-902-006 had a step to secure one RCP in each loop if 100% emergency feedwater flow was available to the Steam Generators.
Technical Reference(s):
OP-902-001 pages 7, 16 Rev. 16 (Attach if not previously provided)
OP-902-009 Appendix 1 Note 2 (including version/revision number)
OP-902-006 page 6 Rev. 19 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE01 obj 12, 16 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 10 55.43
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 23 of 161 Comments: Discuss why student might consider EFW pump B plausible (distractors A and D). EFW Pump B would be a plausible answer if the applicant determines that EFW Pump B has a greater capacity than EFW Pump AB. Added this plausibility statement to explanations for distractors A and D.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 24 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
000055 EA2.01 Importance Rating 3.5 K/A Statement (055EA2.01) Station Blackout: Ability to determine and/or interpret the following as they apply to (EPE55) Station Blackout: Existing valve positioning.
Proposed Question:
RO 12 Rev:
0 Given:
Station Blackout has occurred The crew has entered OP-902-005, Station Blackout Loss of DC power has occurred to EFW Pump AB Turbine Governor Valve The control Room has dispatched the RCA watch to determine the status of EFW Pump AB Given these conditions, MS-416, EFW Pump AB Turbine Stop Valve is in the
____(1)____ position and MS-417, EFW Pump AB Turbine Governor is in the
____(2)____ position.
(1)
(2)
A.
open closed B.
open open C.
closed closed D.
closed open
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 25 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect. Part 1 is plausible because MS-416, EFW Pump AB Turbine Stop Valve, will close on the mechanical overspeed but the valve operator for this motor operated valve is still required to be taken to the closed position to reset the overspeed condition. This is necessary because MS-416 MOV has no power on the Station Blackout. Part 2 is plausible if the applicant determines that EFW Pump AB governor valve fails in the closed position and would not fail in an overspeed condition.
B. Incorrect. Part 1 is plausible because MS-416, EFW Pump AB Turbine Stop Valve, will close on the mechanical overspeed but the valve operator for this motor operated valve is still required to be taken to the closed position to reset the overspeed condition. This is necessary because MS-416 MOV has no power on the Station Blackout. Part 2 is correct.
C. Incorrect. Part 1 is correct. Part 2 is plausible if the applicant determines that EFW Pump AB governor valve fails in the closed position and would not fail in an overspeed condition.
D. CORRECT: On a loss of the AB-DC bus, EFW Pump AB governor valve will fail to the full open position causing EFW Pump AB to trip on a mechanical overspeed. This overspeed condition would close MS-416, EFW Pump AB Turbine Stop Valve through a mechanical leakage.
Technical Reference(s):
OP-902-005 page 12 Rev. 23 (Attach if not previously provided)
SD-EFW page 16 Rev. 18 (including version/revision number)
OP-901-313 page 15 Rev. 308 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-EFW00 obj. 6 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 7, 10 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 26 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
056 AK1.07 Importance Rating 4.0 K/A Statement (056AK1.07) Loss of Offsite Power: Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 56) Loss of Offsite Power (CFR: 41.5 / 41.7 / 45.7 / 45.8): Long term core cooling Proposed Question:
RO 13 Rev:
0 Given:
OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery has been implemented After 30 minutes, which of the following would indicate adequate single phase natural circulation flow per OP-902-003?
A. Thot is 538°F and rising; Tcold is 529°F and constant.
B. RCS Subcooling based on representative CET temperature is 26°F and constant.
C. Thot is 480°F with Representative CET temperature 492°F.
D. Steam Generator pressures are 450 PSIA with RCS Tcold 450°F.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 27 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect. Hot Leg temperature is not meeting natural circulation (NC) criteria.
Natural Circulation criteria requires both Hot Leg and Cold Leg temperature constant or lowering.
B. Incorrect. Subcooling is <28°F, which does not meet Natural Circulation criteria of greater than or equal to 28°F.
C. Incorrect. Th and CET temperature are greater than 10°F, which does not meet Natural Circulation criteria of less than 10°F.
D. CORRECT: Steam Generator pressure is approximately equal to saturation pressure for the existing Tcold. This requirement is a contingency action for verifying Natural Circulation.
Technical Reference(s):
OP-902-003 page 15 Revision 11 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE05 obj. 4 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 10 55.43 Comments: Delete "ONE" in stem. Add "per OP-902-003" after "flow" in stem. Deleted "ONE" in stem and added "per OP-902-003" after "flow" in stem.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 28 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
057 AA1.06 Importance Rating 3.8 K/A Statement (057AA1.06) LOSS OF VITAL AC ELECTRICALINSTRUMENT BUS: Ability to operate and/or monitor the following as they apply to (APE 57) LOSS OF VITAL AC ELECTRICALINSTRUMENT BUS: Manual control of components for which automatic control is lost Proposed Question:
RO 14 Rev:
0 Given:
Reactor Coolant System cooldown is in progress using the Atmospheric Dump Valves (ADVs)
The Main Condenser is unavailable PDP MC fails Due to the failure of PDP MC, Atmospheric Dump Valve 1 can be operated manually using the ____________.
A. local handwheel only B. local handwheel and local air station only C. local handwheel and ADV1 controller located on CP-8 only D. local handwheel, local air station and ADV1 controller on CP-8
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 29 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. The ADV can be operated using the local handwheel and local air station upon a loss of PDP MC. The student may assume that instrument air is not available because ADV1 does in fact fail closed upon a loss of PDP MC.
B. CORRECT: The ADV can be operated using the local handwheel and local air station only upon a loss of PDP MC.
C. Incorrect: The ADV can be operated using the local handwheel and local air station only upon a loss of PDP MC. The ADV1 controller on CP-8 is plausible because the ADVs can be operated using N2 cylinders. The student may assume that the loss of PDP MC affects only the instrument air to the valve and the use of the controller on CP-1 is available due to the nitrogen cylinders. This is not the case because the N2 cylinders use the same tubing as instrument air and is a backup in case instrument air is lost.
D. Incorrect. The ADV can be operated using the local handwheel and local air station only upon a loss of PDP MC. The student may assume that only automatic control of ADV1 is lost during a loss of PDP MC. If that were the case, this distractor would be correct.
Technical Reference(s):
OP-901-312 pages 55, 75 Revision 325 (Attach if not previously provided)
OP-005-004 pages 25-27 Rev. 37 (including version/revision number)
OP-901-511 page 19 Rev. 20 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO30 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 7,10 55.43
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 30 of 161 Comments: Discuss why student would think an ADV opening on a loss of power is plausible (distractors B and D). There are malfunctions where the ADVs fail open off and the off-normal procedures direct the crew to take manual control of the ADVs and close them (such as a failure low of the ADV setpoint or controller output failure). The student could determine that the SUPS failure affects the ADV in this manner or the student may determine that an ADV fails open to maintain cooling to a Steam Generator to prevent opening a MSSV upon an accident. Get rid of part 2 and derive the question using part
- 1. Got rid of part 2 and based the question on how ADV1 will be manually controlled.
Changed the question from a bank question to a new question. SAT.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 31 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
058 G2.1.19 Importance Rating 3.9 K/A Statement (058) Loss of DC Power: (G2.1.19) CONDUCT OF OPERATIONS: Ability to use available indications to evaluate system or component status.
Proposed Question:
RO 15 Rev:
0 Given:
Loss of 125 Volt TGB-DC Bus has occurred Crew has entered OP-901-313, Loss of a 125 Volt DC Bus The remote operation of the feeder breakers for the ____(1)____ feeder breakers is(are) lost.
All remote manual control and automatic protection of the switchgear and associated connected components are disabled for the ____(2)____.
(1)
(2)
A.
2 bus only 1 and 2 busses B.
2 bus only 2 bus only C. 1 and 2 busses 1 and 2 busses D. 1 and 2 busses 2 bus only
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 32 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: The remote operation of the 2 bus feeder breakers are lost upon a loss of 125V TGB-DC. The 1A and 1B busses control power are fed from A and B DC Safety busses, so they are still available (designed this way to ensure RCP overcurrent protection is from a safety bus). The control power for both the 1 busses and the 2 busses are from TGB-DC. These busses will lose all indication in the control room and locally and remote/manual remote control are lost.
B. Incorrect. Part 1 is correct. The control power for both the 1 busses and the 2 busses are from TGB-DC. These busses will lose all indication in the control room and locally and remote/manual remote control are lost.
C. Incorrect. The remote operation of the 2 bus feeder breakers are lost upon a loss of 125V TGB-DC. The 1A and 1B busses control power are fed from A and B DC Safety busses, so they are still available (designed this way to ensure RCP overcurrent protection is from a safety bus). Part 2 is correct.
D. Incorrect. The remote operation of the 2 bus feeder breakers are lost upon a loss of 125V TGB-DC. The 1A and 1B busses control power are fed from A and B DC Safety busses, so they are still available (designed this way to ensure RCP overcurrent protection is from a safety bus). The control power for both the 1 busses and the 2 busses are from TGB-DC. These busses will lose all indication in the control room and locally and remote/manual remote control are lost.
Technical Reference(s):
OP-901-313 pages 13 and 16 Rev 308 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PP03 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7
55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 33 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
062 AK2.09 Importance Rating 3.3 K/A Statement (062AK2.09) LOSS OF SERVICE WATER: Knowledge of the relationship between (APE62) LOSS OF SERVICE WATER and the following systems or components: AFW System Proposed Question:
RO 16 Rev:
0 Per OP-902-009 Appendix 10, Transferring EFW Pump Suction, the transfer of EFW pump suction to Auxiliary Component Cooling Water (ACCW) should be completed by a MINIMUM CSP level of __________ to prevent EFW Pump cavitation.
A. 5%
B. 10%
C. 11%
D. 25%
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 34 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Plausible because 5% is from an older revision to EOPs that did not take instrument uncertainties into account.
B. Incorrect. Plausible because 10% is when action is required for an RWSP low level.
C. CORRECT: Appendix 10 of OP-902-009 states Transfer of EFW Pump suction should be completed by a CSP level of 11% to prevent cavitation of EFW pumps.
D. Incorrect. The optimal recovery procedures and OI-038-000, EOP Expectations/Guidance procedures states that ACCW flow to EFW should not be established until the CSP contents have depleted. The lineup should commence at 25% CSP level, however, ACCW flow to the suction of EFW should be completed before a CSP level of 11% is reached to prevent cavitation of the EFW Pumps.
Technical Reference(s):
OP-902-009 Appendix 10 Rev. 323 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE01 obj. 6 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 8,10 55.43 Comments: Add "MINIMUM" prior to CSP in stem. Added "MINIMUM" prior to CSP in the stem. Put Minimum in CAPS. Changed MIMIMUM to CAPS. SAT.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 35 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
065 AK3.03 Importance Rating 3.6 K/A Statement (065AK3.03) Loss of Instrument Air: Knowledge of the reasons for the following responses and/or actions as they apply to (APE 65) LOSS OF Instrument Air: Knowing effects on plant operation of isolating certain equipment from instrument air Proposed Question:
RO 17 Rev:
0 Given:
Plant is in a refueling outage Shutdown Cooling Train A is in service and Train B is in standby SI-129A, LPSI Pump A Flow Control, is 20% open SI-415A, Shutdown Cooling HX A Temperature Control, is 50% open CC-963A, SDC HX A TCV is full open Shutdown Cooling Train A flow is 3000 gpm An instrument Air tubing rupture occurs at SI-129A, LPSI Pump A Flow Control. The crew entered OP-901-511, Loss of Instrument Air Malfunction.
The crew should manually throttle SI-129A in the ____(1)____ direction because RCS temperature is ____(2)____.
____(1)____
____(2)____
A.
closed lowering B.
closed rising C.
open lowering D.
open rising
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 36 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. Part 1 is correct. SI-415 does not respond automatically to SDC outlet temperature and will stay at 50% open. This failure will cause total SDC flow to rise and cause flow to bypass the SDC heat exchanger which will make RCS temperature rise.
B. CORRECT: SI-129A fails OPEN on a loss of air and will fail to the full open position.
OP-901-511 directs the crew to manually throttle closed SI-129A. SI-415 does not respond automatically to SDC outlet temperature and will stay at 50% open. This failure will cause total SDC flow to rise and cause flow to bypass the SDC heat exchanger which will make RCS temperature rise.
C. Incorrect. SI-129A fails OPEN on a loss of air and will fail to the full open position.
SI-415 does not respond automatically to SDC outlet temperature and will stay at 50% open. This failure will cause total SDC flow to rise and cause flow to bypass the SDC heat exchanger which will make RCS temperature rise. OP-901-511 directs the crew to manually throttle closed SI-129A.
D. Incorrect. SI-129A fails OPEN on a loss of air and will fail to the full open position.
OP-901-511 directs the crew to manually throttle closed SI-129A. Part 2 is correct.
Technical Reference(s):
OP-901-511 page 6 Rev. 19 (Attach if not previously provided)
SD-SDC Pages 6,7,14,39 Rev. 9 (including version/revision number)
OP-009-008 page 58 Revision 48 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO50 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 7
55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 37 of 161 Examination Outline Cross-
Reference:
1 Group #
1 K/A #
077 AA2.04 Importance Rating 3.6 K/A Statement (077AA2.04) GENERATOR VOLTAGE AND ELECTRIC Grid Disturbances: Ability to determine and/or interpret the following as they apply to (APE 77) GENERATOR VOLTAGE AND ELECTRIC Grid Disturbances: VAR Proposed Question:
RO 18 Rev:
0 Given:
Reactor power is 100%
A large load connected to the grid is lost causing a grid disturbance MVAR load changed from 20 MVAR out to 70 MVAR in The administrative limit for MVAR IN as defined in OP-010-004, Power Operations
__(1)__ being exceeded.
To restore MVAR load to 20 MVAR out, the crew should adjust the Main Generator voltage adjust regulator control switch to ____(2)____.
(1)
(2)
A.
is raise B.
is lower C.
is not raise D.
is not lower
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 38 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Part 1 is plausible because the applicant must know what the administrative limit for MVAR IN is to get this correct. Part 2 is correct.
B. Incorrect. Part 1 is plausible because the applicant must know what the administrative limit for MVAR IN is to get this correct. Part 2 is plausible because the applicant could determine taking the Voltage Adjust Regulator Switch to Lower would make the absolute number of MVAR go from 70 to 20.
C. CORRECT: In accordance with limitation 3.2.16 and step 9.8.1.9.1 in OP-010-004, Power Operations, the administrative limit for MVAR in is 75 MVAR. To raise MVARS (Less MVAR IN or More MVAR OUT), take the Voltage Adjust Regulator Switch to Raise.
D. Incorrect. Part 1 is correct. Part 2 is plausible because the applicant could determine taking the Voltage Adjust Regulator Switch to Lower would make the absolute number of MVAR go from 70 to 20.
Technical Reference(s):
OP-010-004 pages 7, 65 Rev. 341 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPN01 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 5,10 55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 39 of 161 Examination Outline Cross-
Reference:
1 Group #
2 K/A #
001 G2.4.12 Importance Rating 4.0 K/A Statement (001) (APE 1) Continuous Rod Withdrawal: (G2.4.12) Knowledge of operating crew responsibilities during emergency and abnormal operations Proposed Question:
RO 19 Rev:
0 Given:
Plant is at 5% power Group P CEAs are 85 inches withdrawn All other CEAs are at the Upper Electrical Limit ATC withdraws Group P CEAs 3 steps and releases the CEA Manual Shim switch CEA Group P CEAs continued stepping out Which of the following is performed FIRST per OP-901-102, CEA or CEDMCS Malfunction?
A. Adjust Turbine load to match Tave and Tref.
B. Place the CEDMCS Mode Select switch to OFF.
C. Trip the Reactor and GO TO OP-902-000, Standard Post Trip Actions.
D. Momentarily place the Manual Shim Switch to insert and then release.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 40 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. Matching Tave and Tref by adjusting turbine load is plausible and is the third step of this procedure section. Matching Tave and Tref is the first step in many events such as a dropped rod.
B. CORRECT: Placing the CEMCS mode select switch to OFF is the first step directed in the continuous movement of CEA group section of OP-901-102, CEA or CEDMCS Malfunction. This step is performed in an attempt to stop the CEA group movement. This is a quick event and this step is important for the RO to know and may be performed before the off-normal is officially entered. The Mode Select switch to OFF is the method used to attempt to stop rod motion. Matching Tave and Tref by adjusting turbine load is plausible and is the third step of this procedure section.
Matching Tave and Tref is the first step in many events such as a dropped rod.
C. Incorrect. Tripping the Reactor is performed when placing the CEDMCS mode select switch in OFF does not stop rod movement but is not the first step performed and not the preferred sequence.
D. Incorrect. Placing the CEA manual shim switch to insert and releasing it is not a step in the off-normal for continuous motion of a group of CEAs: however, it does hold the possibility of correcting the situation by exercising the switch contacts.
Technical Reference(s):
OP-901-102 page 17 Rev. 308 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO10 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 41 of 161 Examination Outline Cross-
Reference:
1 Group #
2 K/A #
003 AA2.09 Importance Rating 3.8 K/A Statement (003AA2.09) DROPPED Control Rod: Ability to determine and/or interpret the following as they apply to (APE 3) DROPPED Control Rod: Reactor Power Proposed Question:
RO 20 Rev:
0 Given:
Plant was operating at 80% when CEA 40 dropped into the core Crew has entered OP-901-102, CEA or CEDMCS Malfunction Crew is lowering power to comply with TS 3.1.3.1, Movable Control Assemblies-CEA position The crew must be at or below the minimum requirement of___(1)___ percent power within 30 minutes of the dropped rod. The highest permissible power that the down power can be stopped to be in compliance with TS 3.1.3.1 is when reactor power reaches ____(2)_____ percent.
(1)
(2)
A.
70 60 B.
75 60 C.
70 50 D.
75 50
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 42 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: COLR Figure 3 requires a power reduction of 10% 30 minutes from the time of the dropped rod. COLR Figure 3 requires a power reduction of 30% after a single CEA deviation, unless power is reduced to 60%, then no further reduction is required. Initial reactor power is 80%, therefore, the power reduction can be stopped at 60%.
B. Incorrect. Part 1 is plausible because COLR figure 3 is written in 5% increments.
Part 2 is correct.
C. Incorrect. Part 1 is correct. Part 2 is plausible because COLR Figure 3 requires a power reduction of 30% after a single CEA deviation, unless power is reduced to 60%, then no further reduction is required. Initial reactor power is 80%, therefore, power reduction to 50% would be correct if the floor of 60% is not known.
D. Incorrect. Part 1 is plausible because COLR figure 3 is written in 5% increments.
Part 2 is plausible because COLR Figure 3 requires a power reduction of 30% after a single CEA deviation, unless power is reduced to 60%, then no further reduction is required. Initial reactor power is 80%, therefore, power reduction to 50% would be correct if the floor of 60% is not known.
Technical Reference(s):
OP-901-102 page 12 Rev. 308 (Attach if not previously provided)
TS 3.1.3.1 and COLR Figure 3 (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO10 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 10 55.43
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 43 of 161 Comments: Distractor C is also correct as written. Restructure stem such that the second part of the question asks what the highest procedurally permissable power level is when the power reduction can be stopped. Changed part 2 to read The highest permissible power that the down power can be stopped to be in compliance with TS 3.1.3.1 is when reactor power reaches ____(2)_____ percent. Also, added the title of TS 3.1.3.1 to the stem.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 44 of 161 Examination Outline Cross-
Reference:
1 Group #
2 K/A #
032 AK3.02 Importance Rating 3.5 K/A Statement (032AK3.02) LOSS OF SOURCE RANGE Nuclear Instrumentation: Knowledge of the reasons for the following responses and/or actions as they apply to (APE 32) LOSS OF SOURCE RANGE Nuclear Instrumentation: Guidance contained in procedures for loss of source range NI Proposed Question:
RO 21 Rev:
0 Given:
Reactor Power is 5.5 X 10-8 Startup Channel 1 OFF NORMAL annunciates at CP-2 The HV Control switch in Startup Channel #1 drawer is selected to PRIMARY The annunciator response procedure will direct the crew to select ALTERNATE in Startup #1 channel drawer because ENI LOG ______ has failed high.
A. Channel A B. Channel B C. Channel C D. Channel D
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 45 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Log Channel A controls high voltage shutoff to Startup Channel 2 if the HV control Switch in Startup Channel 2 is selected to Primary B. Incorrect. Log Channel B controls high voltage shutoff to Startup Channel 2 if the HV control Switch in Startup Channel 2 is selected to Alternate C. CORRECT: The startup channels are de-energized by the 5X10-6% bistables of the selected log channel. Log Channel C controls high voltage shutoff to Startup Channel 1 if the HV control Switch in Startup Channel 1 is selected to Primary. The power source to startup channel 1 will be log channel D when the HV control switch is taken to alternate and High Voltage power will be restored D. Incorrect. Log Channel D controls high voltage shutoff to Startup Channel 1 if the HV control Switch in Startup Channel 1 is selected to Alternate.
Technical Reference(s):
OP-500-008 attachments 4.93 and 4.94. Rev. 26 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-ENI00 obj. 2 and 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 6, 10 55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 46 of 161 Examination Outline Cross-
Reference:
1 Group #
2 K/A #
033 AA1.02 Importance Rating 3.3 K/A Statement (033AA1.02) LOSS OF INTERMEDIATE RANGE Nuclear Instrumentation: Ability to operate and/or monitor the following as they apply to (APE 33) LOSS OF INTERMEDIATE RANGE Nuclear Instrumentation: Level trip bypass Proposed Question:
RO 22 Rev:
0 Given:
- Plant is in Mode 4
- The following Operating Bypasses are bypassed on all four channels:
o DNBR/LPD Trip o Low SG Flow Trip o High SG Level Trip
- Channel C Excore middle detector fails high Which of the following Channel C Operating bypasses should be in bypass following the middle detector failing high?
A. Hi Log Power Trip B. DNBR/LPD Trip C. Low SG Flow Trip D. High SG Level Trip
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 47 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect: Hi Log Power Trip bypass is automatically removed when power is
< 10-4%. The Hi Log Power trip bypass must be manually restored when power goes above 10-4%. Therefore, the Hi Log Power Trip is in service at the present condition and is still in service (not in bypass) after the log channel fails high.
B. Incorrect: DNBR/LPD Trip bypasses are automatically removed when power goes above 10-4%. Therefore, DNBR/LPD trip bypasses will be removed when its log channel fails high.
C. Incorrect. Low SG Flow Trip bypass is automatically removed when power goes above 8.5 X10-5%. Therefore, Low SG Flow trip bypasses will be removed when its log channel fails high.
D. CORRECT: High SG Level Trip bypass has no auto feature and is manually initiated and removed from service. This trip bypass is administratively controlled. Therefore, the log channel failing high has no effect on its operating bypass. The High SG Level Trip remains in bypass.
Technical Reference(s):
WLP-OPS-PPS00 pages 30-32 Rev. 18 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPS00 obj. 4 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2018 RO NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 2
55.43 Comments: Please discuss - explanations are not making sense to me. Will discuss and added words to the explanations to clear the confusion. Get rid of "one". Change "will" to "should". Got rid of "one". Changed "will" to "should". Good.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 48 of 161 Examination Outline Cross-
Reference:
1 Group #
2 K/A #
037 G2.2.22 Importance Rating 4.0 K/A Statement (037) (APE 37) Steam Generator Tube Leak: (G2.2.22) EQUIPMENT CONTROL:
Knowledge of limiting conditions for operation and safety limits Proposed Question:
RO 23 Rev:
0 Given:
- A Steam Generator Tube Leak is in progress and the crew has implemented OP-901-202, Steam Generator Tube Leakage or High Activity
- AE Discharge Radiation Monitor is in HIGH Alarm
- PSLR indicates 0.04 GPM into Steam Generator #1
- PSLR indicates 0.05 GPM into Steam Generator #2
- Secondary Coolant Specific Activity is 0.11 µci/gram DEI-131 Which of the following conditions will require a plant shutdown in accordance with OP-010-005, Plant Shutdown?
A. Secondary Coolant Specific Activity B. AE Discharge Radiation Monitor is in HIGH Alarm C. Primary to Secondary Leakage in Steam Generator #2 ONLY D. Combined Primary to Secondary Leakage in Steam Generator #1 and Steam Generator #2
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 49 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: OP-901-202 step 4 requires a plant shutdown in accordance with OP-010-005 if the Specific activity of the Secondary Coolant System is >.1 microci/gram Dose Equivalent I-131. This step complies with the actions required in TS 3.7.1.4.
This action is in effect if leakage is < 75 gpd, because if and steam generator leakage is > 75 gpd, a rapid plant power reduction is required.
B. Incorrect. AE Discharge Radiation Monitor is in HIGH Alarm is plausible because it is listed in OP-901-202 as the primary Rad Monitor which has the sensitivity to measure small Primary to Secondary Leakage. There is no required shutdown for this Rad Monitor being in high alarm.
C. Incorrect. Leakage in SG#2 is 72 gpd (.05 gpmx60x24). The limit in TS 3.4.5.2 and the requirement in step 3 of OP-901-202 is 75 gpd. No shutdown is required.
D. Incorrect. Plausible if the applicant determines that the combined leakage of the two steam generators meet the threshold of TS 3.4.5.2. TS 3.4.5.2 limits is for leakage in one steam generator.
Technical Reference(s):
OP-901-202 pages 9, 10 Rev. 16 (Attach if not previously provided)
TS 3.4.5.2 (including version/revision number)
TS 3.7.1.4 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO2 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 10 55.43 Comments: Delete "ONE" in stem. Add "ONLY" at the end of C, change "Leak" to "Leakage." Incorporated these three changes. Place only in caps. Placed only in caps. GOOD.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 50 of 161 Examination Outline Cross-
Reference:
1 Group #
2 K/A #
074 EK2.07 Importance Rating 3.4 K/A Statement (000074EK2.03) Knowledge of the relationship between (EPE 74) Inadequate Core Cooling and the following systems or components (CFR: 41.8 / 41.10 / 45.3): Main steam system Proposed Question:
RO 24 Rev:
0 Per TS 3.7.1.7, Atmospheric Dump Valves, the Atmospheric Dump Valve controller setpoints are required to be operable prior to exceeding ____(1)____ percent power.
The basis for this requirement is to mitigate the effects of a ____(2)_____.
(1)
(2)
A.
70 Small Break LOCA B.
70 Station Blackout C.
85 Small Break LOCA D.
85 Station Blackout
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 51 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: Per TS 3.7.1.7, the ADV automatic actuation channels shall be operable greater than 70% Rated Thermal Power. Per TS 3.7.1.7 basis, above 70% power, an ADV is required along with a HPSI Train to mitigate the effects of a SBLOCA to ensure adequate core cooling.
B. Incorrect: Per TS 3.7.1.7 basis, above 70% power, an ADV is required along with a HPSI Train to mitigate the effects of a SBLOCA. The station blackout is credible due to the importance of the ADVs during a loss of all power.
C. Incorrect: 85% power is the power level that the plant is required to reduce to in the event of one MSSV inoperable.
D. Incorrect. 85% power is the power level that the plant is required to reduce to in the event of one MSSV inoperable. Per TS 3.7.1.7 basis, above 70% power, an ADV is required along with a HPSI Train to mitigate the effects of a SBLOCA to ensure adequate core cooling.
Technical Reference(s):
TS 3.7.1.7 (Attach if not previously provided)
TS 3.7.1.7 basis (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS MS00 obj. 6 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2014 RO NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 4
55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 52 of 161 Examination Outline Cross-
Reference:
1 Group #
2 K/A #
CE A16 AK1.06 Importance Rating 3.8 K/A Statement (CE A16AK1.06) EXCESS RCS Leakage: Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (CE A16)
EXCESS RCS Leakage: Methods for quantifying an RCS leak Proposed Question:
RO 25 Rev:
0 Given:
Plant is at 100% power The crew has entered OP-901-111, Reactor Coolant System Leak Charging Pump A is running Pressurizer level is 55% and slowly lowering The Standby Charging Pumps selector switch is selected to the B-AB position To allow for a more accurate leak rate determination, OP-901-111, Reactor Coolant System Leak, provides the guidance to ____(1)____.
The ATC should determine an RCS leak rate by subtracting the total of ____(2)____.
(1)
(2)
A. place Charging Pump B control switch to the ON position Charging flow and RCP CBO flow from Letdown flow B. place the Letdown Flow controller to manual Charging flow and RCP CBO flow from Letdown flow C. place the Letdown Flow controller to manual Letdown flow and RCP CBO flow from Charging flow D. place Charging Pump B control switch to the ON position Letdown flow and RCP CBO flow from Charging flow
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 53 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect. Part 1 is correct. A leakrate will be determined by subtracting the total of letdown flow and RCP CBO flow from charging flow.
B. Incorrect. Plausible because placing the letdown flow controller to manual will maintain a steady letdown flow, but this is not what OP-901-111 directs. A leakrate will be determined by subtracting the total of letdown flow and RCP CBO flow from charging flow.
C. Incorrect. Plausible because placing the letdown flow controller to manual will maintain a steady letdown flow, but this is not what OP-901-111 directs. Part 2 is correct.
D. CORRECT: Note in OP-901-111 states if RCS leakage will result in a backup charging Pump cycling to maintain pressurizer level, starting and continuously running (place to on) an additional Charging Pump will allow for a more accurate leakrate determination. A leakrate will be determined by subtracting the total of letdown flow and RCP CBO flow from charging flow.
Technical Reference(s):
OP-901-111 page 8 Rev. 307 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO10 obj. 3 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2015 NRC RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 5, 10 55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 54 of 161 Examination Outline Cross-
Reference:
1 Group #
2 K/A #
CE E13 EA1.14 Importance Rating 2.7 K/A Statement (CE13EA1.14) LOSS OF FORCED CIRCULATION AND/OR LOOP AND/OR A BLACKOUT: Ability to operate and/or monitor the following as they apply to (CE E13)
LOSS OF FORCED CIRCULATION AND/OR LOOP AND/OR A BLACKOUT: MFW system Proposed Question:
RO 26 Rev:
0 Given:
Power is 100%
SG-ILR-1111, Steam Generator 1 Narrow Range level indicator located on CP-1 has failed low A subsequent reactor trip occurs due to a loss of Component Cooling Water to the Reactor Coolant pumps requiring entry into OP-902-003, Loss of Offsite Power/Loss of Forced Flow Recovery Procedure The expected post trip responses to these conditions are that FW IHIC 1107 Main Feedwater Pump A speed controller ___(1)___ and FW IHIC1111, Main Feedwater Regulating Valve A and FW IHIC1105 Startup Feedwater Regulating Valve A Controller
__(2)___.
(1)
(2)
A.
remains at 4500 RPM remain at their pre-trip positions B.
remains at 4500 RPM reposition to their Reactor Trip Positions C.
lowers to 3900 RPM remain at their pre-trip positions D.
lowers to 3900 RPM reposition to their Reactor Trip Positions
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 55 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Part 1 is plausible if the student is not aware that upon the reactor trip the Feed pump speed controller swaps from manual (in manual due to the level deviation) to auto and will go to 3900 RPM. Part 2 is correct.
B. Incorrect. Part 1 is plausible if the student is not aware that upon the reactor trip the Feed pump speed controller swaps from manual (in manual due to the level deviation) to auto and will go to 3900 RPM. Part 2 is plausible if the student does not realize that the Main feedwater regulating valve controller and the Startup Feedwater Regulating Valve controller has swapped to manual due to the level deviation.
C. CORRECT: Level deviation exists in the FWCS #1. The level deviation shifts the Feed pump speed controller, Main feedwater regulating valve controller and the Startup Feedwater Regulating Valve controllers to manual. Upon the reactor trip, Feed pump speed controller swaps to auto and goes to 3900 RPM. The Main Feedwater Regulating Valve Controller and Startup Feedwater Regulating Valves are still in manual and do NOT go to Reactor Trip Override position (remain in their pre-trip positions). The crew will be directed to place FWCS in RTO during Standard Post Trip Actions.
D. Incorrect. Part 1 is correct. Part 2 is plausible if the student does not realize that the Main feedwater regulating valve controller and the Startup Feedwater Regulating Valve controller has swapped to manual due to the level deviation.
Technical Reference(s):
OP-901-201 page 5, Att. 1 Rev. 7 (Attach if not previously provided)
OP-902-000 page 11 Rev. 17 (including version/revision number)
WLP-OPS-PPO20 slide 20 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO20 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 4,10 55.43 Comments: Close FRV A is in 3 out of four distractors, meaning it's probably in the correct answer. Adjust the start-up FRV between 13-21% open is in two distractors while closing it is in one. This cues the answer is very probably C or D without reading the
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 56 of 161 question. Changed distractor A and its explanation to include closing Main Feedwater Regulating Valve A. Put MFRV in the stem and try to even out distractors. This question is new. Needs a review.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 57 of 161 Examination Outline Cross-
Reference:
1 Group #
2 K/A #
003 A1.05 Importance Rating 3.4 K/A Statement (003 A1.05) REACTOR COOLANT PUMP SYSTEM: Ability to predict and/ or monitor changes in parameters associated with operation of the REACTOR COOLANT PUMP SYSTEM including: RCS flow Proposed Question:
RO 27 Rev:
0 Given:
The reactor was manually tripped due to 1A RCP ARRD High Temperature 1A RCP has been secured Five minutes later, the ATC reports that the RCP PMC Mimic indicates RCP 1A speed is 600 rpm OP-901-130, Reactor Coolant Pump Malfunction, provides the guidance to trip the reactor if ARRD temperature exceeds ____(1)____ °F.
Based on the above conditions, the crew should ______(2)______.
(1)
(2)
A.
225 remove reactor coolant pump 1B from service only B.
210 remove reactor coolant pump 1B from service only C.
225 remove all reactor coolant pumps from service D.
210 remove all reactor coolant pumps from service
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 58 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Part 1 is correct. With the given conditions, RCP 1A is reverse rotating even though speed on the RCP mimic is indicating a positive number. This guidance on RCP speed indication is given in a note in the Reverse rotation section of OP-901-130. If RCP is reverse rotating, all RCPs must be secured. Part 2 is plausible because RCP 1B is on the same loop as RCP 1A and forced flow would be maintained.
B. Incorrect. Per OP-901-130, the crew is required to trip the reactor and secure the affected RCP when ARRD temperature exceeds 225 °F. At 210°F, a plant shutdown must be commenced. With the given conditions, RCP 1A is reverse rotating. Part 2 is plausible because RCP 1B is on the same loop as RCP 1A and forced flow would be maintained C. CORRECT: Per OP-901-130, the crew is required to trip the reactor and secure the affected RCP when ARRD temperature exceeds 225 °F. With the given conditions, RCP 1A is reverse rotating even though speed on the RCP mimic is indicating a positive number. This guidance on RCP speed indication is given in a note in the Reverse rotation section of OP-901-130. If a RCP is reverse rotating, all RCPs must be secured. The question meets the K/A because the operator is monitoring for reverse flow through the RCP.
D. Incorrect. Per OP-901-130, the crew is required to trip the reactor and secure the affected RCP when ARRD temperature exceeds 225 °F. At 210°F, a plant shutdown must be commenced. Part 2 is correct.
Technical Reference(s):
OP-901-130 page 7, 19, 21 Revision 12 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO10 obj. 3 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2015 NRC RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 10 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 59 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
003 G2.1.28 Importance Rating 4.1 K/A Statement (003) (SF4P RCP) REACTOR COOLANT PUMP SYSTEM: (G2.1.28) CONDUCT OF OPERATIONS: Knowledge of the purpose and function of major system components and controls Proposed Question:
RO 28 Rev:
0 The ATC notes the following indications on RCP 1A:
- Vapor Seal pressure is 45 PSIG
- Upper Seal pressure is 910 PSIG
- Middle Seal pressure is 1950 PSIG
A. Vapor B. Upper C. Middle D. Lower
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 60 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect. Normal pressure range is 25 to 45 PSIG. Pressure is high in the band due to a degraded lower seal.
B. Incorrect. Normal pressure range is 585 to 915 PSIG. Upper seal pressure is high in the band due to a degraded lower seal. The upper seal is working properly.
C. Incorrect. Normal pressure range is 1237 to 1815 PSIG. The middle seal pressure is out of band high due a degraded lower seal.
D. CORRECT: Normal pressure range is 1237 to 1815 PSIG. The middle seal pressure is out of band high due a degraded lower seal. These parameters are indicative of a degraded lower seal causing middle seal pressure to be high out of band.
Technical Reference(s):
OP-901-130 page 9 Rev. 12 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO10 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7,10 55.43 Comments: Delete "ONE" in stem. Discuss possibility of changing middle seal parameter to a lower value (around 1950?) to make the question a little more discriminating.
Deleted "ONE" in the stem. Changed middle seal pressure to 1950 psig as recommended. Changed all explanations to indicate a degraded seal instead of a failed seal is in progress. A failed seal is indicated by D/P < 100 psid. Added the word pressure to all distractors.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 61 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
004 A2.22 Importance Rating 3.4 K/A Statement (004A2.22) CHEMICAL AND VOLUME CONTROL SYSTEM: Ability to (a) predict the impacts of the following on the (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Mismatch of letdown and charging flows Proposed Question:
RO 29 Rev:
0 Given:
Plant is operating at 100% power Pressurizer Level Control CHANNEL SELECT switch is selected to Channel Y Now:
Pressurizer Level Control Channel RC-ILT-0110Y fails high Pressurizer level will initially __(1)__. If the non-faulted channel is selected prior to actual level being restored to program level, the crew should expect standby charging pumps to automatically __(2)__.
(1)
(2)
A.
rise start B.
lower start C.
rise secure D.
lower secure
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 62 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. With the in-service pressurizer level control channel failed high, the PLCS will see a higher level than setpoint and raise letdown flow which would cause actual pressurizer level to lower and. Part 2 is correct.
B. CORRECT: With the in-service pressurizer level control channel failed high, the PLCS will see a higher level than setpoint and raise letdown flow which would cause actual pressurizer level to lower. If the non-faulted channel is selected prior to actual level being restored to program level, the crew should expect standby charging pumps to auto start. This is not desired and there is a note in the off-normal (OP-901-110) to alert the operator of this possibility.
C. Incorrect. With the in-service pressurizer level control channel failed high, the PLCS will see a higher level than setpoint and raise letdown flow which would cause actual pressurizer level to lower. Part 2 is plausible because the student must recognize what actual pressurizer level is doing and what would happen when the selected channel is moved to the faulted channel to the non-faulted channel.
D. Incorrect. Part 1 is correct. Part 2 is plausible because any standby charging pumps running will have secured when a level control channel failed high, but the student must recognize what will happen once the non-faulted channel is selected.
Technical Reference(s):
OP-901-110 page 7 Rev. 11 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO1 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7,10 55.43
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 63 of 161 Comments: Appears to be identical to event 3 in scenario 1. This question is identical.
Need to replace this question. Replaced this question. The new question uses the Y control channel for PLCS and the revised question will fail this control channel high vise low as written in the scenario. Verified this question does not overlap the audit written or the previous two NRC exams. Discuss, appears that action (2) doesn't change and the scenario would still probably cue them onto this. Develop a new question. Changed part 2 of the question to eliminate any overlap.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 64 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
004 K6.07 Importance Rating 3.4 K/A Statement (004K6.07) CHEMICAL AND VOLUME CONTROL SYSTEM: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM: Regenerative and nonregenerative heat exchangers.
Proposed Question:
RO 30 Rev:
0 Given:
Plant operating at 100% power Charging Pump B is running with Charging Pumps A and AB in standby Upon a trip of Charging Pump B, the first backup charging pump is designed to start at a pressurizer level of __(1)__ %. If uncorrected, letdown should isolate on __(2)__ heat exchanger outlet temperature.
(1)
(2)
A.
51.7 Regenerative B.
51.7 Letdown C.
53.1 Letdown D.
53.1 Regenerative
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 65 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect: The PLCS is designed such that the first Backup Charging Pump will start at a Pressurizer level deviation of 2.5%. The second Charging Pump will start at a level deviation of 3.9% which would equate to a level of 51.7% at 100% power. Part 2 is correct.
B. Incorrect. The PLCS is designed such that the first Backup Charging Pump will start at a Pressurizer level deviation of 2.5%. The second Charging Pump will start at a level deviation of 3.9% which would equate to a level of 51.7% at 100% power. A loss of Charging flow will raise Regenerative HX outlet temperature. If temperature reaches 470ºF, letdown will isolate.
The letdown HX is downstream of the Regenerative HX and is cooled by CCW C. Incorrect. Part 1 is correct. A loss of Charging flow will raise Regenerative HX outlet temperature. If temperature reaches 470ºF, letdown will isolate. The letdown HX is downstream of the Regenerative HX and is cooled by CCW.
D. CORRECT: The PLCS is designed such that the first Backup Charging Pump will start at a Pressurizer level deviation of 2.5%. The applicant must know that Pressurizer level at 100%
power is programmed at 55.6%. Charging flow is the cooling medium for the Regenerative HX. Therefore, a loss of Charging flow will raise Regenerative HX outlet temperature. If temperature reaches 470ºF, letdown will isolate.
Technical Reference(s):
OP-901-112 page 5 and 8 Revision 11 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO10 obj. 3 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2017 NRC RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7,10 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 66 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
005 K6.16 Importance Rating 3.9 K/A Statement (005K6.16) RESIDUAL HEAT REMOVAL SYSTEM: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF4P RHR) RESIDUAL HEAT REMOVAL SYSTEM: Injection and/or recirculation valves Proposed Question:
RO 31 Rev:
0 Given:
An RCS drain down to less than 20 feet MSL is in progress in accordance with OP-001-003, RCS Drain Down Shutdown Cooling (SDC) Train A is in service LPSI Flow Control Valves (SI-138A and SI-139A) have been placed in their transient flow limiting positon Throttling the in-service LPSI Flow control valves to their transient flow limiting positions will limit maximum SDC Train A flow to __(1)__ gpm. This is performed to prevent
__(2)__
(1)
(2)
A.
3,000 vortexing in the RCS B.
3,000 diverting flow from the SDC Heat Exchanger C.
4,000 vortexing in the RCS D.
4,000 diverting flow from the SDC Heat Exchanger
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 67 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: Throttling the in-service SDC train LPSI Flow control valves is performed to limit maximum Transient SDC flow to 3000 gpm while the RCS is at a lowered inventory condition (20 feet MSL).This high flow could occur if SI-129 (SDC Flow Control Valve) fails open. Flow is limited to 3000 gpm to prevent vortexing in the RCS.
B. Incorrect. Part 1 is correct. Part 2 is plausible because this is the reason flow must not be taken to greater than 3,000 gpm if the LPSI FCVs are throttled, but this not the reason the LPSI FCVs are throttled.
C. Incorrect. Part 1 is plausible because both 3000 gpm and 4000 gpm are Tech Spec required flow rates based on hours after shutdown and both numbers are referenced to in the RCS drain down procedure (OP-001-003). Part 2 is correct.
D. Incorrect. Part 1 is plausible because both 3000 gpm and 4000 gpm are Tech Spec required flow rates based on hours after shutdown and both numbers are referenced to in the RCS drain down procedure (OP-001-003). Part 2 is plausible because this is the reason flow must not be taken to greater than 3,000 gpm if the LPSI FCVs are throttled, but this not the reason the LPSI FCVs are throttled.
Technical Reference(s):
OP-001-003 page 38 Revision 328 (Attach if not previously provided)
WLP-OPS-REQ13 slide 118 notes Rev. 28 (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-REQ13 obj. 1 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 7,10 55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 68 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
006 A2.02 Importance Rating 3.9 K/A Statement (006A2.02) EMERGENCY CORE COOLING SYSTEM: Ability to (a) predict the impacts of the following on the (SF2; SF3 ECCS) EMERGENCY CORE COOLING SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Loss of flowpath Proposed Question:
RO 32 Rev:
0 Given:
A LOCA occurred 15 minutes ago The crew has entered OP-902-002, Loss of Coolant Accident Recovery RCS Pressure is 500 psia and stable HPSI flow to Cold Leg 1A is zero gpm LPSI flow to both RCS loops is zero gpm In accordance with the HPSI and LPSI flow curves located in OP-902-009, Standard Appendices, which of the following is true?
A. Both HPSI and LPSI flow curves are being met B. Both HPSI and LPSI flow curves are not being met.
C. HPSI flow curves are met and the LPSI flow curves are not met.
D. LPSI flow curves are met and the HPSI flow curves are not met.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 69 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect. The current RCS pressure is above 200 psia, which is above LPSI shutoff head. Therefore, LPSI flow is meeting the curve in Attachment 2F. HPSI flow curves are not being met, because one injection line is below the required curve. Plausible because only one LPSI train has to meet the curve to obtain required flow.
B. Incorrect. The applicant could assume LPSI flow is not within the curve if it is not determined that RCS pressure is above LPSI shutoff head. HPSI flow curves are not met.
C. Incorrect. The applicant could assume LPSI flow is not within the curve if it is not determined that RCS pressure is above LPSI shutoff head. Attachment 2E of OP-902-009 provides the required HPSI flow for the applicable RCS pressure. The required flow is for each injection line. With one injection line below the curve, HPSI flow is not being met.
D. CORRECT: Attachment 2E of OP-902-009 provides the required HPSI flow for the applicable RCS pressure. The required flow is for each injection line. With one injection line below the curve, HPSI flow is not being met. The current RCS pressure is above 200 psia, which is above LPSI shutoff head. Therefore, LPSI flow is meeting the curve in Attachment 2F.
Technical Reference(s):
OP-902-009 Attachments 2E and 2F Rev. 323 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE01 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7,10 55.43
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 70 of 161 Comments: Stem cues that the HPSI flow curve is not met, making only B and D as plausible distractors. Changed the stem to state HPSI flow to Cold Leg 1A is zero gpm instead of HPSI flow is not meeting the HPSI flow curve. This question is valid because the student must know that if any HPSI flow leg is not meeting the curves than the HPSI curve is considered not met. This is different than the LPSI flow curves which only requires one train to meet the curves. Delete the 4th bullet in the stem. Deleted the 4th bullet in the stem. Good.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 71 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
007 A2.02 Importance Rating 3.6 K/A Statement (007A2.02) PRESSURIZER RELIEF/QUENCH TANK SYSTEM: Ability to (a) predict the impacts of the following on the (SF5 PRTS) PRESSURIZER RELIEF/QUENCH TANK SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Abnormal pressure in the PRT/quench tank Proposed Question:
RO 33 Rev:
0 Given:
- Plant is at 100% power
- The following annunciators are received:
QUENCH TANK PRESSURE HI QUENCH TANK LEVEL HI/LO The crew should monitor pressure in the ____(1)____ tank while draining the Quench Tank. If pressure in the Quench Tank were allowed to rise, the Quench tank rupture disc should rupture at a MINIMUM pressure of ____(2)____.
(1)
(2)
A.
holdup 124 psig B.
holdup 150 psig C.
reactor drain 124 psig D.
reactor drain 150 psig
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 72 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Part 1 is plausible because the holdup tanks accept borated waste water but not from the Quench Tank. Part 2 is correct.
B. Incorrect. Part 1 is plausible because the holdup tanks accept borated waste water but not from the Quench Tank. Part 2 is plausible because CBO would divert to the quench tank at a pressure of 150 psig.
C. CORRECT: The annunciator response and Boron Management procedure direct the crew to monitor pressure in the Reactor Drain Tank while draining the quench tank.
The annunciator response states that the Quench Tank rupture disc will rupture at 124 psig.
D. Incorrect. Part 1 is correct. Part 2 is plausible because CBO would divert to the quench tank at a pressure of 150 psig.
Technical Reference(s):
OP-500-008 Attachment 4.2 and 4.12 Rev. 48 (Attach if not previously provided)
OP-007-001 page 87 Revision 40 (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-RCS00 obj. 2 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 7
55.43 Comments: FIRST TEN. In stem, "is" should be "are." Two correct answers as written as the disk would certainly rupture at 150 psig if it would rupture at 124 psig. Add "MINIMUM" prior to "pressure" and change "would" to "should" in stem. Question needs LOD and CFR information. Incorporated all of the requested changes. Added LOD and CFR information. Place MIMIMUM in caps. Placed MIMIMUM in caps. SAT.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 73 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
007 A3.01 Importance Rating 3.4 K/A Statement (007A3.01) PRESSURIZER RELIEF/QUENCH TANK SYSTEM: Ability to monitor automatic features of the (SF5 PRTS) PRESSURIZER RELIEF/QUENCH TANK SYSTEM, including: Components that discharge to the PRT/quench tank Proposed Question:
RO 34 Rev:
0 A Steam Generator Tube Rupture has occurred resulting in an automatic Safety Injection Actuation Signal (SIAS) and Containment Isolation Actuation Signal (CIAS).
Realignment of ___(1)____ should result in a rise in Quench Tank pressure and temperature. This piping is normally aligned to the ___(2)____.
(1)
(2)
A.
RCP Control Bleedoff Volume Control Tank B.
RCP Vapor Seal Leak Off Volume Control Tank C.
RCP Control Bleedoff Containment Sump D.
RCP Vapor Seal Leak Off Containment Sump
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 74 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: RC-606, RCP Control Bleedoff Inside Containment Isolation Valve closes on a CIAS, redirecting RCP control bleedoff to the quench tank through a relief valve (RC-603).Controlled bleedoff from the Reactor Coolant Pumps is normally aligned to the Volume Control Tank (VCT).
B. Incorrect. RCP Vapor seal leakage is directed to the containment sump at all times.
Normally aligned to the VCT is plausible because RCP CBO is normally aligned to the VCT.
C. Incorrect. Part 1 is correct. Part 2 is plausible because RCP Vapor Seal Leakage is normally aligned to the containment sump.
D. Incorrect. RCP Vapor seal leakage is directed to the containment sump at all times.
Part 2 is correct.
Technical Reference(s):
SD-CVC pages 39, 40, Figure 9 Rev. 20 (Attach if not previously provided)
SD-RCS page 20 Rev. 26 (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-RCS00 obj. 2 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7
55.43 Comments: Discuss alternatives to the word "could" in stem, as almost anything "could" happen. Changed "could" to "should".
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 75 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
008 A4.04 Importance Rating 2.8 K/A Statement (008A4.04) COMPONENT COOLING WATER SYSTEM: Ability to manually operate and/or monitor the (SF8 CCW) COMPONENT COOLING WATER SYSTEM in the control room: Startup of a CCW pump when the system is shut down Proposed Question:
RO 35 Rev:
0 Given:
Component Cooling Water (CCW) pumps are being started for a system startup in accordance with OP-002-003, CCW System Startup Lowering CCW temperature may cause containment pressure to lower. Lowering containment pressure will cause indicated containment spray riser level to __(1)__.
Lowering CCW temperature and Letdown temperature may __(2)__ boron from CVCS Ion Exchanger effluent.
(1)
(2)
A.
rise remove B.
rise release C.
lower remove D.
lower release
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 76 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Part 1 is plausible because the applicant must know how containment pressure will affect riser levels. Part 2 is correct.
B. Incorrect. Part 1 is plausible because the applicant must know how containment pressure will affect riser levels. Part 2 is plausible if the applicant is not aware of the correlation between CCW temperature and reactivity.
C. CORRECT: In accordance with the CCW system startup section of OP-002-003, changing CCW temperature will cause changes in containment pressure. Lowering containment pressure will cause indicated containment spray riser level to lower.
Lowering letdown temperature may remove boron from ion exchanger effluent in the CVCS system. This would result in a corresponding increase in reactor power.
D. Incorrect. Part 1 is correct. Part 2 is plausible if the applicant is not aware of the correlation between CCW temperature and reactivity.
Technical Reference(s):
OP-002-003 page 10 Revision 322 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-CC00 Rev. 44 obj. 8 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 10 55.43 Comments: FIRST TEN. Question needs LOD and CFR information. Discuss; I remember the reactivity event at Beaver Valley involved a failure of the temperature control valve to the non-regenerative HX; would like to fully understand how just a change in CCW temp could cause this event. Added LOD and CFR information.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 77 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
010 A3.03 Importance Rating 3.3 K/A Statement (010A3.03) PRESSURIZER PRESSURE CONTROL SYSTEM: Ability to monitor automatic features of the (SF3 PZR PCS) PRESSURIZER PRESSURE CONTROL SYSTEM, including: PZR heater operation Proposed Question:
RO 36 Rev:
0 Given:
Plant is at 100% power RCS pressure reduces to a minimum of 2210 PSIA due to a dropped rod event The ATC should verify that the Pressurizer Proportional heaters are at a ____(1)_____
% firing rate. The Pressurizer backup heaters should be _____(2)_____.
(1)
(2)
A.
100 energized B.
100 de-energized C.
67 energized D.
67 de-energized
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 78 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. Part 1 is correct. The Pressurizer backup heaters energize at an RCS pressure of 2200 psia. The stem indicates that RCS pressure is 2210 psia, therefore the backup heaters are de-energized. Part 2 is plausible because the student could assume that the backup heaters energize at 2225 psia.
B. CORRECT: The Pressurizer proportional heaters should be at maximum firing rate at an RCS pressure of 2225 psia. The Pressurizer backup heaters energize at an RCS pressure of 2200 psia. The stem indicates that RCS pressure is 2210 psia, therefore the backup heaters are de-energized.
C. Incorrect. Part 1 is plausible because the pressurizer controller output will be at 67%
when it is giving the proportional heaters a signal to fire at 100%. Part 2 is plausible because the student could assume that the backup heaters energize at 2225 psia.
This is the pressure that the proportional heaters are firing at 100%.
D. Incorrect. Part 1 is plausible because the pressurizer controller output will be at 67%
when it is giving the proportional heaters a signal to fire at 100%. Part 2 is correct.
Technical Reference(s):
SD-PLC pages 25-27 Rev. 12 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO10 obj. 3 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2017 NRC RO exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7,10 55.43 Comments: Looks identical to event 2 in scenario 3. It is identical. Need to replace this question. This question has been replaced. Still need to send references but question is good.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 79 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
012 K2.01 Importance Rating 4.0 K/A Statement (012K2.01) REACTOR PROTECTION SYSTEM: Knowledge of electrical power supplies to the following: (SF7 RPS) REACTOR PROTECTION SYSTEM RPS channels, components, and interconnections Proposed Question:
RO 37 Rev:
0 Given:
The plant is at 100% power A loss of PDP MD occurs Reactor Trip Switchgear breakers _____(1)_____ open and a reactor trip
_______(2)______.
(1)
(2)
A.
3, 4, 7, and 8 occurs B.
3, 4, 7, and 8 does not occur C.
1, 2, 5, and 6 occurs D.
1, 2, 5, and 6 does not occur
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 80 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. Correct breakers but reactor trip does not occur, as power to CEDMCS is not interrupted with these reactor trip breakers open. Reactor trip is p B. CORRECT: On a loss of SUPS MD, Reactor trip breakers 3, 4, 7, and 8 open but power is still available to CEDMCS.
C. Incorrect. Reactor trip breakers 1, 2, 5, and 6 are A train powered and are not affected. A reactor trip would still not occur.
D. Incorrect. Reactor trip breakers 1, 2, 5, and 6 are A train powered and are not affected. A reactor trip would still not occur Technical Reference(s):
OP-901-312 page 18 Rev. 325 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO50 obj. 3 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2015 NRC RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 6
55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 81 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
013 A1.16 Importance Rating 2.9 K/A Statement (013A1.16) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM: Ability to predict and/or monitor changes in parameters associated with operation of the (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM, including:
Auxiliary building HVAC system status Proposed Question:
RO 38 Rev:
0 Given:
Controlled Ventilation Area System (CVAS) Filtration Unit A is running for OP-903-124, CVAS Pressure Boundary Testing when a Loss of Cooling Accident occurs RCS pressure is 1670 psia Containment pressure is 16.9 psia What should be the present status of the Controlled Ventilation Filtration Units?
A. Both CVAS Filtration Units are secured B. Both CVAS Filtration Units are running C. Only CVAS Filtration Unit A is running D. Only CVAS Filtration Unit B is running
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 82 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Plausible if the applicant is not aware that CVAS filtration units get a start on a SIAS. It could be assumed the unit that is running for surveillance secures for EDG loading limitations.
B. Incorrect. Plausible because both units start on a SIAS if one unit was not already running.
C. CORRECT: The applicant must first determine that a SIAS has occurred by recognizing that pressure (<1684 psia) meets the criteria. Containment pressure does not meet the criteria (>17.1 psia). CVAS provides a safety function during a design basis accident after a Safety Injection Actuation signal. Both fans will start on the SIAS. If one CVAS Filtration unit is already operating, the standby unit will not start.
D. Incorrect. Plausible if the applicant determines that the unit not started by the SIAS secures and the other unit gets the start signal from the SIAS.
Technical Reference(s):
SD-HVR page 40 Rev.15 (Attach if not previously provided)
SD-PPS page 43 Rev. 23 (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-HVR00 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7
55.43 Comments: FIRST TEN. In stem, change "is" to "should be." Question needs LOD and CFR information. Made all changes as requested. Stem still needs to be changed.
Changed the stem to should be.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 83 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
013 K4.06 Importance Rating 4.1 K/A Statement (013K4.06) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM: Knowledge of (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM design features and/or interlocks that provide for the following: Recirculation actuation/reset Proposed Question:
RO 39 Rev:
0 Recirculation Actuation Signal (RAS) occurs at an RWSP level of ____(1)____ percent.
Recirculation Actuation Signal can be initiated manually from the ____(2)____.
(1)
(2)
A.
10 auxiliary relay cabinets in the RAB switchgear only B.
10 control room and auxiliary relay cabinets in the RAB switchgear C.
20 control room and auxiliary relay cabinets in the RAB switchgear D.
20 auxiliary relay cabinets in the RAB switchgear only
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 84 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: Recirculation Actuation Signal (RAS) occurs at an RWSP level of 10%.
An RAS signal is the only ESFAS signal that cannot be initiated from the Control Room. It can only be initiated from auxiliary relay cabinets in the RAB switchgear.
B. Incorrect. Part 1 is correct. Part 2 is plausible because an RAS signal is the only ESFAS signal that cannot be initiated from the Control Room. It can only be initiated from auxiliary relay cabinets in the RAB switchgear.
C. Incorrect. Part 1 is plausible because other ESFAS actions occur at 20% such as bypassing High SG water level trip and actions that occur with the CSP. Part 2 is plausible because an RAS signal is the only ESFAS signal that cannot be initiated from the Control Room. It can only be initiated from auxiliary relay cabinets in the RAB switchgear.
D. Incorrect. Part 1 is plausible because other ESFAS actions occur at 20% such as bypassing High SG water level trip and actions that occur with the CSP. Part 2 is correct.
Technical Reference(s):
SD-PPS page 50 and 52 Revision 23 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPS00 obj. 1 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 7
55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 85 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
022 A1.01 Importance Rating 3.8 K/A Statement (022A1.01) CONTAINMENT COOLING SYSTEM: Ability to predict and/or monitor changes in parameters associated with operation of the (SF5 CCS) CONTAINMENT COOLING SYSTEM, including: Containment temperature Proposed Question:
RO 40 Rev:
0 Given:
Plant is in Mode 1 The BOP operator is taking Tech Spec Logs in accordance with OP-903-001, Technical Specification Surveillance Logs When taking readings for containment temperature, which of the following is true?
A. Containment average air temperature shall be the average of temperatures taken at any three Containment Fan Cooler (CFC) air intake locations.
B. Containment average air temperature shall be the average of temperatures taken at any three Containment Fan Cooler (CFC) air discharge locations.
C. Containment average air temperature shall be the average of temperatures taken at all four Containment Fan Cooler (CFC) air intake locations D. Containment average air temperature shall be the average of temperatures taken at all four Containment Fan Cooler (CFC) air discharge locations.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 86 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: Note 2 of the Mode 1-4 Technical Specification Surveillance Logs states that Containment average air temperature shall be the average of temperatures taken at any three Containment Fan Cooler (CFC) air intake locations.
B. Incorrect. Note 2 of the Mode 1-4 Technical Specification Surveillance Logs states that Containment average air temperature shall be the average of temperatures taken at any three Containment Fan Cooler (CFC) air intake locations.
C. Incorrect. Note 2 of the Mode 1-4 Technical Specification Surveillance Logs states that Containment average air temperature shall be the average of temperatures taken at any three Containment Fan Cooler (CFC) air intake locations. Plausible because there are four CFCs at W3.
D. Incorrect. Note 2 of the Mode 1-4 Technical Specification Surveillance Logs states that Containment average air temperature shall be the average of temperatures taken at any three Containment Fan Cooler (CFC) air intake locations. Plausible because there are four CFCs at W3.
Technical Reference(s):
OP-903-001 page 48, 227 Rev. 102 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-CB00 obj. 6 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 7,10 55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 87 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
026 K2.01 Importance Rating 3.9 K/A Statement (026K2.01) CONTAINMENT SPRAY SYSTEM: Knowledge of electrical power supplies to the following: (SF5 CSS) CONTAINMENT SPRAY SYSTEM: Containment spray pumps Proposed Question:
RO 41 Rev:
0 Containment Spray Pump A is powered from which bus?
A. 1A B. 2A C. 3A D. 31A
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 88 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Plausible because the 1A bus is a 6.9 KV bus that powers major pumps at W3.
B. Incorrect. Plausible because the 2A bus is a 4.16 KV bus that powers major pumps at W3.
C. CORRECT: Containment Spray Pump A is powered from the 3A safety bus.
D. Incorrect. Plausible because the 31A bus is a 480V safety bus that is powered from the 3A safety bus.
Technical Reference(s):
OP-009-001 page 40 Rev. 308 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-CS00 obj. 4 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 7
55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 89 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
039 2.1.23 Importance Rating 4.3 K/A Statement (039) (SF4S MSS) MAIN AND REHEAT STEAM (2.1.23) CONDUCT OF OPERATIONS: Ability to perform general and/or normal operating procedures during any plant condition.
Proposed Question:
RO 42 Rev:
0 Given:
The crew is placing Moisture Separator Reheaters (MSRs) in service following a turbine trip in accordance with OP-005-005 Reheat Steam System The Moisture Separator Reheaters should be started in the _____(1)_____ start mode.
Once the _______(2)______ pushbutton is depressed on the Reheater Control Panel, the MSR temperature control valves should begin to open.
(1)
(2)
A.
hot Reset B.
hot Ramp C.
cold Reset D.
cold Ramp
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 90 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect. (OP-005-005 precaution 3.1.3) The MSR Cold Start Mode should always be used. The MSR Hot Start Mode is no longer used because the MSR Warm-up valves are maintained closed. Part 2 is plausible because there is a Reset pushbutton on the Reheater Control Panel. This reset pushbutton closes the reheater TCVs following a turbine trip.
B. Incorrect. (OP-005-005 precaution 3.1.3) The MSR Cold Start Mode should always be used. The MSR Hot Start Mode is no longer used because the MSR Warm-up valves are maintained closed. Part 2 is correct.
C. Incorrect. Part 1 is correct. Part 2 is plausible because there is a Reset pushbutton on the Reheater Control Panel. This reset pushbutton closes the reheater TCVs following a turbine trip.
D. CORRECT: (OP-005-005 precaution 3.1.3) The MSR Cold Start Mode should always be used. The MSR Hot Start Mode is no longer used because the MSR Warm-up valves are maintained closed. A necessary condition for performing an MSR Hot Start is that the MSRs have remain pressurized. With the MSR Warmup valves closed, the MSRs will not remain pressurized.
Technical Reference(s):
OP-005-005 pages 5, 8, 12 Rev. 307 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-MS00 obj. 8 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 4, 10 55.43 Comments: Change "will's" to "should's" in stem. Delete "over a 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> span" from stem, as this cues it is a "ramp." Changed wills to shoulds. Changed over a 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> span to begin to open.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 91 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
059 K1.14 Importance Rating 3.8 K/A Statement (059K1.14) MAIN FEEDWATER SYSTEM: Knowledge of the physical connections and/or cause and effect relationships between the (SF4S MFW) MAIN FEEDWATER SYSTEM and the following systems: ESFAS Proposed Question:
RO 43 Rev:
0 Given:
The ATC reports that Reactor Coolant System temperature is dropping rapidly The reactor was manually tripped and the ATC reports the following parameters:
Pressurizer pressure is 1720 psia and lowering Containment pressure is 17.2 psia and rising The proper alignment for Main Feedwater is _____________.
A.
Main Feed Regulating Valves closed and Startup Feed Regulating Valves 13-21% open, Main Feed Isolation Valves closed.
B.
Main Feed Regulating Valves closed and Startup Feed Regulating Valves 13-21% open. Main Feed Isolation Valves open.
C.
Main Feed Regulating, Startup Feed Regulating, and Main Feed Isolation Valves are closed.
D.
Main Feed Regulating Valves closed and Startup Feed Regulating Valves closed, Main Feed Isolation Valves open.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 92 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Plausible because the Main Feed Isolation Valves close on a MSIS and would isolate all feedwater. The Main Feed Regulating and Startup Feed Regulating Valves also get a closed signal on a MSIS.
B. Incorrect. Plausible because the Main Feed Regulating valve going closed and Startup Feed Regulating valve going to 13 to 21% open (RTO) would be the proper position for these valves after a reactor trip but not if a MSIS has occurred.
C. CORRECT: The applicant must first determine that a Main Steam Isolation (MSIS) has occurred. The logic for a MSIS is met because containment pressure is > 17.1 psia. On a MSIS, the Main Feed Regulating, Startup Feed Regulating, and Main Feed Isolation Valves get a closed signal.
D. Incorrect. Plausible if the applicant is not aware that the Main Feed Isolation Valves also get a closed signal on a MSIS. Main Feedwater would be effectively isolated to the Steam Generators if the Main Feed Regulating and Startup Feed Regulating Valves are closed.
Technical Reference(s):
SD-FW page 4 Revision 18 (Attach if not previously provided)
OP-902-000 page 11 Revision 17 (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-FW00 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 4,10 55.43
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 93 of 161 Comments: FIRST TEN. Discuss possibility of mofifying question to have a Rx trip with no ESD (to make a little more discriminating, as it appeared one need only summarize that a main feedwater isolation occurs to determine the correct answer). Question needs LOD and CFR information. There needs to be an ESD to meet the K/A (ESFAS). Leave as is. The student must first determine that a MSIS has occurred and then determine how it affects the MFW system. Added LOD and CFR information. Find a way such that we are not telling them that an ESD has occurred. Deleted the bullet that stated "an excess steam demand has occurred" and replaced it with "the ATC reports that RCS cold leg temperature is dropping. SAT.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 94 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
059 K3.05 Importance Rating 2.7 K/A Statement (059K3.05) MAIN FEEDWATER SYSTEM: Knowledge of the effect that a loss or malfunction of the (SF4S MFW) MAIN FEEDWATER SYSTEM will have on the following systems or system parameters: Extraction steam Proposed Question:
RO 44 Rev:
0 Given:
Plant is at 100% power Level in Feedwater Heater 2B level reached the Hi-Hi level alarm set point The crew has entered OP-901-221, Secondary System Transient Level in Feedwater Heater 2B should directly cause ____(1)____. This event should cause reactor power to ____(2)___.
(1)
(2)
A. Heater Drain Pump B to trip lower B. Heater Drain Pump B to trip rise C. ES-205, ES to #2 Heaters Isolation to close lower D. ES-205, ES to #2 Heaters Isolation to close rise
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 95 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect. Part 1 is plausible because Heater Drain Pump B takes a suction from Feedwater Heater 2B, but it does not get an automatic trip signal on high level. Part 2 is plausible if the applicant is not aware of the dynamics of feedwater pre-heating nor RCS temperature effects on reactor power.
B. Incorrect. Part 1 is plausible because Heater Drain Pump B takes a suction from Feedwater Heater 2B, but it does not get an automatic trip signal on high level. Part 2 is correct.
C. Incorrect. Part 1 is correct. Part 2 is plausible if the applicant is not aware of the dynamics of feedwater pre-heating nor RCS temperature effects on reactor power.
D. CORRECT: ES to #2 Heaters Isolation, ES-205, will automatically close if any #2 heater level continues to rise above the Hi-Hi level alarm setpoint. As a result of ES-205 going closed, RCS Tcold temperature will lower which will make reactor power rise.
Technical Reference(s):
OP-003-034 page 14 Revision 29 (Attach if not previously provided)
OP-901-221 page 10 Revision 11 (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO2 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 4,5 55.43 Comments: FIRST TEN. Change "will's" to "should's" in stem. Distractors missing "A" "B" "C" "D." Question appears to employ "impossible physics" - can't fathom why one would believe a loss of heating will cause temperature to rise(?) Question needs LOD and CFR information. Changed wills to should in the stem. Labeled the distractors. Added LOD and CFR information. Would like to leave as is, the student must use some system knowledge to determine part 2. Could change to what does reactor power do. Discuss.
Change part 2 to indicate effects on reactor power. Changed part 2 from RCS temperature to reactor power. SAT.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 96 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
061 K4.11 Importance Rating 3.6 K/A Statement (061K4.11) AUXILIARY/EMERGENCY FEEDWATER SYSTEM: Knowledge of (SF4S AFW) AUXILIARY/EMERGENCY FEEDWATER SYSTEM design features and/or interlocks that provide for the following: Automatic level control*
Proposed Question:
RO 45 Rev:
0 Upon an EFAS-1 event, the Primary Flow Control Valve for Steam Generator 1 will A.
open at 55% WR level in Steam Generator 1 and control level at 82% WR B.
open at 55% WR level in Steam Generator 1 and control level at 85% WR C.
open at 27.4% NR level in Steam Generator 1 and control level at 82% WR D.
open at 27.4% NR level in Steam Generator 1 and control level at 85% WR
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 97 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect: At 55% WR following an EFAS-1, the Primary FCV will fully open then maintain level at 85% WR. 82% WR level is where the Alternate FCV is designed to maintain B. CORRECT: At 55% WR following an EFAS-1, the Primary FCV will fully open then maintain level at 85% WR.
C. Incorrect. At 55% WR following an EFAS-1, the Primary FCV will fully open then maintain level at 85% WR. Steam Generator level of 27.4% is the level at which EFAS-1 actuates. 82% WR level is where the Alternate FCV is designed to maintain.
D. Incorrect. At 55% WR following an EFAS-1, the Primary FCV will fully open then maintain level at 85% WR. Steam Generator level of 27.4% is the level at which EFAS-1 actuates.
Technical Reference(s):
WLP-OPS-EFW00 page 119 Rev. 49 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-EFW00 obj. 6 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 7
55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 98 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
062 K3.02 Importance Rating 4.4 K/A Statement (062K3.02) AC ELECTRICAL DISTRIBUTION SYSTEM: Knowledge of the effect that a loss or malfunction of the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM will have on the following systems or system parameters: EDG Proposed Question:
RO 46 Rev:
0 Given:
Plant was at 100% power when a loss of offsite power occurred The BOP is performing verification of the Maintenance of Vital Auxiliaries and observes the following for EDG B:
EDG B frequency is 59.8 Hertz EDG B output breaker is open EDG B voltage is 3900 AC volts In accordance with OP-902-000, Standard Post Trip Actions, which of the following should the BOP perform?
A.
Manually close EDG B output breaker.
B.
Direct the NAO to manually close EDG B output breaker locally.
C.
Raise EDG B voltage and verify EDG B output breaker auto closes.
D.
Raise EDG B frequency and verify EDG B output breaker auto closes.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 99 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. If EDG B output breaker did not close in auto, then the operator should verify voltage in band prior to manually closing the EDG output breaker.
B. Incorrect. Closing the EDG output breaker locally is an immediate action step but is performed only after EDG voltage is verified to be within band.
C. CORRECT: Per OP-902-000, the contingency action for an EDG output breaker not closing is to verify EDG voltage 3920-4350 VAC. If the voltage is not in the band, the operator is expected to manually adjust voltage to within the band and the EDG output breaker should then close. (This step is an immediate action)
D. Incorrect. EDG frequency cannot be adjusted when the EDG is running in Emergency mode.
Technical Reference(s):
OP-902-000 page 7 Revision 17 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE01 obj. 10 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2012 RO NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7,10 55.43 Comments: Discuss possibility of modifying A and B to closer resemble C and D (using manually close instead of verify auto closed)? Changed answers to specify manual or auto closure.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 100 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
063 A4.03 Importance Rating 3.5 K/A Statement (063A4.03) DC ELECTRICAL DISTRIBUTION SYSTEM: Ability to manually operate and/or monitor the (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM in the control room: Battery discharge rate Proposed Question:
RO 47 Rev:
0 Given:
A reactor trip occurred due to a Station Blackout The crew entered OP-902-005, Station Blackout Recovery To ensure the Station batteries survive the designed ____(1)____ hours with acceptable DC voltage upon the onset of the Station Blackout, the crew will strip loads from the station batteries using Attachment 7 of OP-902-009, Standard Appendices.
The NAO can obtain Attachment 7 of OP-902-009 from the ____(2)___.
(1)
(2)
A.
four electrical equipment locker for both the A and B switchgear room B.
four Appendix R locker located at LCP-43 C.
two electrical equipment locker for both the A and B switchgear room D.
two Appendix R locker located at LCP-43
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 101 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: OI-038-000 Emergency Operating Procedure Expectations/Guidance Procedure step 5.5.7 states that DC loads are stripped in order to ensure that Station Safety related batteries will survive 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with acceptable DC voltage. This same step states that a copy of Appendix 7A, 7B & 7C is located in the electrical equipment locker for both the A and B switchgear room.
B. Incorrect. Part 1 is correct. Part 2 is plausible because the Appendix R locker in LCP-43 is located next to the Safety Related Switchgears and house field controlled procedures used in emergencies, but not Attachment 7 of OP-902-009.
C. Incorrect. Two hours is plausible because some of the DC bus Tech Specs have two-hour requirements such as the loss of the AB DC bus. Part 2 is correct.
D. Incorrect. Two hours is plausible because some of the DC bus Tech Specs have two-hour requirements such as the loss of the AB DC bus. Part 2 is plausible because the Appendix R locker in LCP-43 is located next to the Safety Related Switchgears and house field controlled procedures used in emergencies, but not of OP-902-009.
Technical Reference(s):
OI-038-000 page 49 Revision 21 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE01 obj. 4 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 8,10 55.43
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 102 of 161 Comments: Don't understand plausibility of C and D. Why would one think action is necessary in the A switchgear room while the B switchgear room could be ignored?
Agreed. Removed the portion of the question concerned with where to send the NAO and substituted it with where the NAO can locate the procedure to strip DC loads upon a Station Blackout. This is important because the location of these procedures are not in the EOP and will not be able to be printed during a SBO.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 103 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
064 K5.07 Importance Rating 3.7 K/A Statement (064K5.07) EMERGENCY DIESELGENERATOR SYSTEM: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM: Loading the EDG*
Proposed Question:
RO 48 Rev:
0 Given:
The crew is restoring Emergency Diesel Generator (EDG) B following a Station Blackout Emergency Diesel Generator B has started and the output breaker is closed The Input Transformer to MCC 315B develops a direct short to ground upon being re-energized by the 1 second Sequencer Load Block (S1 relay)
An undervoltage condition exists on 4160 Volt Bus 3B Which of the following conditions describes the Sequencer response?
A. Immediately stops the automatic loading process due to Under Voltage Override (UVO) condition.
B. Immediately stops the automatic loading process due to Sequencer Lockout (SLO) condition.
C. Stops the automatic loading process when the 7 second Load Block (S3 relay) is reached.
D. Stops the automatic loading process when the 17 second Load Block (S4 relay) is reached.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 104 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect. The Undervoltage Override (UVO) of the Sequencer occurs at 0.5 seconds. UVO is the interlock that allows the sequencer to remain running between 0.5 and 17 seconds while large transformer loads are sequenced on.
B. Incorrect. Sequencer Lockout is blocked between the 0.5 second Sequencer Load block and the 17 Second load block (due to the UVO feature). The short occurs on the 1 Second load block so the sequencer will not stop immediately.
C. Incorrect. A SLO condition occurs at 17 seconds not 7 seconds as stated in the distractor. Sequencer Lockout is active at the 7 second load block but is blocked by the UVO feature.
D. CORRECT: A SLO condition will occur at Load Block S4 due to the undervoltage condition on Bus 3A.
Technical Reference(s):
SD-EDG page 49 Revision 32 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-EDG00 obj. 3 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2017 NRC RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7
55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 105 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
073 K1.05 Importance Rating 3.1 K/A Statement (073K1.05) PROCESS RADIATION MONITORING SYSTEM: Knowledge of the physical connections and/or cause and effect relationships between the (SF7 PRM)
PROCESS RADIATION MONITORING SYSTEM and the following systems: CCWS Proposed Question:
RO 49 Rev:
0 Given:
Plant is at 100% power DRY COOLING TOWER SUMP 1 ACTIVITY HI annunciator is received High Activity reading on DCT Sump 1 radiation monitor, PRM-IRE-6775, indicated on the RM-11 Which of the following AUTOMATIC actions are expected for DCT 1 Sump?
A. Sump pumps trip.
B. Flow path to Circ Water isolates.
C. Flow path aligns to the Waste Tanks.
D. Flow path to the storm drains isolates.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 106 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: The automatic actions on a DCT Sump 1 rad monitor high alarm are that both DCT sump pumps for the respective rad monitor will trip. K/A match because the Dry Cooling Towers are part of the CCWS. The sumps used in this question serve the Dry Cooling Towers.
B. Incorrect. The automatic actions on a DCT Sump 1 rad monitor high alarm are that both DCT sump pumps for the respective rad monitor will trip. The DCT Sump Pumps are normally aligned to the Circ Water System. Alignment to the Waste Tanks is performed manually.
C. Incorrect. The automatic actions on a DCT Sump 1 rad monitor high alarm are that both DCT sump pumps for the respective rad monitor will trip. The DCT sumps are aligned to the waste tanks on high radiation. Aligning the waste tanks is performed manually.
D. Incorrect. The automatic actions on a DCT Sump 1 rad monitor high alarm are that both DCT sump pumps for the respective rad monitor will trip. The storm drains are an alternate flow path for the DCT Sump Pumps.
Technical Reference(s):
OP-901-414, Effluent Discharge High Radiation (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-SP00 obj. 6 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2012 RO NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 11 55.43
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 107 of 161 Comments: Please fix grammar in the explanations. Discuss to ensure that D could not be argued correct. Discuss K/A match. Fixed the grammar in the explanations. The flow path to the storm drains do not isolate on a DCT Sump 1 rad monitor high alarm. The flow path is still available but the sump pumps are secured. Distractor D could not be argued as the correct answer. K/A match because the Dry Cooling Towers are part of the CCWS. The sumps used in this question serve the Dry Cooling Towers. Added the reason for the K/A match to the explanation.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 108 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
076 K5.05 Importance Rating 3.1 K/A Statement (076K5.05) SERVICE WATER SYSTEM: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF4S SW)
SERVICE WATER SYSTEM: Radiation alarms on SWS Proposed Question:
RO 50 Rev:
0 Given:
Blowdown discharge to Circ Water is in progress Circ Water Disch Activity Hi annunciates on CP-1 Which of the following should occur as a result of the high activity?
A. High radiation on the Blowdown Radiation Monitor B. BD-303, Blowdown to Circ Water or Waste Ponds Header Isolation closes C. Trip of the running Blowdown Pump D. Blow down discharge is aligned to the waste tanks
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 109 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. The blowdown radiation monitor does not send signals for any components to actuate. Alarm only. Plausible to determine that the Blowdown Radiation Monitor would be the Monitor that would annunciate when discharging blowdown to circ water.
B. CORRECT: High Radiation on the Circ Water Radiation Monitor will cause Circ Water Disch Activity Hi to annunciate and automatically close BD-303, isolating blowdown flow to the circ water system.
C. Incorrect. Plausible because Blowdown pumps is the motive force for pumping blowdown to circ water.
D. Incorrect. Plausible because discharge from the Dry Cooling Tower sumps (normally aligned to Circ Water) and the Industrial Waste Sump align to the waste tanks on a high radiation.
Technical Reference(s):
OP-500-005 Attachment 4.69 Rev. 14 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-BD00 obj. 1 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 7,11 55.43 Comments: Delete "ONE" in stem. Question asks for something that has happened but explanation says isolation occurs after the alarm. Revise question to correctly match the past and present(?). Discuss how this question meets the K/A (service water). Deleted ONE in the stem. Changed the stem to read Which of the following will occur as a result of the high activity? W3 does not have a service water system. To match the K/As, we have always interpreted our Turbine Cooling Water System and Circ Water systems to be service water. Change will to should.Changed will to should.
Question is good.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 110 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
078 A3.03 Importance Rating 3.3 K/A Statement (078A3.03) INSTRUMENT AIR SYSTEM: Ability to monitor automatic features of the (SF8 IAS) INSTRUMENT AIR SYSTEM, including: Isolation of instrument air to containment Proposed Question:
RO 51 Rev:
0 IA-909, Instrument Air to Containment, will get an automatic close signal on a
____(1)____. The Containment Isolation Actuation Signal to IA-909____(2)___ be overridden.
(1)
(2)
E.
Containment Isolation Actuation Signal (CIAS) only can F.
Containment Isolation Actuation Signal (CIAS) only can NOT G.
Containment Isolation Actuation Signal (CIAS) and lowering Instrument Air pressure can H.
Containment Isolation Actuation Signal (CIAS) and lowering Instrument Air pressure can NOT
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 111 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: IA-909, Instrument Air to Containment, will automatically close on a Containment Isolation Actuation Signal (CIAS). The CIAS to IA-909 can be overridden using its C/S on CP-8.
B. Incorrect. Part 1 is correct. Part 2 is plausible because not all containment isolation valves at W3 can be overridden on a CIAS.
C. Incorrect. Part 1 is plausible because it would make sense for the containment isolation to close on a lowering instrument air pressure to isolate the leak.
D. Incorrect. Part 1 is plausible because it would make sense for the containment isolation to close on a lowering instrument air pressure to isolate the leak. Part 2 is plausible because not all containment isolation valves at W3 can be overridden on a CIAS.
Technical Reference(s):
SD-AIR page 12, 49 Rev. 15 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-AIR00 obj. 1 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 4
55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 112 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
078 K6.06 Importance Rating 3.0 K/A Statement (078K6.06) INSTRUMENT AIR SYSTEM: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF8 IAS)
INSTRUMENT AIR SYSTEM: Cross-tie valve Proposed Question:
RO 52 Rev:
0 Given:
Plant is at 100% power An instrument air leak has occurred and instrument air receiver pressure is lowering Crew has entered OP-901-511, Instrument Air Malfunction The BOP should direct the NAO to ____(1)____ the set point for SA-125, SA Backup Supply for IA Press Cntl Valve, to force it open. When instrument air pressure lowers to 105 psig, _____(2)_____.
(1)
(2)
A.
raise IA-123, Instrument Air Dryers Bypass solenoid, opens B.
raise the standby Instrument Air Compressor starts C.
lower IA-123, Instrument Air Dryers Bypass solenoid, opens D.
lower the standby Instrument Air Compressor starts
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 113 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. Part 1 is correct. Part 2 is plausible because IA-123 opens automatically at 95 psig on instrument air receiver pressure.
B. CORRECT: OP-901-511, Instrument Air Malfunction states that SA-125 will open and the standby Instrument Air Compressor will start at an instrument air receiver pressure of 105 psig. The setpoint will be raised on SA-125 to force it open early or if it is not operating properly. If it is malfunctioning, IA pressure will drop to 105 psig, and auto start the standby air compressor.
C. Incorrect. Part 1 is plausible because the applicant may assume that lowering the setpoint of SA-125 will open the valve sooner. Part 2 is plausible because IA-123 is opens automatically at 95 psig on instrument air receiver pressure.
D. Incorrect. Part 1 is plausible because the applicant may assume that lowering the setpoint of SA-125 will open the valve sooner. Part 2 is correct.
Technical Reference(s):
OP-901-511 page 4 and 6 Revision 19 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO50 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7,10 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 114 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
103 G2.4.49 Importance Rating 4.4 K/A Statement (103) (SF5 CNT) CONTAINMENT SYSTEM (G2.4.49) EMERGENCY PROCEDURES/PLAN: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls Proposed Question:
RO 53 Rev:
0 Given:
Containment Pressure is 16.9 PSIA RCS Pressure is 1600 PSIA SSL-8004A, Sampling Isolation SG1 is OPEN BAM-126A, Boric Acid Makeup Pump A Recirc Valve is CLOSED HVR 313A, CVAS Train A Outlet Valve OPEN FP-601A, Fire Water A to Containment is CLOSED Which of the following valves requires operator action for the current plant conditions?
A. SSL-8004A B. BAM-126A C. HVR-313A D. FP-601A
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 115 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: With the given conditions, Safety Injection Actuation Signal (SIAS) and a Containment Isolation Actuation Signal (CIAS) are present due to RCS pressure
<1684 psia. SSL-8004A is a Containment Isolation Valve that closes on a CIAS. This valve is overridden to the open position during an accident in order to sample steam generators for activity.
B. Incorrect. BAM-126A is a normally open valve. In addition to a CIAS, the student must identify that a SIAS also exists. BAM-126A will close on a SIAS.
C. Incorrect. HVR-313A is a normally closed valve. In addition to a CIAS, the student must identify that a SIAS also exists SIAS. On the SIAS, CVAS Train A will start and HVR-313A will open.
D. Incorrect. FP-601A is a normally open valve and closes on a CIAS. Plausible because the student may determine that Fire Protection must remain available to containment.
Technical Reference(s):
OP-902-009 Attachments 4C and 4D Rev. 323 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE01 obj. 6 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 7,8 55.43 Comments: Delete "one" in stem. Discuss plausibility of B,C, and D as correct answer appears obvious. Deleted one in the stem. Added words to the explanations to explain the plausibility of B, C, and D. Seems that A is the obvious answer only if you know what the K/A is. Got rid of "one". Good.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 116 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
103 K3.04 Importance Rating 3.0 K/A Statement (103 K3.04) CONTAINMENT SYSTEM: Knowledge of the effect that a loss or malfunction of the (SF5 CNT) CONTAINMENT SYSTEM will have on the following systems or system parameters (CFR 41.7/45.4) Shield Building Vent system Proposed Question:
RO 54 Rev:
0 A plant trip and SIAS have occurred due to low Pressurizer pressure.
What is the designed range of Containment Annulus to ambient differential pressure in inches of water?
A. -3.0 to -8.0 B. +2.0 to -8.0 C. -3.0 to -10.0 D. +2.0 to -10.0
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 117 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: SBV will cycle after starting on a SIAS at -3.0 to -8.0 of Containment Annulus to ambient differential pressure measured in inches of water.
B. Incorrect. The -8 is correct, but +2.0 inches is the maximum containment pressure that would ensure supply air to containment from the CAR System.
C. Incorrect. The -3.0 is correct but the10.0 inches is the maximum value for Containment pressure before containment purge can be initiated.
D. Incorrect. The +2.0 inches is the maximum containment pressure that would ensure supply air to containment from the CAR System and the 10.0 inches is the maximum value for Containment pressure before containment purge can be initiated.
Technical Reference(s):
OP-008-008 page 11 Revision 11 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-SBV obj. 2 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2015 RO NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 8
55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 118 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
001 A4.01 Importance Rating 2.9 K/A Statement (001A4.01) CONTROL ROD DRIVE SYSTEM: Ability to manually operate and/or monitor the (SF1 CRDS) CONTROL ROD DRIVE SYSTEM in the control room: CRDM Cooling.
Proposed Question:
RO 55 Rev:
0 In accordance with OP-008-004, Control Element Drive Mechanism Cooling System, which of the following would be the correct sequence to swap Control Element Drive Mechanism (CEDM) Cooling Fans?
Assume CEDM Cooling Fans A and B are running.
A.
Start CEDM Cooling Fan D then secure CEDM Cooling Fan B.
B.
Secure CEDM Cooling Fan A then start CEDM Cooling Fan D.
C.
Start CEDM Cooling Fan D then secure CEDM Cooling Fan A.
D.
Secure CEDM Cooling Fan A then start CEDM Cooling Fan C.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 119 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect. Plausible if the applicant determines that running only one CEDM at a time is not allowed.
B. Incorrect. Plausible if the applicant is not aware of the train requirements or not aware of which electrical bus the CEDM is designated to.
C. Incorrect. Plausible if the applicant determines that running only one CEDM at a time is not allowed.
D. CORRECT: The guidance for swapping CEDM fans in OP-008-004, Control Element Drive Mechanism Cooling System, has two requirements. 1) One train from each safety bus should normally be running. 2) Do not operate more than two CEDM Cooling fans at a time. CEDM Fans A and C (A train) CEDM fans B and D (B train).
This answer is the only one that meets these requirements.
Technical Reference(s):
OP-008-004 page 8 revision 9 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-CCS00 obj. 6 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 4,10 55.43 Comments: 2nd half of B and D are identical, which cues that one of those distractors is probably the correct answer. Re-arranged the swapping of the CEDM fans in the distractors such that the trains are equal between answers and distractors.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 120 of 161 Examination Outline Cross-
Reference:
2 Group #
2 K/A #
033 K5.06 Importance Rating 3.7 K/A Statement (033K5.06) SPENT FUEL POOL COOLING SYSTEM: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF8) SPENT FUEL POOL COOLING SYSTEM: Shielding (water level)
Proposed Question:
RO 56 Rev:
0 Per Tech Specs, the MINIMUM required water level in the Spent Fuel Pool is
___(1)___ feet.
The makeup source to Spent Fuel Pool can be procedurally aligned from the ___(2)___.
(1)
(2)
A.
43 Condensate Storage Pool only B.
43 Refuel Water Storage Pool or Condensate Storage Pool C.
23 Condensate Storage Pool only D.
23 Refuel Water Storage Pool or Condensate Storage Pool
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 121 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. Part 1 is correct. Part 2 is plausible because makeup to the SFP is done frequently on shift. The makeup is always from the non-borated CSP to make-up for evaporated losses. However, the off-normal procedure allows makeup from either source B. CORRECT: Tech Spec 3.9.11 states At least 23 feet of water shall be maintained over the top of the fuel seated in the storage racks. The top of the fuel seated in the storage racks is at the 20 foot level. Therefore, required level is 43 feet. Makeup can be aligned to either the CSP or the RWSP.
C. Incorrect. Part 1 is plausible because TS 3.9.11 requires that At least 23 feet of water shall be maintained over the top of the fuel seated in the storage racks, the top of the fuel is assembly is at 20 feet, therefore required level is 43 feet. Part 2 is plausible because makeup to the SFP is done frequently on shift. The makeup is always from the non-borated CSP to make-up for evaporated losses. However, the off-normal procedure allows makeup from either source.
D. Incorrect. Part 1 is plausible because TS 3.9.11 requires that At least 23 feet of water shall be maintained over the top of the fuel seated in the storage racks. The top of the fuel is assembly is at 20 feet, therefore, required level is 43 feet. Part 2 is correct.
Technical Reference(s):
TS 3.9.11 (Attach if not previously provided)
OP-901-513 page 6 Rev. 28 (including version/revision number)
OP-002-006 page 9 Rev. 330 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-FS00 objs. 3 and 6 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 8
55.43
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 122 of 161 Comments: Add "Per TS, the MINIMUM" at beginning of first sentence. Add "procedurally alligned" after "can be" in stem. Added "Per TS, the MINIMUM" at beginning of first sentence. Added "procedurally aligned" after "can be" in stem.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 123 of 161 Examination Outline Cross-
Reference:
2 Group #
2 K/A #
016 A3.01 Importance Rating 3.3 K/A Statement (016A3.01) NONNUCLEAR INSTRUMENTATION SYSTEM: Ability to monitor automatic features of the (SF7 NNI) NONNUCLEAR INSTRUMENTATION SYSTEM, including: Automatic selection of NNI system inputs to control systems Proposed Question:
RO 57 Rev:
0 Given:
- A plant power reduction is in progress
- Reactor power is 40% and slowly lowering
- The BOP reports NO response while attempting to operate the Master Controller #2 in MANUAL Which of the following should be operated in MANUAL mode to restore and maintain Steam Generator level within band?
A. Main Feedwater Pump Speed #2 M/A station only.
B. Main Feedwater Regulating valve #2 M/A station only.
C. Startup Feedwater Regulating valve #2 M/A station only.
D. Both the SUFRV #1 M/A station and Main Feedwater Pump Speed #2 M/A station.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 124 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. MFW Pump Speed will take the high select from FWC Master #1 or #2.
Pump speed will be adequate. In this case, from FWC Master #1. This is where the automatic selection of an NNI input to a control system occurs to meet the K/A.
B. CORRECT: MFW regulating valve controller adjustment is the proper action at this power level. The function of the SUFRV is to maintain level at low power levels. The SUFRV has the capacity to provide feedwater up to 22% flow demand. At 40%
power, the SUFRV capacity is inadequate to restore level. The Main FWRV must be opened.
C. Incorrect. MFW regulating valve controller adjustment is the proper action at this power level. The function of the SUFRV is to maintain level at low power levels. The SUFRV has the capacity to provide feedwater up to 22% flow demand.
D. Incorrect. The SUFRV capacity is inadequate to restore SG level at this power Feedwater flow at this power level. MFW Pump Speed will take the high select from FWC Master #1 or #2. In this case, from FWC Master #1. Pump speed will be adequate.
Technical Reference(s):
SD-FWC page 11 Rev. 14 (Attach if not previously provided)
OP-901-201 Attachment 1 Rev. 7 (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO2 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 4
55.43 Comments: Distractor C does not appear plausible for the given conditions. Changed reactor power from 50% to 40% in the stem to make distractor C more plausible. The SUFRV has the capacity to provide feedwater up to 22% flow demand.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 125 of 161 Examination Outline Cross-
Reference:
2 Group #
2 K/A #
028 K3.01 Importance Rating 3.1 K/A Statement (028K3.01) HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM:
Knowledge of the effect that a loss or malfunction of the (SF5 HRPS) HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM will have on the following systems or system parameters: Hydrogen concentration in containment Proposed Question:
RO 58 Rev:
0 Given:
A LOCA has occurred Containment Hydrogen concentration is rising slowly The crew is placing Hydrogen Recombiners in service Hydrogen Recombiner B trips and CANNOT be restarted Which of the following describes the MAXIMUM designed containment hydrogen concentration with ONLY ONE Hydrogen Recombiner in service and the direction for placing Hydrogen Recombiners in service?
A. 4% and should be manually started as directed by the TSC.
B. 4% and should be manually started as directed by OP-902-002, LOCA Recovery Procedure.
C. 8% and should be manually started as directed by the TSC.
D. 8% and should be manually started as directed by OP-902-002, LOCA Recovery Procedure.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 126 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: The design function of the hydrogen recombiners is to limit hydrogen concentration to less than 4 percent. Each hydrogen recombiner is 100% capacity.
The direction for starting a Hydrogen Recombiner is from the TSC.
B. Incorrect. Part 1 is correct. Part 2 is plausible because OP-902-002 is the implementing procedure for a LOCA and direction to start the hydrogen analyzers is located in OP-902-002. Guidance was once provided int OP-902-002 to start the recombiners but has since been removed.
C. Incorrect. Part 1 is plausible because the explosive limit is 13%. 8% is approximately half that number. Part 2 is correct.
D. Incorrect. Part 1 is plausible because the explosive limit is 13%. 8% is approximately half that number. Part 2 is plausible because OP-902-002 is the implementing procedure for a LOCA and direction to start the hydrogen analyzers is located in OP-902-002. Guidance was once provided int OP-902-002 to start the recombiners but has since been removed.
Technical Reference(s):
SD-HRA pages 4, 5, 8, 9 Rev. 6 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-HRA00 obj. 4 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 8
55.43 Comments: Delete "remain below" in distractors. Deleted remain below in the distractors.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 127 of 161 Examination Outline Cross-
Reference:
2 Group #
2 K/A #
034 A2.07 Importance Rating 3.7 K/A Statement (034A2.07) FUEL HANDLING EQUIPMENT SYSTEM: Ability to (a) predict the impacts of the following on the (SF8 FHS) FUEL HANDLING EQUIPMENT SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Loss of Refueling Cavity or Spent Fuel Pool level Proposed Question:
RO 59 Rev:
0 Given:
Core offload is in progress A failure of Reactor Cavity Pool Seal has occurred and crew is implementing OP-010-006 Attachment 9.23, Loss of Refuel Cavity Water Level Guidelines With no means of isolating the leak, the crew should expect a final level of ____(1)____
ft. MSL in the core.
If the leak occurs with a fuel assembly on the refueling machine grapple, the preferred location to place the fuel assembly as recommended by OP-010-006 is in the
_____(2)_____.
(1)
(2)
A.
13.5 Reactor Vessel B.
20 Reactor Vessel C.
13.5 Fuel assembly storage rack in the Refueling Cavity D.
20 Fuel assembly storage rack in the Refueling Cavity
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 128 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. Part 1 is plausible because this is the level the Refuel Cavity will go to if the nozzle dams were leaking. This leak location is also listed in OP-010-006. Part 2 is correct.
B. CORRECT: OP-010-006 step 9.23.1.1 states a loss of the pool seal will result in a final water level of 20 ft. MSL in the core. This level is equal to the level of the reactor vessel flange. OP-010-006, step 9.23.2.4 provides a recommendation for placing the assembly upon a leak. The locations are listed in a decreasing order of preference.
The Reactor Vessel is the first preferred location.
C. Incorrect. Part 1 is plausible because this is the level the Refuel Cavity will go to if the nozzle dams were leaking. This leak location is also listed in OP-010-006. Part 2 is plausible because the Fuel assembly storage racks in the Refuel Cavity are listed in the locations to place a fuel assembly and will still be underwater upon a refuel cavity leak to 20 ft. MSL. But, OP-010-006 list the reactor vessel as a more preferred location than the storage racks.
D. Incorrect. Part 1 is correct. Part 2 is plausible because the Fuel assembly storage racks in the Refuel Cavity are listed in the locations to place a fuel assembly and will still be underwater upon a refuel cavity leak to 20 ft. MSL. But, OP-010-006 list the reactor vessel as a more preferred location than the storage racks.
Technical Reference(s):
OP-010-006 page 108, 109 Rev. 341 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-REQ04 obj. 5 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 9,10 55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 129 of 161 Examination Outline Cross-
Reference:
2 Group #
2 K/A #
055 K1.02 Importance Rating 3.5 K/A Statement (055K1.02) CONDENSER AIR REMOVAL SYSTEM: Knowledge of the physical connections and/or cause and effect relationships between the (SF4S CARS)
CONDENSER AIR REMOVAL SYSTEM and the following systems: Main condenser Proposed Question:
RO 60 Rev:
0 Given:
Plant is at 100% power Condenser Vacuum Pump B has tripped To maintain a suction path for Condenser Air Evacuation PIG Rad Monitor (PRM-IRE-0004), the BOP should verify Condenser Vacuum Pump ____(1)____ is running. Condenser Vacuum Pumps are designed to automatically start at a Main Condenser Vacuum of ____(2)____ inches Hg.
(1)
(2)
A.
A 24.5 B.
A 26 C.
C 26 D.
C 24.5
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 130 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Condenser Vacuum Pump B or C must be operating to maintain a suction path for Condenser Air Evacuation PIG Rad Monitor (PRM-IRE-0004). Part 2 is plausible because the Loss of Condenser Vacuum off-normal procedure requires the crew to trip the reactor at 24.5 inches Hg.
B. Incorrect. Condenser Vacuum Pump B or C must be operating to maintain a suction path for Condenser Air Evacuation PIG Rad Monitor (PRM-IRE-0004). Part 2 is correct.
C. CORRECT: Condenser Vacuum Pump B or C must be operating to maintain a suction path for Condenser Air Evacuation PIG Rad Monitor (PRM-IRE-0004).
Standby Condenser Vacuum Pumps will auto start at 26 inches Hg on lowering Main Condenser Vacuum.
D. Incorrect. Part 1 is correct. Part 2 is plausible because the Loss of Condenser Vacuum off-normal procedure requires the crew to trip the reactor at 24.5 inches Hg.
Technical Reference(s):
OP-003-001 page 9 and 22 Rev. 25 (Attach if not previously provided)
OP-901-220 page Rev. 306 (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-AE00 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2017 NRC RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 4,10 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 131 of 161 Examination Outline Cross-
Reference:
2 Group #
2 K/A #
056 K4.14 Importance Rating 3.6 K/A Statement (056K4.14) CONDENSATE SYSTEM: Knowledge of (SF4S CDS) CONDENSATE SYSTEM design features and/or interlocks that provide for the following: MFW Pump NPSH Proposed Question:
RO 61 Rev:
0 Given:
The plant is at 100% power Heater Drain Pump A tripped The crew has entered OP-901-221, Secondary System Transient CD-1532, Condensate Polisher Bypass, may need to be throttled ____(1)____
to maintain > 250 PSIG at Steam Generator Feed Pumps suction.
____(2)____ Main Feedwater Pump(s) should trip 10 seconds after reaching the suction pressure trip setpoint.
(1)
(2)
A.
closed both B.
closed one C.
open both D.
open one
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 132 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect. Condensate Polisher D/P will rise because more flow is being forced through the polisher on HDP trips. Only Main Feedwater Pump A will trip 10 seconds after reaching 250 psig for FWP suction pressure. Main Feedwater Pump B has a 30 second time delay to trip on low suction pressure. Suction pressure should restore after the MFP A trip. Opening CD-1532 will bypass the polishers and help to restore Main Feed Suction pressure.
B. Incorrect. Condensate Polisher D/P will rise because more flow is being forced through the polisher on HDP trips. The second part is correct.
C. Incorrect. The first part is correct. Only Main Feedwater Pump A will trip 10 seconds after reaching 250 psig for FWP suction pressure. Main Feedwater Pump B has a 30 second time delay to trip on low suction pressure. Suction pressure should restore after the MFP A trip. Opening CD-1532 will bypass the polishers and help to restore Main Feed Suction pressure.
D. CORRECT: Condensate Polisher D/P will rise because more flow is being forced through the polisher on HDP trips. Only Main Feedwater Pump A will trip 10 seconds after reaching 250 psig for FWP suction pressure. Main Feedwater Pump B has a 30 second time delay to trip on low suction pressure. Suction pressure should restore after the MFP A trip. Opening CD-1532 will bypass the polishers and help to restore Main Feed Suction pressure.
Technical Reference(s):
OP-901-221 pages 4, 13 Rev. 11 (Attach if not previously provided)
SD-CDP pages 25, 26 Rev. 8 (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO2 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 3
10 CFR Part 55 Content:
55.41 4,10 55.43
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 133 of 161 Comments: Change "will" to "should" in stem. Where is there direction to potentially throttle CD-1532 (I didn't see any in the references). Changed will to should. The procedure provides the guidance to throttle the condensate polisher bypass valve to maintain D/P. Will provide the reference.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 134 of 161 Examination Outline Cross-
Reference:
2 Group #
1 K/A #
068 G2.3.11 Importance Rating 3.8 K/A Statement (068) LIQUID RADWASTE SYSTEM (G2.3.11) RADIATION CONTROL: Ability to Control Radiation Releases Proposed Question:
RO 62 Rev:
0 Prior to discharging a Waste Condensate Tank to the Circulating Water System, OP-007-001 Liquid Waste Management procedure, states that the crew should verify
____________ is(are) in service.
A. either A1, A2, or B1 water box B. all A1, A2, and B1 water boxes C. either B2, C1 or C2 water box D. all B2, C1 and C2 water boxes
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 135 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Both the Liquid Waste Management (LWM) and Boron Management (BM) systems effluent discharge to the Circulating Water System through the second discharge block of the condenser. This block contains circ water boxes B2, C1 and C2. The procedure requires one of these water boxes to be in service prior to discharging.
B. Incorrect. Both the Liquid Waste Management (LWM) and Boron Management (BM) systems effluent discharge to the Circulating Water System through the second discharge block of the condenser. This block contains circ water boxes B2, C1 and C2. The procedure requires one of these water boxes to be in service prior to discharging.
C. CORRECT: Both the Liquid Waste Management (LWM) and Boron Management (BM) systems effluent discharge to the Circulating Water System through the second discharge block of the condenser. This block contains circ water boxes B2, C1 and C2. The procedure requires one of these water boxes to be in service prior to discharging. Not a substep issue here because the stem is asking what does the procedure state to verify.
D. Incorrect. Both the Liquid Waste Management (LWM) and Boron Management (BM) systems effluent discharge to the Circulating Water System through the second discharge block of the condenser. This block contains circ water boxes B2, C1 and C2. The procedure requires one of these water boxes to be in service prior to discharging.
Technical Reference(s):
OP-007-004 page 21 Rev. 322 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-CW00 obj. 1 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2020 NRC RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 4,13 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 136 of 161 Examination Outline Cross-
Reference:
2 Group #
2 K/A #
071 A1.09 Importance Rating 3.2 K/A Statement (071A1.09) WASTE GAS DISPOSAL SYSTEM: Ability to predict and/or monitor changes in parameters associated with operation of the (SF9 WGS) WASTE GAS DISPOSAL SYSTEM, including: Waste gas tank discharge radiation levels Proposed Question:
RO 63 Rev:
0 Given:
- Gas Decay Tank(s) discharge is in progress in accordance with OP-007-003, Gaseous Waste Management
- The RM-11 alarms and the associated annunciator is received The validity of this annunciator is verified by checking Waste Gas Flow and Rad Recorder (GWMIFRR0648) located on __(1)__.
High radiation on __(2)__ Radiation Monitor will cause the Gas Decay Tank discharge to automatically isolate.
(1)
(2)
A.
CP-42 either Plant Stack Vent B. CP-4 either Plant Stack Vent C.
CP-42 the Gaseous Waste Management D. CP-4 the Gaseous Waste Management
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 137 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect. LCP-42 is the location for the Waste Gas Decay Tanks to Plant Vent Flow Indicator as mentioned in the ARP. This is not the indicator the off-normal directs use of to verify the validity of the annunciator. On high radiation during a GDT release, the Gaseous Waste Management Rad Monitor will automatically close GWM-309. The Plant Stack Vent Rad monitor is plausible because it is listed as one of the indications in OP-901-413.
B. Incorrect. Part 1 is correct. On high radiation during a GDT release, the Gaseous Waste Management Rad Monitor will automatically close GWM-309. The Plant Stack Vent Rad monitor is plausible because it is listed as one of the indications in OP-901-413.
C. Incorrect. LCP-42 is the location for the Waste Gas Decay Tanks to Plant Vent Flow Indicator as mentioned in the ARP. This is not the indicator the off-normal directs use of to verify the validity of the annunciator. Part 2 is correct.
D. CORRECT: From the annunciator response and off-normal procedure, the validity of this annunciator is verified by checking Waste Gas Flow and Rad Recorder (GWMIFRR0648).
This recorder is located on CP-4. On high radiation during a GDT release, the Gaseous Waste Management Rad Monitor will automatically close GWM-309.
Technical Reference(s):
OP-901-413 page 4 and 6 Rev. 2 (Attach if not previously provided)
OP-500-007 Att. 4.50 Rev. 17 (including version/revision number)
SD-GWM page 13 Rev. 8 Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO10 obj. 3 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2017 NRC RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10,13 55.43 Comments: OK, but locations of plant equipment should normally be evaluated during the operating test. OK.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 138 of 161 Examination Outline Cross-
Reference:
2 Group #
2 K/A #
G2.1.8 Importance Rating 3.4 K/A Statement (G2.1.8) CONDUCT OF OPERATIONS: Ability to coordinate personnel activities outside the control room Proposed Question:
RO 64 Rev:
0 Given:
The control room is being evacuated due to a fire Procedures for supporting performance of OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown, can be found in the cabinets located at LCP-43 and the RAB +35 ____(1)____. The Emergency Communicator should assist the control room staff with activating the Fire Brigade, Plant Announcements, and notifying Hahnville Fire Department in accordance with the guidance in ____(2)____.
(1)
(2)
A.
Cable vault room OP-901-524, Fires in areas affecting Safe Shutdown B.
Cable vault room FP-001-020, Fire Emergency/Fire Report C.
Relay room OP-901-524, Fires in areas affecting Safe Shutdown D.
Relay room FP-001-020, Fire Emergency/Fire Report
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 139 of 161 Proposed Answer:
D Explanation: (Optional)
A.
Incorrect. Part 1 is plausible because the Cable Spreading Room is located next to the Relay Room on the RAB +35. Actions in OP-901-502 are performed in both the Cable Vault and Relay rooms, but the cabinet where the procedures are stored are in the Relay Room.
Part 2 is plausible because OP-901-524 provides the guidance for actions to be taken depending on which room the fire is located, but the guidance for plant announcements, activating the Fire Brigade, etc. are located in FP-001-020.
B.
Incorrect. Part 1 is plausible because the Cable Spreading Room is located next to the Relay Room on the RAB +35. Actions in OP-901-502 are performed in both the Cable Vault and Relay rooms, but the cabinet where the procedures are stored are in the Relay Room.
Part 2 is correct.
C.
Incorrect. Part 1 is correct. Part 2 is plausible because OP-901-524 provides the guidance for actions to be taken depending on which room the fire is located, but the guidance for plant announcements, activating the Fire Brigade, etc. are located in FP-001-020.
D.
CORRECT: Procedures to support the performance of OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown are in a cabinet located in the RAB +35 Relay Room. FP-001-020 provides the guidance for actions to be taken such as plant announcements, activating the Fire Brigade, etc. The question is generic because the Control Room can be evacuated for many reasons and this information is located on the Notes and Information section of OP-901-502.
Technical Reference(s):
OP-901-502, page 50 Rev. 41 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO51 obj. 6 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 55.43 Comments: OK, but locations of in-plant procedures should nrmally be evaluated during the operating test. OK.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 140 of 161 Examination Outline Cross-
Reference:
2 Group #
2 K/A #
G2.1.47 Importance Rating 3.2 K/A Statement (G2.1.47) CONDUCT OF OPERATIONS: Ability to direct non-licensed personnel activities inside the control room Proposed Question:
RO 65 Rev:
0 Per OI-042-000, Watch Station Processes, the Switchgear Operator and the Emergency Communicator shall be staffed at all times. Which of the following is an additional MINIMAL restriction for these positions as stated in OI-042-000?
A. The Switchgear Operator and the Emergency Communicator shall remain inside the protected area.
B. The Switchgear Operator and the Emergency Communicator shall remain inside RAB, RCA, FHB or Turbine Building (+15 or +40).
C. The Switchgear Operator shall remain in the protected area and the Emergency Communicator shall remain inside the RAB, RCA, FHB or Turbine Building (+15 or +40).
D. The Emergency Communicator shall remain in the protected area and the Switchgear operator shall remain inside the RAB, RCA, FHB or Turbine Building
(+15 or +40).
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 141 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. OI-042-000, Watch Station Process, states that the Switchgear operator shall remain in the protected area and the Emergency Communicator shall remain inside the RAB, RCA, FHB or Turbine Building (+15 or +40).
B. Incorrect. OI-042-000, Watch Station Process, states that the Switchgear operator shall remain in the protected area and the Emergency Communicator shall remain inside the RAB, RCA, FHB or Turbine Building (+15 or +40).
C. CORRECT: OI-042-000, Watch Station Process, states that the Switchgear operator shall remain in the protected area and the Emergency Communicator shall remain inside the RAB, RCA, FHB or Turbine Building (+15 or +40).
D. Incorrect. OI-042-000, Watch Station Process, states that the Switchgear operator shall remain in the protected area and the Emergency Communicator shall remain inside the RAB, RCA, FHB or Turbine Building (+15 or +40).
Technical Reference(s):
OI-042-000 page 82 Rev. 67 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPA00 obj. 2 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 55.43 Comments: Capitalize MINIMAL in stem. Capitalized MINIMAL in the stem.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 142 of 161 Examination Outline Cross-
Reference:
3 Group #
1 K/A #
G2.2.12 Importance Rating 3.7 K/A Statement (G2.2.12) EQUIPMENT CONTROL: Knowledge of surveillance procedures Proposed Question:
RO 66 Rev:
0 In accordance with OP-100-014, Technical Specification and Technical Requirements Compliance, the crew is required to enter the appropriate cascading Technical Specifications upon declaring a(an) ___(1)____ inoperable.
The crew will be required to ____(2)____ within a MAXIMUM of one hour.
(1)
(2)
A.
Emergency Diesel Generator complete OP-903-066, Electrical Breaker Alignment Check B. Component Cooling Water Train complete OP-903-066, Electrical Breaker Alignment Check C. Component Cooling Water Train verify Emergency Feedwater Pump AB operable D. Emergency Diesel Generator verify Emergency Feedwater Pump AB operable
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 143 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. Even though the EDG supplies power to various loads during an emergency, W3 does not cascade due to an EDG being inoperable. Part 2 is correct.
B. CORRECT: OP-100-014, Technical Specification and Technical Requirements Compliance designates systems that required cascading Tech Specs, CCW is one of those systems. The Electrical Breaker Lineup Check is required to be completed w/i 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in accordance with TS 3.8.1.1b. This question is generic because cascading TS applies to more than one system, cascading TS also applies to Essential Chillers and the UHS.
C. Incorrect. Part 1 is correct. TS 3.8.1.1d (verify EFW Pump AB operable) is required during cascading Tech Specs but must be performed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. Incorrect. Even though the EDG supplies power to various loads during an emergency, W3 does not cascade due to an EDG being inoperable. TS 3.8.1.1d (verify EFW Pump AB operable) is required during cascading Tech Specs but must be performed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Technical Reference(s):
OP-100-014 page 43, 48 Rev. 365 (Attach if not previously provided)
TS 3.8.1.1 actions b and d (including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-CC00 obj. 9 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2017 RO NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 55.43 Comments: No comments
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 144 of 161 Examination Outline Cross-
Reference:
3 Group #
1 K/A #
G2.2.13 Importance Rating 4.1 K/A Statement (G2.2.13) EQUIPMENT CONTROL: Knowledge of tagging and clearance procedures Proposed Question:
RO 67 Rev:
0 Which of the following components qualifies as a NO TAG component on a Danger Tagout?
A. A drain valve that is going to be removed by maintenance.
B. A handwheel on a Motor Operated Valve being used as an isolation boundary.
C. A breaker that maintenance personnel will need to operate while signed on to the tagout.
D. A pump discharge valve that is used as the inside double valve isolation on a high energy system.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 145 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: EN-OP-102 identifies a purpose of a no tag is to identify components that cannot be tagged but require positioning when hanging a tagout. Removing a drain valve meets this purpose.
B. Incorrect. Not allowed as a no tag per EN-OP-102.
C. Incorrect. Not allowed as a no tag per EN-OP-102.
D. Incorrect. Not allowed as a no tag per EN-OP-102.
Technical Reference(s):
EN-OP-102 page 78 Revision 28 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
ELP-OPS-CLR obj. 3 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2012 NRC RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 146 of 161 Examination Outline Cross-
Reference:
3 Group #
1 K/A #
G2.3.5 Importance Rating 2.9 K/A Statement (G2.3.5) RADIATION CONTROL: Ability to use RMSs, such as fixed radiation monitors and alarms or personnel monitoring equipment Proposed Question:
RO 68 Rev:
0 The ___(1)____ Rad Monitor is specified as the primary monitor with the designed sensitivity to measure small Primary to Secondary leakage and the ___(2)____ radiation monitor is specified as qualified for use if the primary monitor fails.
________(1)________
____________(2)_______________
A MS Line N-16 PRM-RE5501-1 (2)
Steam Generator 1 and 2 Blowdown PRM-IRE-0100X B
MS Line N-16 PRM-RE5501-1 (2)
AE Discharge PRM-IRE-0004 C
AE Discharge PRM-IRE-0004 Steam Generator 1 and 2 Blowdown PRM-IRE-0100X D
AE Discharge PRM-IRE-0004 MS Line N-16 PRM-RE5501-1 (2)
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 147 of 161 Proposed Answer:
D Explanation: (Optional)
A. Incorrect: AE Discharge Radiation Monitor is considered the primary Radiation Monitor with the designed sensitivity to measure small Primary to Secondary Leakage. The Blowdown Rad Monitor is listed as available indication but is not the primary indication or backup.
B. Incorrect: AE Discharge is primary and MS Line N-16 is backup C. Incorrect: Part 1 is correct. The Blowdown Rad Monitor is listed as available indication but is not the primary indication or backup.
D. CORRECT: AE Discharge Radiation Monitor is considered the primary Radiation Monitor with the designed sensitivity to measure small Primary to Secondary Leakage. The MS Line N16 Rad Monitors may be used as verification for the AE Discharge Radiation Monitor or as primary indication if the AE Discharge Radiation Monitor is out of service.
Technical Reference(s):
OP-901-202 page 4 Revision 16 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPO2 obj. 3 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam 2014 NRC RO Exam Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 11 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 148 of 161 Examination Outline Cross-
Reference:
3 Group #
2 K/A #
G2.4.21 Importance Rating 4
K/A Statement (G2.4.21) EMERGENCY PROCEDURES/PLAN: Knowledge of the parameters and logic used to assess the status of emergency operating procedures critical safety functions or shutdown critical safety functions (CFR: 41.7/43.5/45.12)
Proposed Question:
RO 69 Rev:
0 Which of the following is the guidance stated in the RCS Inventory Control and Core Heat Removal Safety Functions criteria located in OP-902-002, Loss of Coolant Accident Recovery Procedure?
A. Core uncovery and superheated conditions may be expected for up to a MAXIMUM of 15 minutes within the first 30 minutes of some LOCA events B. Core uncovery and superheated conditions may be expected for up to a MAXIMUM of 30 minutes within the first 60 minutes of some LOCA events.
C. Core uncovery and superheated conditions may be expected for up to a MAXIMUM of 45 minutes within the first 75 minutes of some LOCA events.
D. Core uncovery and superheated conditions may be expected for up to a MAXIMUM of 60 minutes within the first 90 minutes of some LOCA events.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 149 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Plausible because 15 minutes and 30 minutes is used in various situations in the EOPs.
B. Incorrect. Plausible because 30 minutes and 60 minutes is used in various situations in the EOPs.
C. CORRECT: The following note is located in both the RCS inventory control and Core heat removal safety function located in OP-902-002: Core uncovery and superheated conditions may be expected for up to 45 minutes within the first 75 minutes of some LOCA events. If the SI flow is in accordance with the SI flow curves exiting this procedure to the OP-902-008, Functional Recovery Procedure will not provide any additional guidance to restore inventory control.
D. Incorrect. Plausible because 60 minutes is used in various situations in the EOPs.
Technical Reference(s):
OP-902-002 page 73 Revision 21 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-PPE02 objective 16 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 55.43 Comments: A does not fit with the other distractors and is easily eliminated as a possibility. Discuss modifying times to 15/30, 30/60, 45/75. and 60/90 for A,B,C,and D.
Will discuss modifying this question. Believe this question is good as written. Would like to leave it as is. Change distractors as recommended. Changed the distractors as recommended. SAT.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 150 of 161 Examination Outline Cross-
Reference:
4 Group #
K/A #
192006 K1.04 Importance Rating 2.8 K/A Statement (192006K1.04) FISSION PRODUCT POISONS Describe the removal of Xenon 135 Proposed Question:
RO 70 Rev:
0 Reactor power is increased from 50 percent to 60 percent in one hour. What is the most significant contributor to the initial change in xenon-135 reactivity?
A. Production of xenon-135 directly from fission.
B. Production of xenon-135 from iodine-135 decay.
C. Loss of xenon-135 due to absorption of neutrons.
D. Loss of xenon-135 due to decay to cesium-135.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 151 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect: An initial loss of Xenon-135 occurs during a reactor power increase. The greatest contributor to the loss of Xenon-135 is neutron absorption. This question is taken directly from the NRC Exam bank.
B. Incorrect. An initial loss of Xenon-135 occurs during a reactor power increase. The greatest contributor to the loss of Xenon-135 is neutron absorption. This question is taken directly from the NRC Exam bank.
C. CORRECT: An initial loss of Xenon-135 occurs during a reactor power increase.
The greatest contributor to the loss of Xenon-135 is neutron absorption. This question is taken directly from the NRC Exam bank.
D. Incorrect. An initial loss of Xenon-135 occurs during a reactor power increase. The greatest contributor to the loss of Xenon-135 is neutron absorption. This question is taken directly from the NRC Exam bank.
Technical Reference(s):
WLP-OPS-TYR06 slide 94 Revision 8 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-TYR06 obj. 4 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam QID P460 in the NRC Exam Bank Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 1
55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 152 of 161 Examination Outline Cross-
Reference:
4 Group #
K/A #
192007 K1.04 Importance Rating 3.4 K/A Statement (192007K1.04) FUEL DEPLETION AND BURNABLE POISONS: Describe how and why boron concentration changes over core life Proposed Question:
RO 71 Rev:
0 During a 6 month period of continuous 100 percent power operation in the middle of a fuel cycle, the reactor coolant boron concentration must be decreased periodically to compensate for A. buildup of fission product poisons and decreasing control rod worth.
B. Fuel depletion and buildup of fission product poisons.
C. Decreasing control rod worth and burnable poison burnout.
D. Burnable poison burnout and fuel depletion.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 153 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. Fuel depletion adds negative reactivity over core life. Buildup of fission product poison adds negative reactivity over core life. Boron concentration must be decreased over core life to compensate for this negative reactivity.
B. CORRECT: Fuel depletion adds negative reactivity over core life. Buildup of fission product poison adds negative reactivity over core life. Boron concentration must be decreased over core life to compensate for this negative reactivity. This question was taken directly from the NRC Exam bank.
C. Incorrect. Fuel depletion adds negative reactivity over core life. Buildup of fission product poison adds negative reactivity over core life. Boron concentration must be decreased over core life to compensate for this negative reactivity.
D. Incorrect. Fuel depletion adds negative reactivity over core life. Buildup of fission product poison adds negative reactivity over core life. Boron concentration must be decreased over core life to compensate for this negative reactivity.
Technical Reference(s):
WLP-OPS-TYR07 pages 41, 45 and 58 Rev. 6 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-TYR07 obj. 3 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam QID P464 in the NRC Exam Bank Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 1
55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 154 of 161 Examination Outline Cross-
Reference:
4 Group #
K/A #
192008 K1.13 Importance Rating 3.6 K/A Statement (192008K1.13) REACTOR OPERATIONAL PHYSICS: (INTERMEDIATE RANGE OPERATION) Discuss the concept of the POAH and its impact on reactor power Proposed Question:
RO 72 Rev:
0 Given:
Startup in progress Reactor is critical below the POAH RCS TAVG is 541°F and steady Group P CEAs have been withdrawn to achieve a 0.5 DPM startup rate Reactor power should stabilize __(1)__ the POAH, and RCS TAVG should be ___(1)___
541°F. (Assume no change in steaming rate)
___(1)____
___(2)____
A. equal to equal to B. equal to greater than C. greater than equal to D. greater than greater than
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 155 of 161 Proposed Answer:
D Explanation: (Optional)
When the POAH is reached, FTC and MTC will add negative reactivity which will cause reactor power to stabilize above the POAH. RCS Temperature goes up when the POAH is exceeded and will remain above the initial temperature if steaming rate is not raised.
A. Incorrect. See above.
B. Incorrect. See above C. Incorrect. See above D. CORRECT: See above Technical Reference(s):
WLP-OPS-TYR08 page 112 Rev. 9 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-TYR08 obj. 14 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 1
55.43 Comments:
A is essentially "none of the above" (not allowed). Also, two distractors have "create negative reactivity effect," while both of the others are different, which cues that either C or D is probably the correct answer. Need to revise this question. Revised the question such that A is no longer none of the above. Revised the distractors such that C and D are no longer cued as the right answer. Make the question W3 specific.
Question replaced on 7/19/23. Now W3 specific. SAT.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 156 of 161 Examination Outline Cross-
Reference:
3 Group #
4 K/A #
193003 K1.24 Importance Rating 3.1 K/A Statement (193003K1.24) STEAM: Explain the usefulness of steam tables to the control room operator Proposed Question:
RO 73 Rev:
0 Given:
RCS leak in progress.
RCS Temperature is 536°F and steady RCS pressure is 2000 psia and lowering As RCS pressure lowers, when will subcooling equal 0°F? (Assume RCS Temperature is remains constant)
A. 930 psia B. 945 psia C. 962 psia D. 977 psia
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 157 of 161 Proposed Answer:
A Explanation: (Optional)
A. CORRECT: Using steam tables, saturation pressure for 536°F is 930.6 psia.
B. Incorrect. Using steam tables, saturation pressure for 536°F is 930.6 psia. If 15 psia is added for unit conversion, this answer is calculated.
C. Incorrect. Using steam tables, saturation pressure for 536°F is 930.6 psia. If the table is misread, the pressure directly below the correct answer is 962 psia.
D. Incorrect. Using steam tables, saturation pressure for 536°F is 930.6 psia. If the table is misread, the pressure directly below the correct answer is 962 psia. When 15 is added for unit conversion, this answer is calculated.
Technical Reference(s):
Steam Tables (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
Steam Tables Learning Objective:
WLP-OPS-TYR03 obj. 7, 8 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam QID P275 Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 14 55.43 Comments: Discuss possibility of stem having a greater connection to a Waterford system. Tied to Waterford by using temperature and pressure that are consistent with Waterford 3 parameters. SAT.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 158 of 161 Examination Outline Cross-
Reference:
4 Group #
K/A #
193004 K1.15 Importance Rating 2.8 K/A Statement (193004K1.15) THERMODYNAMIC PROCESS: (THROTTLING AND THE THROTTLING PROCESS) Determine the exit conditions for a throttling process based on the use of steam and/or water Proposed Question:
RO 74 Rev:
0 The plant is operating with the following main steam parameters at the main turbine steam inlet valves:
Pressure = 1,050 psia Quality = 100 percent The main turbine steam chest pressure is 400 psia. Assuming an ideal throttling process, which one of the following describes the steam in the steam chest?
A. Saturated, 96 percent quality B. Saturated, 98 percent quality C. Saturated, 100% quality D. Superheated
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 159 of 161 Proposed Answer:
B Explanation: (Optional)
A. Incorrect. Calculated using Mollier diagram using moisture lines and pressure lines.
The student must understand this is a constant enthalpy process.
B. CORRECT: Calculated using Mollier diagram using moisture lines and pressure lines. The student must understand this is a constant enthalpy process.
C. Incorrect. Calculated using Mollier diagram using moisture lines and pressure lines.
The student must understand this is a constant enthalpy process.
D. Incorrect. Calculated using Mollier diagram using moisture lines and pressure lines.
The student must understand this is a constant enthalpy process.
Technical Reference(s):
WLP-OPS-THY03 pages 80 and 81 (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
Steam Tables Learning Objective:
WLP-OPS-THY03 obj. 8 (As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New X
Question History:
Last NRC Exam QID P7140 in the NRC Exam Bank Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
10 CFR Part 55 Content:
55.41 14 55.43 Comments: No comments.
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 160 of 161 Examination Outline Cross-
Reference:
3 Group #
4 K/A #
193009 K1.01 Importance Rating 2.8 K/A Statement (193009 K1.01) CORE THERMAL LIMITS: Explain radial peaking factor.
Proposed Question:
RO 75 Rev:
0 Radial peaking factor (FXY) is the ratio of the ____(1)____ heat flux at one core elevation to the average heat flux for ___ (2)__ __ elevation.
____(1)____
___(2)____
A. minimum the same B. minimum a different C. maximum the same D. maximum a different
2023 NRC Exam RO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 161 of 161 Proposed Answer:
C Explanation: (Optional)
A. Incorrect. Plausible since minimum heat flux is used in the calculation of average heat flux. The same plane is correct.
B. Incorrect. Plausible since minimum heat flux is used in the calculation of average heat flux. A different plane is plausible since it is used to calculate axial or linear heat flux.
C. CORRECT. explanation of radial peaking factor.
D. Incorrect. Plausible since maximum heat flux is correct and a different plane is used to calculate axial or linear heat flux.
Technical Reference(s):
WLP-OPS-TYH09, Core Thermal Limits (Attach if not previously provided)
(including version/revision number)
Proposed references to be provided to applicants during examination:
None Learning Objective:
WLP-OPS-TYH09 Objective 2 (As available)
Question Source:
Bank #
X Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam None Question Cognitive Level:
Memory or Fundamental Knowledge 2
Comprehension or Analysis 10 CFR Part 55 Content:
55.41 1
55.43 Comments: No comments.
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 1 of 25 Question 76:
SRO 1 Given:
An Excess Steam Demand occurred SIAS, CIAS, MSIS and CSAS have been initiated After entering OP-902-004, Excess Steam Demand Recovery, the BOP reports that CFC A has tripped on overcurrent The CRS should determine that the ____(1)____ safety function is not met. The crew should _____(2)_____.
(1)
(2)
A.
containment isolation go to OP-902-008, Functional Recovery procedure B.
containment temperature and pressure control go to OP-902-008, Functional Recovery procedure C.
containment isolation remain in OP-902-004, Excess Steam Demand Recovery procedure D.
containment temperature and pressure control remain in OP-902-004, Excess Steam Demand Recovery procedure
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 2 of 25 Question 77:
SRO 2 Given:
Plant is at 100% power Charging Pump A is running NAO notifies the control room of a failed pulsation dampener for Charging Pump A ATC operator identifies charging flow at 34 gpm and discharge pressure fluctuating The crew should enter OP-901-112, Charging or Letdown Malfunction, subsection
____(1)____. The CRS should direct the crew to ____(2)____.
(1)
(2)
A.
E1 Charging Malfunction secure charging pump A, verify adequate VCT level, and start a standby charging pump B.
E1 Charging Malfunction place all charging pumps to OFF C.
E3 Gas Bound Charging Pumps secure charging pump A, verify adequate VCT level, and start a standby charging pump D.
E3 Gas Bound Charging Pumps place all charging pumps to OFF
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 3 of 25 Question 78:
SRO 3 Given:
RCS TAVG is 300°F and stable Pressurizer level is 43% and stable Shutdown Cooling Trains A and B are in service RCPs are secured The following alarm is received in the Control Room:
LPSI PUMP A FLOW LOST The BOP reports LPSI Pump A shows steady LOW flow and amperage is less than expected for the existing configuration.
The CRS should enter OP-901-131, Shutdown Cooling Malfunction, subsection
___(1)___ and direct the BOP to _ (2)_ __.
(1)
(2)
A.
E2 Loss of Shutdown Cooling Flow stop LPSI Pump A B.
E2 Loss of Shutdown Cooling Flow raise LPSI Pump A Shutdown Cooling flow C.
E4 System Malfunction in Mode 4 stop LPSI Pump A D.
E4 System Malfunction in Mode 4 raise LPSI Pump A Shutdown Cooling flow
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 4 of 25 Question 79:
SRO 4 Given:
Reactor tripped from 100% power due to a momentary grid disturbance EDG A and EDG B are running with their respective output breakers closed Both load sequencers have timed out Implementation of OP-902-009, Appendix 1, Diagnostic Flow Chart, is in progress The CRS should diagnose to ____(1)____ and the implementation of Appendix 20, Operation of DCT Sump Pumps, is ____(2)____.
__________(1)___________
_____(2)______
A.
OP-902-001, Reactor Trip Recovery required B.
OP-902-001, Reactor Trip Recovery NOT required C.
OP-902-003, Loss of Offsite Power required D.
OP-902-003, Loss of Offsite Power NOT required
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 5 of 25 Question: 80 SRO 5 Given:
Plant is at 100% power when a loss of B-DC-S occurs The CRS should implement _ _(1)_. To prevent overflowing the Fuel Oil Day Tank, OP-901-313 Loss of a 125V DC Bus, will direct the crew to secure the EDG B Fuel Oil Transfer Pump by locally ___(2)___.
_____________(1)____________
____________(2)_____________
A.
OP-901-313, Loss of a 125V DC Bus ONLY operating the C/S at the EDG control panel B.
OP-901-313, Loss of a 125V DC Bus ONLY opening the breaker for the Fuel Oil Transfer Pump at MCC-312B C.
OP-901-313, Loss of a 125V DC Bus, and OP-902-000, Standard Post Trip Actions concurrently operating the C/S at the EDG control panel D.
OP-901-313, Loss of a 125V DC Bus and OP-902-000, Standard Post Trip Actions concurrently opening the breaker for the Fuel Oil Transfer Pump at MCC-312B
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 6 of 25 Question 81:
SRO 6 Given:
Plant is in Mode 1 The Shift Manager receives a call from the grid operator informing him that Waterfords post-trip grid voltage would be 222 kV.
Current Line A and B grid voltages do NOT meet the requirements of OP-903-066, Electrical Breaker Alignment Check Based on this information, the crew should ____(1)____ because a projected trip of Waterford 3 should result in ____(2)_____.
(1)
(2)
A.
declare both AC off-site circuits inoperable and enter both Tech Spec 3.8.1.1 and TRM 3.8.1.1 post-trip switchyard voltages that are inadequate to supply emergency loads during a design basis accident B.
declare both AC off-site circuits inoperable and enter both Tech Spec 3.8.1.1 and TRM 3.8.1.1 post trip excessive current from reduced voltage that will actuate the Waterford 3 SUT protective relays C.
enter only TRM 3.8.1.1 post-trip switchyard voltages that are inadequate to supply emergency loads during a design basis accident D.
enter only TRM 3.8.1.1 post trip excessive current from reduced voltage that will actuate the Waterford 3 SUT protective relays
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 7 of 25 Question 82:
SRO 7 Given:
Plant is stable at 100% power RCS Temperature loop 1 Hot Leg (RC-ITI-0111X) has failed low The crew has entered OP-901-110, Pressurizer Level Control Malfunction As a result of the failed temperature instrument, Letdown flow should ____(1)____. The CRS should implement subsection _____(2)_____ of OP-901-110.
___(1) _
____ _(2)_ ____
A.
rise E1 Pressurizer Level Control Channel Malfunction B.
rise E2 Pressurizer Level Setpoint Malfunction C.
lower E1 Pressurizer Level Control Channel Malfunction D.
lower E2 Pressurizer Level Setpoint Malfunction
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 8 of 25 Question 83:
SRO 8 The crew has entered OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown, due to a fire in the Control Room.
The CRS should direct a Nuclear Auxiliary Operator to perform __ __(1)_ ___ as an immediate operator action.
If Nuclear Indication becomes suspect at LCP-43, the crew should consider performing 4, Connecting Excore Neutron Flux Channel D Indicator. This task is performed at the preamplifier located in the ____(2)____.
_________(1)_________
___________(2)_____________
A., Electrical Lockout of Reactor Coolant Pumps RAB Relay Room B., Electrical Lockout of Reactor Coolant Pumps RAB Electrical Penetration Area C., Local Operation of ADVs RAB Relay Room D., Local Operation of ADV RAB Electrical Penetration Area
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 9 of 25 Question 84:
SRO 9 Given:
Reactor startup is in progress in accordance with OP-010-003, Plant Startup CEAs are in Manual Sequential CEA group positions are:
Shutdown Banks A & B are at their upper electrical limit Reg Groups 1-3 are at their upper electrical limit Reg Group 4 is at 100 inches Reg Groups 5 and 6 are All Rods In Nuclear instrumentation and Reactor Engineering reports indicate that criticality is expected in the next 50 inches of rod pull.
Per OP-010-003, The CRS should direct ___(1)___ and then direct the ATC to emergency borate until the required shutdown margin of ___(2)___%k/k is reached.
(1)
(2)
A. a reactor trip 5.15 B. a reactor trip 4.6 C. full insertion of all Reg Group and Group P CEAs using the shim switch 4.6 D. full insertion of all Reg Group and Group P CEAs using the shim switch 5.15
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 10 of 25 Question 85:
SRO 10 Given:
CRS is prioritizing safety functions in accordance with OP-902-008, Functional Recovery Procedure SIAS, CIAS, MSIS and CSAS are present Two CEAs have failed to insert and ATC has verified immediate actions are complete ATC reports that Reactor Power is 10-5 % and dropping CRS is evaluating the Reactivity Control Safety Function
____(1)____ safety function acceptance criteria are met. CRS will implement success path _____(2)_____ for Reactivity control.
(1)
(2)
A.
Only RC-1 RC-1 B.
Only RC-1 RC-2 C.
RC-1 and RC-2 RC-2 D.
RC-1 and RC-2 RC-1
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 11 of 25 Question 86:
SRO 11 Given:
RCS temperature is 180°F and steady RCS pressure is 320 PSIA and steady SDC Train B is in service SDC Train A is secured The following annunciators are received:
SIAS Train A Logic Initiated (Cabinet K, G-19)
SIAS Train B Logic Initiated (Cabinet K, G-20)
LOOP 1 SDC RELIEF VLV ACTIVE (Cabinet M, A-7)
The addition of borated water ____(1)____ the capacity of SI-406B, RC Loop 1 SDC Suction LTOP relief to CNTMT Sump. The CRS should secure High Pressure Safety Injection Pumps in accordance with the guidance in ____(2)____.
(1)
(2)
A.
is within OP-901-504, Inadvertent ESFAS Actuation B.
is within OP-901-131, Shutdown Cooling Malfunction C.
exceeds OP-901-504, Inadvertent ESFAS Actuation D.
exceeds OP-901-131, Shutdown Cooling Malfunction
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 12 of 25 Question 87:
SRO 12 Given:
Plant at 100% power ATC reports PZR spray valves have opened Pressurizer Pressure HI/LO annunciator alarms PZR pressure is 2150 psia and lowering PZR pressure controller output at 0%
PZR spray valve controller output at 100%
When PZR spray valve controller was placed in manual control and output was lowered to minimum, one PZR spray valve remained open The reactor was manually tripped In accordance with OP-901-120, Pressurizer Pressure Control Malfunction, subsection
_____(1)_____, the crew should stabilize RCS pressure by ____(2)____.
(1)
(2)
A.
E2, Pressurizer Pressure Controller Malfunction taking manual control of pressurizer pressure controller B.
E2, Pressurizer Pressure Controller Malfunction securing necessary RCPs C.
E3, Pressurizer Spray Valve Malfunction taking manual control of pressurizer pressure controller D. E3, Pressurizer Spray Valve Malfunction securing necessary RCPs
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 13 of 25 Question 88:
SRO 13 Given:
Plant is at 100% power RCP Speed Sensor input to CPC Channel A fails causing LPD and DNBR trips on CPC Channel A Crew attempted to bypass bistables 3 and 4 on CPC Channel A but the bypass pushbuttons on CP-10 failed to go to bypass The CRS should direct the BOP to utilize the power trip test interlock in accordance with OP-009-007, Plant Protection System and _____________________.
A. place the Linear Calibrate Switch to zero to bypass bistables 3 and 4 B. place the Linear Calibrate Switch to zero to trip bistables 3 and 4 C. pull the associated bistable comparator cards to bypass bistables 3 and 4 D. pull the associated bistable comparator cards to trip bistables 3 and 4
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 14 of 25 Question 89:
SRO 14 Given:
Plant is at 100% power when a loss of the 125 VOLT DC BUS TGB-DC occurs The crew has entered OP-901-313, Loss of a 125 Volt DC Bus The loss of the TGB-DC bus will result in the failure to load for all ____(1)____. If the 125 VOLT DC BUS TGB-DC cannot be restored, the crew should be required to perform the actions of OP-901-313 subsection E4, 125 VOLT DC BUS TGB-DC concurrently with _____(2)_____.
___________(1)__________
____ _(2)_ ____
A.
Station Air Compressors only OP-010-005, Plant Shutdown B.
Station Air Compressors only OP-901-212, Rapid Plant Power Reduction C.
Station Air and Instrument Air Compressors OP-010-005, Plant Shutdown D.
Station Air and Instrument Air Compressors OP-901-212, Rapid Plant Power Reduction
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 15 of 25 Question 90:
SRO 15 Given:
The plant is at 100% power when the following annunciator is received:
EDG A FUEL OIL STORAGE TANK LEVEL HI/LO The minimum required levels for Diesel Fuel Oil Storage local indication and PMC indication to meet TS 3.8.1.3, Diesel Fuel Oil, are located in ____(1)____.
If Diesel Fuel Oil Storage Tank is below a six day supply, ____(2)____ entry is required.
(1)
(2)
A.
OP-009-002, Emergency Diesel Generator TS 3.8.1.3, Diesel Fuel Oil Storage only B.
OP-009-002, Emergency Diesel Generator TS 3.8.1.3, Diesel Fuel Oil Storage and TS 3.8.1.1, AC Electrical Power Sources C.
OP-903-001 Technical Specification Surveillance Logs TS 3.8.1.3, Diesel Fuel Oil Storage only D.
OP-903-001 Technical Specification Surveillance Logs TS 3.8.1.3, Diesel Fuel Oil Storage and TS 3.8.1.1, AC Electrical Power Sources
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 16 of 25 Question 91:
SRO 16 Given:
Plant is at 100% power Letdown flow is 50 gpm and rising PZR level indicator RC-ILI-110X indicates 55% and lowering PZR level indicator RC-ILI-110Y indicates 54% and lowering The ATC reports that the pressurizer level setpoint on the Pressurizer Level Controller (RC-ILIC-0110) is 55.6%
The output of the Pressurizer Level Controller (RC-ILIC-0110) is 90%
The CRS should enter ____(1)____ and direct the ATC to take manual control of the
____(2)____ to restore Pressurizer level.
(1)
(2)
A. OP-901-110, Pressurizer Level Control Malfunction Pressurizer Level Controller (RC-ILIC-0110)
B. OP-901-112, Charging and Letdown Malfunction Pressurizer Level Controller (RC-ILIC-0110)
C. OP-901-110, Pressurizer Level Control Malfunction Letdown Flow Control Valves controller (RC-IHIC-0110)
D. OP-901-112, Charging and Letdown Malfunction Letdown Flow Control Valves controller (RC-IHIC-0110)
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 17 of 25 Question 92:
SRO 17 Given:
Power is 100%
All CEAs fully withdrawn Five minutes later, the ATC reports the following:
CEA 38 indicates 135 inches on the CP-2 CEAPDS CEA 38 indicates 150 inches on the PMC Both the Upper and Lower Electrical Limit lights for CEA 38 are extinguished All Rod Bottom lights are extinguished Tcold is 541 ºF and slowly dropping To verify CEA position, the CRS should request indication on the ____(1)____. The CRS should enter OP-901-102, CEA or CEDMCS Malfunction, sub-section _____(2)_____.
(1)
(2)
A. CPC that CEA 38 is targeted to E1, CEA Misalignment Greater than 7 inches B. CPC that CEA 38 is targeted to E5, CEA Position Indication Malfunction C. CP-2 digital meter for CEA 38 E1, CEA Misalignment Greater than 7 inches D. CP-2 digital meter for CEA 38 E5, CEA Position Indication Malfunction
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 18 of 25 Question 93:
SRO 18 Given: (REFERENCE PROVIDED)
Plant is in MODE 3 Fuel movement is occurring in the Spent Fuel Pool Containment Purge Monitor Reading Monitor Alarm/Trip Setpoint ARM-IRE-5024S reads 150 mR/hr 290 mR/hr ARM-IRE-5025S reads 140 mR/hr 300 mR/hr ARM-IRE-5026S reads 19 mR/hr 40 mR/hr ARM-IRE-5027S reads 15 mR/hr 50 mR/hr ARM-IRE-____(1)___ are inoperable. Technical Specification 3.3.3.1 entry is
___(2)____.
(1)
(2)
A. 5025S and 5027S required B. 5024S and 5026S not required C. 5025S and 5027S not required D. 5024S and 5026S required
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 19 of 25 Question 94:
SRO 19 Given:
Reactor Trip has occurred The BOP is Verifying RCS Heat Removal in accordance with OP-902-000, Standard Post Trip Actions The BOP informs the CRS that power to the Moisture Separator Reheater (MSR)
Control Panel is not available The CRS should direct the Turbine Building watch to isolate the MSR by A. isolating the air and gagging closed all 5 inch and 10 inch Temperature Control valves B. de-energizing and manually closing the 5 inch and 10 inch Motor Operated valves only C. de-energizing and manually closing the 1 inch, 5 inch and 10 inch Motor Operated valves only D. isolating the air and opening the petcock to all 5 inch and 10 inch Temperature Control valves
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 20 of 25 Question 95:
SRO 20 Given:
Plant is performing a cooldown for a refueling outage RCS temperature is 195 ºF RCS pressure is 350 psia EDG B is tagged out Offsite power train A is then declared inoperable because of a voltage problem.
The CRS should ensure ________ is aligned as the operable boration flow path per OP-903-002, Boration Flow Path Valve Lineup Verification.
A.
Boric Acid Makeup Tank B Gravity Feed Valve and Charging Pump B B.
Boric Acid Makeup Tank A Gravity Feed Valve and Charging Pump A C.
Boric Acid Makeup Pump A and Charging Pump A
D. Boric Acid Makeup pump B and Charging pump B
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 21 of 25 Question 96:
SRO 21 Per TS 3.6.3, a locked closed containment isolation valve can be opened on an intermittent basis under administrative controls.
These administrative controls include assigning an operator ____(1)____. The list of containment isolation valves can be found in _____(2)____.
(1)
(2)
A.
to close the valve within four hours of an accident situation TS 3.6.3 B.
to be stationed at the valve controls TS 3.6.3 C.
to close the valve within four hours of an accident situation TRM 3.6.3 D.
to be stationed at the valve controls TRM 3.6.3
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 22 of 25 Question 97:
SRO 22 A required 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> technical specification surveillance was inadvertently missed and was last performed 7 days ago. A risk evaluation has been performed and the risk impact is being managed.
Technical Specification 4.0.3 requires the surveillance be performed no later than
___________ from the time of discovery or the system/component must immediately be declared inoperable.
A. 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> B. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> D. 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 23 of 25 Question 98:
SRO 23 Per TS 3.9.10.1, Water Level - Reactor Vessel, at least 23 feet of water shall be maintained over top of the ___(1)___ during movement of irradiated fuel within reactor pressure vessel.
Per the TS basis, this restriction ensures sufficient water depth is available such that
___(2)___.
(1)
(2)
A.
fuel seated in reactor pressure vessel iodine released is within limits in the event of a rupture of an irradiated fuel assembly B.
reactor pressure vessel flange iodine released is within limits in the event of a rupture of an irradiated fuel assembly C.
reactor pressure vessel flange sufficient cooling capacity is maintained D.
fuel seated in reactor pressure vessel sufficient cooling capacity is maintained
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 24 of 25 Question:99 SRO 24 Per EP-002-102, Emergency Operations Facility (EOF), Activation, Operation and Deactivation, the lowest level of event classification that requires activation of the Emergency Operations Facility (EOF) is an ____(1)____. It is the responsibility of the
_____(2)_____ to direct the activities of the EOF including overall management of the total emergency response.
____(1)____
____(2)____
A.
Alert Emergency Plant Manager B.
Alert Emergency Director C.
Unusual Event Emergency Plant Manager D.
Unusual Event Emergency Director
2023 NRC Exam SRO Written Exam Worksheet Revision 3 Facility:
Waterford 3 Page 25 of 25 Question:100 SRO 25 At time 0900, an Alert classification was declared The Initial Notification to offsite agencies must be made no later than time
____(1)_____. Without a change in emergency classification, subsequent notifications to offsite agencies must be made no later than 60 minutes of the ____(2)_____.
_ _(1)__
_________(2)_______
A.
0915 previous notification message B.
0915 alert classification C.
0930 previous notification message D.
0930 alert classification
2023 NRC Exam Waterford 3 Senior Reactor Operator
- 1.
C
- 26.
C
- 2.
D
- 27.
C
- 3.
A
- 28.
D
- 4.
B
- 29.
B
- 5.
C
- 30.
D
- 6.
C
- 31.
A
- 7.
A
- 32.
D
- 8.
C
- 33.
C
- 9.
D
- 34.
A
- 10.
A
- 35.
C
- 11.
B
- 36.
B
- 12.
D
- 37.
B
- 13.
D
- 38.
C
- 14.
B
- 39.
A
- 15.
A
- 40.
A
- 16.
C
- 41.
C
- 17.
B
- 42.
D
- 18.
C
- 43.
C
- 19.
B
- 44.
D
- 20.
A
- 45.
B
- 21.
C
- 46.
C
- 22.
D
- 47.
A
- 23.
A
- 48.
D
- 24.
A
- 49.
A
- 25.
D
- 50.
B
2023 NRC Exam Waterford 3 Senior Reactor Operator
- 51.
A S1.
C
- 52.
B S2.
D
- 53.
A S3.
C
- 54.
A S4.
C
- 55.
D S5.
D
- 56.
B S6.
A
- 57.
B S7.
B
- 58.
A S8.
B
- 59.
B S9.
B
- 60.
C S10.
C
- 61.
D S11.
A
- 62.
C S12.
D
- 63.
D S13.
B
- 64.
D S14.
D
- 65.
C S15.
B
- 66.
B S16.
A
- 67.
A S17.
A
- 68.
D S18.
C
- 69.
C S19.
D
- 70.
C S20.
C
- 71.
B S21.
D
- 72.
D S22.
C
- 73.
A S23.
B
- 74.
B S24.
B
- 75.
C S25.
A