Text

08 Draft Written Exam
	ML20267A207
Person / Time
Site:	Waterford
Issue date:	08/26/2020
From:	Greg Werner; Operations Branch IV
To:	; Entergy Operations
References
	Download: ML20267A207 (212)
	v • d • e

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 007 (CE02) EK1.2 Importance Rating 3.0 K/A Statement Knowledge of the operational implications of the following concepts as they apply to the (Reactor Trip Recovery): Normal, abnormal and emergency operating procedures associated with (Reactor Trip Recovery).

Proposed Question: RO 1 Rev: 0 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.

The CRS should direct the crew to ______.

A. Trip the reactor only B. Trip the reactor and Emergency Borate C. Fully insert all Regulating Group CEAs using the CEA shim switch D. Withdraw CEAs another 25 inches and observe proper response of nuclear instrumentation.

Revision 0 Facility: Waterford 3 Page 1 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. The CRS will direct tripping the reactor but to ensure adequate shutdown margin the crew must also emergency borate.

B. CORRECT: The applicant will determine that the next pull of CEAs (since the shim switch is in MS) will locate group 5 at 50 inches withdrawn. Per step 9.4.36 of OP-010-003, if Nuclear Instrumentation shows evidence that actual criticality is expected to occur below the PDIL of group 5 at 60, then immediately trip the reactor and emergency borate. This action is required to ensure adequate shutdown margin. This question meets the K/A because the normal operating procedure indirectly puts the crew into the reactor trip recovery procedure (crew will eventually diagnose to OP-902-001) and the crew will be performing the off-normal procedure (Emergency Boration OP-901-103) concurrently with OP-902-001.

C. Incorrect. From step 9.4.41 of OP-010-003. This would be the correct action to take if the CEAs were within TS 3.1.3.6 Transient Insertion limits but outside the calculations of the ECC.

D. Incorrect. From step 9.4.34 of OP-010-003. This would be the correct action to take if the CEAs were within the calculations of the ECC and within the requirements of TS 3.1.3.6 Transient Insertion limits.

Technical Reference(s): OP-010-003 step 9.4.36, 9.4.34, 9.4.41 Rev. 351 (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 and 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 X 10 CFR Part 55 Content: 55.41 6, 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 2 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000008 AK2.03 Importance Rating 2.5 K/A Statement Knowledge of the relationship between the Pressurizer Vapor Space Accident and the following systems or components: Controllers and positioners Proposed Question: RO 2 Rev: 0 Given:

Plant is operating at 100% power when Pressurizer Safety (RC-317A) lifts and does NOT reseat.

Pressurizer level indication will initially trend __(1)__ and the Pressurizer Pressure Controller, RC-IPIC-0100 output will be trending to a __(2)__ output.

(1)_ __(2)__

A. up lower B. up higher C. down lower D. down higher Revision 0 Facility: Waterford 3 Page 3 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT. Due to the loss of inventory being out of a pressurizer safety valve, indicated level will go up due to the low pressure area now at the top of the pressurizer. The loss of inventory will create a lowering RCS pressure and combined with the rise in pressurizer level, the pressure controller will attempt to energize heaters by lowering its output.

B. Incorrect: First part is correct due to the leak being from the top of the pressurizer.

The second part is incorrect but plausible. During a normal pressurizer level rise, pressure would trend up which would make the pressure controller output signal become higher.

C. Incorrect: Plausible since most leaks from the RCS, but not in the pressurizer steam space, would cause indicated pressurizer level to lower. Second part is correct.

D. Incorrect: Plausible since most leaks from the RCS, but not in the pressurizer steam space, would cause indicated pressurizer level to lower. The second part is incorrect but plausible. During a normal pressurizer level rise, pressure would trend up which would make the pressure controller output signal become higher.

Technical Reference(s): OP-901-111 Rev. 305, OP-901-120 Rev 302 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PLC00 obj. 1,3 (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 X 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 4 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000009 EK 3.16 Importance Rating 3.8 K/A Statement Knowledge of the reasons for the following responses as they apply to a Small-Break LOCA: Containment temperature, pressure, humidity and level limits Proposed Question: RO 3 Rev: 1 Given:

A LOCA has occurred

Crew is performing the actions of OP-902-002, Loss of Coolant Accident Recovery Procedure

Pressurizer level indicates 12% and rising

Both Steam Generator levels are 51% NR and rising, being controlled by EFW in manual

CET temperature is 440 degrees F

RCS pressure is 580 psia

QSPDS Reactor Vessel level 5 indicates NOT VOIDED

Containment temperature is 215 degrees F Which of the following must the CRS direct prior to the crew throttling HPSI flow?

A. Raise vessel plenum level to 100% due to possible core voiding.

B. Raise subcooling to 28° F due to harsh containment conditions.

C. Raise pressurizer level to >23% due to harsh containment conditions.

D. Raise Steam Generator levels to greater than 55% NR due to possible core voiding.

Revision 0 Facility: Waterford 3 Page 5 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Vessel level is satisfied when level 5 indicates not voided or plenum level is greater than 80%.The plenum is not required to be full.

B. Incorrect. The RCS is 42 degrees subcooled, based on CET temperature and pressurizer pressure which meets the requirement of 28 degrees subcooled C. CORRECT: Pressurizer level must be greater than 7% to meet HPSI throttle criteria. However, harsh environment conditions exist in containment due to containment temperature >200 degrees F. Therefore, minimum pressurizer level is 23% and is currently not meeting HPSI throttle criteria. The guidance for harsh conditions in containment is located in the administrative procedure OI-038-000, EOP Operations Expectations/Guidance procedure and must be applied to this question.

D. Incorrect. Steam Generator levels must be maintained or being restored to 55%

NR. The operator has control of steam generator level in manual and level is capable of being restored.

Technical Reference(s): OP-902-002 step 23 Rev. 21 (Attach if not previously provided) OI-038-000 page 6 Rev. 19 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 obj. 4 (As available)

WLP-OPS-PPE02 obj. 18 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 X 10 CFR Part 55 Content: 55.41 10 55.43 Comments: Free review question. No comments.

Revision 0 Facility: Waterford 3 Page 6 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000011 EA1.16 Importance Rating 3.5 K/A Statement Ability to operate and monitor the following as they apply to a Large-Break LOCA:

Balancing of HPI loop flows Proposed Question: RO 4 Rev: 0 Given:

Crew has entered OP-902-002, Loss of Coolant Accident Recovery Procedure due to a large break LOCA

Hot and Cold Leg Injection is being aligned per OP-902-009 Appendix 15, Hot and Cold Leg Injection When hot and cold leg injection has been established, OP-902-009 Appendix 15 directs the ATC operator to adjust ____(1)____ leg injection flows to obtain ______(2)______.

(1) (2)

A. hot loop 1 cold leg flows equal to loop 1 hot leg flow and loop 2 cold leg flows equal to loop 2 hot leg flow B. hot the sum of all cold leg flows equal to the sum of the hot leg flows C. cold loop 1 cold leg flows equal to loop 1 hot leg flow and loop 2 cold leg flows equal to loop 2 hot leg flow D. cold the sum of all cold leg flows equal to the sum of the hot leg flows Revision 0 Facility: Waterford 3 Page 7 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Part 1 is correct. Part 2 is plausible if the applicant determines that it is desired to match flows within Loop 1 and within Loop 2 of the RCS. There is sometimes confusion with this during JPMs on this task.

B. CORRECT: Step 3 of OP-902-009 states When Hot and Cold Leg Injection flow has been established, THEN adjust SI-506A and SI-506B to obtain the sum of ALL Cold leg flows equal to the sum of the Hot leg flows.

C. Incorrect. Part 1 is plausible because each cold leg has an associated flow control valve and can be throttled to match flow, but this is not the guidance provided in Appendix 15. Part 2 is plausible if the applicant determines that it is desired to match flows within Loop 1 and within Loop 2 of the RCS. There is sometimes confusion with this during JPMs on this task.

D. Incorrect. Part 1 is plausible because each cold leg has an associated flow control valve and can be throttled to match flow, but this is not the guidance provided in Appendix 15. Part 2 is correct.

Technical Reference(s): OP-902-009 Appendix 15 Rev. 319 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 8 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000015 AA2.01 Importance Rating 3.0 K/A Statement Ability to determine and interpret the following as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow): Cause of RCP failure Proposed Question: RO 5 Rev: 0 Given:

Plant has tripped from 100% power

The ATC operator reports that Reactor Coolant Pump (RCP) 1A amps were indicating abnormally low at the time of the trip A ____(1)____ event has occurred for RCP 1A. The RPS _____(2)_____ trip is designed to protect the reactor core from this type event.

(1) (2)

A. locked rotor Reactor Coolant Flow-Low B. locked rotor DNBR Low C. sheared shaft DNBR Low D. sheared shaft Reactor Coolant Flow-Low Revision 0 Facility: Waterford 3 Page 9 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. The first portion of the question is incorrect because lower amps for RCP 1A would indicate a sheared shaft event due to a decreased load for RCP 1A. The second portion of the question is correct because the reactor would trip on Reactor Coolant Flow-Low. This is the purpose of the Reactor Coolant Flow-Low trip.

B. Incorrect. The first portion of the question is incorrect because lower amps for RCP 1A would indicate a sheared shaft event due to a decreased load for RCP 1A. The second portion of the question is also incorrect because 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.

C. Incorrect. The first portion of the question is correct because lower amps would be indicated on the CP-2 indication for RCP 1A due to a decreased load on the RCP.

The second portion of the question is incorrect because 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.

D. CORRECT: The first portion of the question is correct because lower amps would be indicated on the CP-2 indication for RCP due to a decreased load on the RCP. The second portion of the question is correct because the reactor would trip on Reactor Coolant Flow-Low. This is the purpose of the Reactor Coolant Flow-Low trip.

Technical Reference(s): TS 2.2.1 Basis pages B2-5, B2-6 and B2-7 (Attach if not previously provided) SD-PPS page 26 Rev. 19 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-RCP obj. 7 (As available)

WLP-OPS-CPC00 obj. 2 Question Source: Bank # RO28 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 3 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 10 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000022 G2.3.12 Importance Rating 3.2 K/A Statement Loss of Reactor Coolant Makeup 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel-handling responsibilities, access to locked high-radiation areas, alignment of filters, etc.

Proposed Question: RO 6 Rev: 0 Given:

Plant is at 100% power when a loss of all Charging has occurred due to a leak downstream of the Charging Pumps

The crew has entered OP-901-112, Charging or Letdown Malfunction and OP-901-402, High Airborne Activity in Reactor Auxiliary Building OP-901-112 section E1, Charging Malfunction, will direct the crew to close ____(1)____

and stop all Charging Pumps. OP-901-402 will direct the crew to reduce airborne activity levels, if required, by starting _____(2)_____ .

(1) (2)

A. CVC-101, Letdown either CVAS Train A or Stop Valve CVAS Train B B. CVC-101, Letdown the Personnel and Health Stop Valve Physics area ventilation C. CVC-103, Letdown either CVAS Train A or Inside Containment CVAS Train B Isolation D. CVC-103, Letdown the Personnel and Health Inside Containment Physics area ventilation Isolation Revision 0 Facility: Waterford 3 Page 11 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: OP-901-112 section E1 step 5 directs the crew close Letdown Stop Valve CVC-101 and stop Charging pumps if a Charging Line rupture has occurred. As stated in the first note in Section E1, if all Charging Pumps are secured, then CVC-101 will close on high Regen HX Outlet temperature. This automatic feature is why this procedure directs closure of CVC-101 and not CVC-103. OP-901-402 step 11 directs the crew to start either CVAS Train A or CVAS Train B (which will align emergency filtration) if required to reduce airborne activity levels.

B. Incorrect. Part 1 is correct. Part 2 is plausible because there is a section to start the Personnel and Health Physics area ventilation in the same procedure as starting CVAS units (OP-002-010). Starting this ventilation may help activity levels in the areas it serves but is not the ventilation that OP-901-402 directs to start.

C. Incorrect. CVC-103, Letdown Inside Containment Isolation, is plausible because this valve is located directly downstream of CVC-101 and gets an automatic signal to close (CIAS and SIAS). Part 2 is correct.

D. Incorrect. CVC-103, Letdown Inside Containment Isolation, is plausible because this valve is located directly downstream of CVC-101 and gets an automatic signal to close (CIAS and SIAS). Part 2 is plausible because there is a section to start the Personnel and Health Physics area ventilation in the same procedure as starting CVAS units (OP-002-010).

Starting this ventilation may help activity levels in the areas it serves but is not the ventilation that OP-901-402 directs to start.

Technical Reference(s): OP-901-112 page 10 Rev. 8 (Attach if not previously provided) OP-901-402 step 11 Rev. 5 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO30 obj. 3 (As available)

WLP-OPS-CVC00 obj. 3 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10,12 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 12 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000026 AA2.06 Importance Rating 2.8 K/A Statement Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The length of time after the loss of CCW flow to a component before that component may be damaged Proposed Question: RO 7 Rev: 0 Given:

At time 0810, the crew manually initiated a SIAS and CIAS due to lowering RCS pressure

At time 0815, CCW Pump A tripped

The crew diagnosed to OP-902-002, Loss of Coolant Accident Recovery Procedure

Station loads are powered from the Startup Transformers Without causing damage, the latest time that Emergency Diesel Generator A can remain in service without CCW flow is ____(1)____. If CCW flow cannot be restored to EDG A, the diesel is secured using the ____(2)____.

(1) (2)

A. 0820 emergency Shutdown push buttons on CP-1 B. 0820 overspeed trip plunger C. 0835 overspeed trip plunger D. 0835 emergency Shutdown push buttons on CP-1 Revision 0 Facility: Waterford 3 Page 13 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect: OI-038-000 step 5.2.4 states that EDGs can run without CCW for 10.7 minutes at 3.23 MW and for 20.9 minutes unloaded without causing damage to the diesels. EDG A started and is running unloaded due to the SIAS, therefore the crew has 20.9 minutes from 0815 to restore CCW flow. OP-902-002 requires the crew to pull the affected EDG overspeed trip plunger if CCW flow cannot be restored.

B. Incorrect: OI-038-000 step 5.2.4 states that EDGs can run without CCW for 10.7 minutes at 3.23 MW and for 20.9 minutes unloaded without causing damage to the diesels. EDG A started and is running unloaded due to the SIAS, therefore the crew has 20.9 minutes from 0815 to restore CCW flow. Part 2 is correct.

C. CORRECT: OI-038-000 step 5.2.4 states that EDGs can run without CCW for 10.7 minutes at 3.23 MW and for 20.9 minutes unloaded without causing damage to the diesels. EDG A started and is running unloaded due to the SIAS, therefore the crew has 20.9 minutes from 0815 to restore CCW flow upon the loss of CCW.

OP-902-002 requires the crew to pull the affected EDG overspeed trip plunger if CCW flow cannot be restored.

D. Incorrect: Part 1 is correct. OP-902-002 requires the crew to pull the affected EDG overspeed trip plunger if CCW flow cannot be restored.

Technical Reference(s): OI-038-000 step 5.2.4 Revision 19 (Attach if not previously provided) OP-902-002 step 10 Rev. 21 (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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 14 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000029 EA1.12 Importance Rating 4.1 K/A Statement Ability to operate and monitor the following as they apply to an Anticipated Transient Without Scram: M/G set power supply and reactor trip breakers.

Proposed Question: RO 8 Rev: 0 Which of the following describes how the Diverse Reactor Trip System (DRTS) inserts Control Element Assemblies (CEAs) during an Anticipated Transient Without Scram (ATWS) condition?

A. The shunt trip coils of the Reactor Trip Breakers are energized.

B. The undervoltage (UV) coils of the Reactor Trip Breakers are de-energized.

C. The CEDM Motor-Generator Set feeder breakers on busses 32A and 32B open.

D. The CEDM Motor-Generator Set output load contactors open.

Revision 0 Facility: Waterford 3 Page 15 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. The shunt trip coil is operated by the PPS system on an automatic reactor trip signal or from the Manual Trip Pushbuttons.

B. Incorrect. The undervoltage coil is operated by the PPS system on an automatic reactor trip signal or from the Manual Trip Pushbuttons.

C. Incorrect. These feeder breakers would be opened manually as part of the Standard Post Trip Actions if AUTO and MANUAL reactor trips failed to open the reactor trip breakers and DRTS fails to operate the CEDM MG Set load contactors.

D. CORRECT: Diverse Reactor Trip opens both CEDM MG set load contactors whenever DRTS is automatically or manually actuated.

Technical Reference(s): SD-ATS00 page 7 Rev. 5 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-ATS00 Obj. 2 (As available)

Question Source: Bank # RO9 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2011 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 16 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000038 EK3.09 Importance Rating 4.1 K/A Statement Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Rupture: Criteria for securing/throttling ECCS Proposed Question: RO 9 Rev: 0 Given:

A Steam Generator Tube Rupture in Steam Generator #1 (SG1) occurred

The crew has entered OP-902-007, Steam Generator Tube Rupture Recovery Procedure

Two Reactor Coolant Pumps remain in operation

The CRS has directed the ATC to verify proper subcool margin to determine if HPSI Throttle criteria is met The ATC will verify proper subcooling using ____(1)____ temperature indication. The Technical Guide for Steam Generator Tube Rupture Procedure states the reason for this is because the _____(2)_____ instruments are exposed to a mixture of core exit fluid and core bypass fluid due to their location inside the ICI Tubes.

(1) (2)

A. Thot Core Exit Thermocouple (CET)

B. Thot Thot C. Core Exit Core Exit Thermocouple Thermocouple (CET) (CET)

D. Core Exit Thot Thermocouple (CET)

Revision 0 Facility: Waterford 3 Page 17 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: Per the tech guide for OP-902-007, Steam Generator Tube Rupture Recovery Procedure, Thot should be used to determine RCS subcooling if RCPs are operating.

Representative CET temperature should be used if natural circulation is in progress. Because of the location of the CETs inside the ICI tubes, the CETs are exposed to a mixture of core exit fluid and core bypass fluid during forced circulation making them less accurate than Thot indication during forced flow conditions.

B. Incorrect. Part 1 is correct. Part 2 is plausible if the applicant does not have the knowledge of the locations of the Thot and CET instruments in the core.

C. Incorrect. Part 1 is plausible because CET temperatures are used to verify RCS subcooling but only during natural circulation conditions. In this case, two RCPs are running. Part 2 is correct.

D. Incorrect. Part 1 is plausible because CET temperatures are used to verify RCS subcooling but only during natural circulation conditions. In this case, two RCPs are running. Part 2 is plausible because the applicant could determine that the Thot instruments are less accurate because they are exposed a mixture of core exit fluid and core bypass fluid.

Technical Reference(s): TG-OP-902-007 page 47 Rev. 309 (Attach if not previously provided) OP-902-007 step 20 Rev. 18 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE07 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 X 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 18 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 040 (CE05)

EK2.1 Importance Rating 3.3 K/A Statement Knowledge of the interrelations between the (Excess Steam Demand) and the following:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Proposed Question: RO 10 Rev: 1 Given:

An Excess Steam Demand event has occurred

The reactor was manually tripped and the ATC reports the following parameters:

Pressurizer pressure is 1720 psia and dropping Containment pressure is 17.2 psia and rising The ATC verifies that the Charging pumps are taking a suction from the ____(1)____

and that Charging flow is approximately _____(2)________ gpm.

(1) (2)

A. Volume Control Tank 132 B. Volume Control Tank 88 C. Boric Acid Makeup Tanks 88 D. Boric Acid Makeup Tanks 132 Revision 0 Facility: Waterford 3 Page 19 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. The suction source after the trip but before the SIAS was coming from the VCT. Following the Reactor trip the ATC should verify three charging pumps (132 gpm) are running. After the SIAS, one of the charging pumps will trip leaving two running (88gpm).

B. Incorrect. The suction source after the trip but before the SIAS was coming from the VCT. Part 2 is correct.

C. CORRECT: SIAS occurs at either Pressurizer pressure of 1684 psia or Containment pressure > 17.1 psia. Therefore, a SIAS has occurred due to containment pressure.

On a SIAS, the suction source for the charging pumps swap to the BAMTs. Three charging pumps would start on the reactor trip, but one charging pump auto secures when the SIAS occurs. The capacity of one charging pump is 44 gpm, therefore, two charging pumps running is 88 gpm.

D. Incorrect. Part 1 is correct. Following the Reactor trip the ATC should verify three charging pumps (132 gpm) are running. After the SIAS, one of the charging pumps will trip leaving two running (88gpm).

Technical Reference(s): OI-038-000 step 5.4.72 Rev. 19 (Attach if not previously provided) SD-CVC page 30-31, 68 Rev. 19 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP=OPS-CVC00 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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Comments: Free review question. No comments.

Revision 0 Facility: Waterford 3 Page 20 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 00054 (CE06)

EK1.2 Importance Rating 3.2 K/A Statement Knowledge of the operational implications of the following concepts as they apply to the (Loss of Feedwater): Normal, abnormal and emergency operating procedures associated with (Loss of Feedwater).

Proposed Question: RO 11 Rev: 0 A total loss of feed water event has occurred. Upon entry into OP-902-006, Loss of Feedwater Recovery Procedure, the crew will secure ____(1)___.

BOTH Steam Generators have boiled dry. When a source of feedwater is available, feedwater flow is initiated slowly to _____(2)______ Steam Generator(s).

(1) (2)

A. all Reactor Coolant Pumps one B. all Reactor Coolant Pumps both C. one Reactor Coolant Pump both in each loop D. one Reactor Coolant Pump one in each loop Revision 0 Facility: Waterford 3 Page 21 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: Part 1: Step 6 of OP-902-006 directs the crew to secure all Reactor Coolant Pumps to minimize heat input into the RCS. Part 2: Step 5.4.75 of OI-038-000, EOP Operations Expectations/Guidance procedure directs the crew to initiate core cooling by slowly restoring feedwater flow to ONE steam generator.

B. Incorrect. Part 1 is correct. Part 2 is plausible because restoring feed to both SGs would restore core heat removal more quickly.

C. Incorrect. Part 1 is plausible because the previous W3 strategy was to secure one reactor coolant pump in each loop. OP-902-006 has since been revised to secure all RCPs (see 2015 RO EXAM RO13, the correct answer is secure one RCP in each loop). Part 2 is plausible because restoring feed to both SGs would restore core heat removal more quickly.

D. Incorrect. Part 1 is plausible because the previous W3 strategy was to secure one reactor coolant pump in each loop. OP-902-006 has since been revised to secure all RCPs (see 2015 RO EXAM RO13, the correct answer is secure one RCP in each loop.). Part 2 is correct.

Technical Reference(s): OI-038-000 step 5.4.75 Rev. 19 (Attach if not previously provided) OP-902-006 step 6 Rev 19 (including version/revision number) TG-OP-902-006 step 6 Rev. 19 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE obj. 9 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 22 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000055 EK1.01 Importance Rating 3.3 K/A Statement Knowledge of the operational implications of the following concepts as they apply to the Station Blackout: Effect of battery discharge rates on capacity Proposed Question: RO 12 Rev: 0 Given:

At 0700, a reactor trip occurred due to a Station Blackout

At 0710, the crew entered OP-902-005, Station Blackout Recovery

At 0715, the CRS directs the ATC operator to reduce battery loads Which of the following describes the clock time limit to accomplish these actions and the reason for those actions?

A. 0745; meet two hour coping time for 125 VDC buses to carry vital loads.

B. 0730; meet two hour coping time for125 VDC buses to carry vital loads.

C. 0745; meet four hour coping time for 125 VDC buses to carry vital loads.

D. 0730; meet four hour coping time for 125 VDC buses to carry vital loads Revision 0 Facility: Waterford 3 Page 23 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Time is incorrect. 30 minutes is from the time of the SBO occurrence.

Coping time is four hours. Two hours is TS 3.8.2.1 time limit for restoration of an inoperable battery bank.

B. Incorrect. Part 1 is correct. Coping time is four hours. Two hours is TS 3.8.2.1 time limit for restoration of an inoperable battery bank.

C. Incorrect. Time is incorrect. 30 minutes is from the time of the SBO occurrence.

Coping time is correct. The station blackout coping time analysis is performed in EC-E89-016, which is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

D. CORRECT: Time is correct. 30 minutes is from the time of the SBO occurrence.

The station blackout coping time analysis is performed in EC-E89-016, which is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Technical Reference(s): TGOP-902-005 step 6 on page 20 Rev. 311 (Attach if not previously provided) OP-902-005 step 6 on page 6. Rev. 22 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE05 obj.7 (As available)

Question Source: Bank # RO13 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC RO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 24 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000056 AK3.02 Importance Rating 4.4 K/A Statement Knowledge of the reasons for the following responses as they apply to Loss of Offsite Power: Actions contained in EOP for loss of offsite power Proposed Question: RO 13 Rev: 1 Given:

A loss of 3B Safety Bus has occurred

CCW Pump A is available and is running

Crew is performing the actions of OP-901-311, Loss of Train B Safety Bus Splitting the A and B CCW headers is performed to prevent ____(1)____. To restore Spent Fuel Pool Cooling, CC-620, CCW to the Spent Fuel Pool, ____(2)_____.

(1) (2)

A. runout of CCW pump A must be opened locally B. runout of CCW pump A can be overridden to the open position at CP-8 C. CCW backflow through the can be overridden to the idle loop open position at CP-8 D. CCW backflow through the must be opened locally idle loop Revision 0 Facility: Waterford 3 Page 25 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Part 1 is correct. CC-620 can be operated manually but OP-901-310 directs the crew to override the valve from CP-8.

B. CORRECT: OP-901-311 step 4 contains the steps to perform if two CCW pumps are not operating. Step 4.2 states Split CCW trains to prevent runout of the operating pump. The note before this step states that Closing CC-200B/563 will also close CC-620. CC-620 can be overridden to lower Spent Fuel Pool Temperature. CC-620 is re-opened by taking the C/S to CONTROL at CP-8.

C. Incorrect. Part 1 is plausible because it could be assumed that with no pump running on one of the CCW trains there could be some backflow from the running train. If this were true, isolating the loops would correct that problem. Part 2 is correct.

D. Incorrect. Part 1 is plausible because it could be assumed that with no pump running on one of the CCW trains there could be some backflow from the running train. If this were true, isolating the loops would correct that problem. CC-620 can be operated manually but OP-901-310 directs the crew to override the valve at CP-8.

Technical Reference(s): OP-901-311 step 4 Rev. 310 (Attach if not previously provided) SD-CC page 37 Rev. 24 (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 X 10 CFR Part 55 Content: 55.41 7, 10 55.43 Comments: Free Review question. FIRST TEN. Change "will's" to should's" in stem.

Procedure OP-901-310 does not appear to prohibit local manual operation of CC-620.

This would make both A and B correct. Resolutions (Changed "will" to "should".

Changed part 2 distractor to state "CC-620 must be opened locally". Makes the distractor incorrect since the procedure directs the crew to override CC-620 from CP-8).

Revision 0 Facility: Waterford 3 Page 26 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000057 AA1.06 Importance Rating 3.5 K/A Statement Ability to operate and monitor the following as they apply to Loss of Vital AC Instrument 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)

A loss of PDP MD occurs SG2 Atmospheric Dump Valve (MS-116B) has failed ______(1)______ and must be operated manually using the ______(2)______.

(1) (2)

A. open handwheel only B. closed handwheel only C. open local air station or handwheel D. closed local air station or handwheel Revision 0 Facility: Waterford 3 Page 27 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect: The ADV fails closed on loss of power or air. OP-901-312 and OP-005-004 have instructions for using the local air station and this would be the preferred method. OP-005-004 also has instructions for local handwheel operation which could be used if the local air station is not working.

B. Incorrect. Part 1 is correct. OP-901-312 and OP-005-004 have instructions for using the local air station and this would be the preferred method. OP-005-004 also has instructions for local handwheel operation which could be used if the local air station is not working.

C. Incorrect. The ADV fails closed on loss of power or air. Part 2 is correct.

D. CORRECT: The ADV fails closed on loss of power or air. OP-901-312 and OP-005-004 have instructions for using the local air station and this would be the preferred method. OP-005-004 also has instructions for local handwheel operation which could be used if the local air station is not working.

Technical Reference(s): OP-901-312 page 52 Rev. 319 (Attach if not previously provided) OP-005-004 Attachment 8.7 Rev. 36 (including version/revision number)

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 None Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 28 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000058 AA2.02 Importance Rating 3.3 K/A Statement Ability to determine and interpret the following as they apply to Loss of DC Power: 125V dc bus voltage, low/critical low, alarm.

Proposed Question: RO 15 Rev: 0 Given:

The following annunciator is received:

o Cabinet N, M-13, EMER FW TURBINE SG2 SHUTOFF VLV TROUBLE/EFAS OVRD The BOP operator will direct the NAO to check breaker condition and DC bus voltage at the ________(1)________ bus to trouble shoot the cause of the alarm.

If the NAO finds the DC breaker in the trip free positon, it can be determined that the breaker has tripped on ___(2)____ .

(1) (2)

A. AB-DC overcurrent B. AB-DC thermal overload C. B-DC thermal overload D. B-DC overcurrent Revision 0 Facility: Waterford 3 Page 29 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: The annunciator provided in the stem is an indication of a problem with MS-401B Main Steam Line 2 to EFWPT Isol. The annunciator response for this annunciator gives Overcurrent as one of the possible causes. The annunciator response also indicates that the breaker will be found in the tripped free condition on a overcurrent and can be reset by placing the breaker to OFF then back to the ON position.

B. Incorrect. Part 1 is correct. Part 2 is plausible because thermal overload is a possible cause from the annunciator response. But, the annunciator response states that the breaker will remain in the closed position following the thermal overload.

C. Incorrect. Part 1 is plausible because the power supply to MS-401B is from the AB-DC bus, but it is plausible that the power supply could be from the B-DC bus due to the train designation of the valve. Part 2 is plausible because thermal overload is a possible cause from the annunciator response. But, the annunciator response states that the breaker will remain in the closed position following the thermal overload.

D. Incorrect. Part 1 is plausible because the power supply to MS-401B is from the AB-DC bus, but it is plausible that the power supply could be from the B-DC bus due to the train designation of the valve. Part 2 is correct.

Technical Reference(s): OP-901-313 page 5, Rev. 306 (Attach if not previously provided) OP-500-012 Att. 4.103 Rev. 37 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-EFW00 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 X 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 30 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000062 G2.2.39 Importance Rating 3.9 K/A Statement Loss of Nuclear Service Water 2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.

Proposed Question: RO 16 Rev: 0 The minimum required water level in the wet cooling tower basins per Technical Specification 3.7.4 is ___(1)___.

The basis for Technical Specification 3.7.4 states that the minimum water level in each WCT basin ensures that cooling water to essential equipment will be maintained for

____(2)____ days.

(1) (2)

A. 92% 7 B. 92% 30 C. 97% 7 D. 97% 30 Revision 0 Facility: Waterford 3 Page 31 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is plausible because 92% is the minimum required level allowed in the Condensate Storage Pool per Tech Spec 3.7.1.3. Part 2 is plausible because there are other action statements within TS 3.7.4 that are 7 day limitations.

B. Incorrect. Part 1 is plausible because 92% is the minimum required level allowed in the Condensate Storage Pool per Tech Spec 3.7.1.3. Part 2 is correct.

C. Incorrect. Part 1 is correct. Part 2 is plausible because there are other action statements within TS 3.7.4 that are 7 day limitations.

D. CORRECT: The minimum required water level in the wet cooling tower basins as required by TS 3.7.4 is 97%. This is RO knowledge because it is a less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Tech Spec. The basis for TS 3.7.4 states that the minimum water level of 97% in the wet cooling tower basins are based on providing a 30 day cooling water supply to essential equipment.

Technical Reference(s): T.S 3.7.4 LCO (Attach if not previously provided) T.S 3.7.4 basis (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OP-CC00 obj. 9 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 32 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000065 AA2.01 Importance Rating 2.9 K/A Statement Ability to determine and interpret the following as they apply to Loss of Instrument Air:

Cause and effect of low-pressure instrument air alarm.

Proposed Question: RO 17 Rev: 0 Given:

Plant is at 100% power

An un-isolable instrument air leak has occurred at SG1 Main Feedwater Isolation Valve (FW-184A)

SG1 FW ISOL VLV ACCU PRESS LO annunciator is locked in on Cabinet M A compete loss of Air Reservoir pressure will cause FW-184A to fail _____(1)_____. Off-normal procedure ____(2)____ provides the guidance on actions to take in response to this event.

(1) (2)

A. as is OP-901-201, Steam Generator Level Control Malfunction B. closed OP-901-201, Steam Generator Level Control Malfunction C. as is OP-901-511, Instrument Air Malfunction D. closed OP-901-511, Instrument Air Malfunction Revision 0 Facility: Waterford 3 Page 33 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Part 1 is correct. OP-901-201, Steam Generator Level Control Malfunction is plausible because failure of this valve to respond properly will affect steam generator level control.

B. Incorrect. Main Feedwater Isolation Valves fail as is on a loss of air. Failing closed is plausible because the MFIVs close on a MSIS. OP-901-201, Steam Generator Level Control Malfunction is plausible because failure of this valve to respond properly will affect steam generator level control.

C. CORRECT: The Main Feedwater Isolation Valves fail as is on a loss of air. The guidance to respond to this event is located in step 13 of OP-901-511, Loss of Instrument Air. The annunciator response procedure OP-500-011 also directs the crew to OP-901-511. This is important for the crew to know where to find this information because this event will require a shutdown of the plant and closure of the MFIV.

D. Incorrect. Main Feedwater Isolation Valves fail as is on a loss of air. Failing closed is plausible because the MFIVs close on a MSIS. Part 2 is correct.

Technical Reference(s): OP-500-011, attachment 4.113 Rev. 38 (Attach if not previously provided) OP-901-511 page 9 revision 17 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 34 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000077 AA2.04 Importance Rating 3.6 K/A Statement Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: VARs outside the capability curve Proposed Question: RO 18 Rev: 1 Given:

Reactor power is 100%

A large load connected to the grid is lost causing a grid disturbance

MVAR load changed from 40 MVAR out to 65 MVAR in The Generator MVAR administrative limits required by OP-010-004, Power Operations, are __(1)__.

To restore MVAR load to 40 MVAR out, the Main Generator Voltage Adjust Regulator Switch is taken to ____(2)____.

(1) (2)

A. still met raise B. still met lower C. no longer met raise D. no longer met lower Revision 0 Facility: Waterford 3 Page 35 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: Losing a large load on the grid caused grid voltage to rise because Reactive Power (VAR) decreases. OP-010-004 limitation 3.2.16 states that the generator MVAR administrative limits are 75 MVAR in and 400 MVAR out. These limits are more restrictive than the limits on the generator capability curve. To change MVAR from leading to lagging the voltage regulator C/S must be taken to raise.

B. Incorrect. Part 1 is correct. To change MVAR from leading to lagging the voltage regulator C/S must be taken to raise.

C. Incorrect. Losing a large load on the grid caused grid voltage to rise because Reactive Power (VAR) decreases. OP-010-004 limitation 3.2.16 states that the generator MVAR administrative limits are 75 MVAR in and 400 MVAR out. These limits are more restrictive than the limits on the generator capability curve. Part 2 is correct.

D. Incorrect. Losing a large load on the grid caused grid voltage to rise because Reactive Power (VAR) decreases. OP-010-004 limitation 3.2.16 states that the generator MVAR administrative limits are 75 MVAR in and 400 MVAR out. These limits are more restrictive than the limits on the generator capability curve. To change MVAR from leading to lagging the voltage regulator C/S must be taken to raise.

Technical Reference(s): OP-010-004 limitation 3.2.16 Rev. 334 (Attach if not previously provided) PDB002 figure 7 Rev. 0 (including version/revision number) OP-010-004 step 9.8.1.9.1 Rev. 335 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 X 10 CFR Part 55 Content: 55.41 5 55.43 Comments: Free Review question. Changed "will" to "should" in stem. Discuss changing MVAR values to be closer to their respective limits. Resolutions: (Changed "will" to "should". Changed MVAR in to 65 MVAR so that it is closer to the limit").

Revision 0 Facility: Waterford 3 Page 36 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000003 AA2.03 Importance Rating 3.6 K/A Statement Ability to determine and interpret the following as they apply to the Dropped Control Rod:

Dropped rod, using in-core/ex-core instrumentation, in-core or loop temperature measurements.

Proposed Question: RO 19 Rev: 0 Given:

Plant power ascension to 100% is in progress

The following conditions are observed:

o Tave has lowered 1.5°F o Core Exit thermocouple indication has lowered by 10-13°F near Loop 2 o CPC B power indication is 63%

o CPC A, C and D power indication is 74%

Which of the following describes the cause of these indications?

A. Xenon oscillation B. Dropped CEA C. Inadvertent boration D. Inadvertent opening of an Atmospheric Dump Valve Revision 0 Facility: Waterford 3 Page 37 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. A xenon oscillation would affect all 4 quadrants of power and temperature.

B. CORRECT: Temp will lower to compensate for - reactivity added by dropped CEA, adding + reactivity. The - reactivity will show up in one core quadrant, and the other 3 will rise to compensate as well.

C. Incorrect. An inadvertent boron injection would affect all 4 quadrants of power and temperature.

D. Incorrect. The inadvertent opening of an Atmospheric Dump valve would result in lower temperature and higher power in all quadrants, not just 3 of 4.

Technical Reference(s): WLP-OPS-TYR05 Rev 5, slides 121-123 (Attach if not previously provided) OP-901-102 page 5 Rev. 305 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-TYR05 Rev 5, EO-14 (As available)

Question Source: Bank # RO20 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 X 10 CFR Part 55 Content: 55.41 1, 2 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 38 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000005 G2.4.6 Importance Rating 3.7 K/A Statement Inoperable/Stuck Control Rod 2.4.6 Knowledge of EOP mitigation strategies.

Proposed Question: RO 20 Rev: 0 Given:

A Reactor trip and Loss of Offsite Power has occurred

Three CEAs are stuck out on the Reactor trip

Emergency boration is in progress using BAM pump A After five minutes, the RAB watch reports a large lube oil leak on EDG A and the CRS directs securing EDG A by pulling the overspeed trip mechanism. Which of the following actions should the crew take as a result of the changing plant conditions?

A. Restore Emergency Boration using BAM Pump B.

B. Restore Emergency Boration using the Gravity Feed valves.

C. Commence a plant cooldown to 400°F using ADVs and EFW.

D. Depressurize the RCS to less than 1400 psia and initiate HPSI flow into one cold leg.

Revision 0 Facility: Waterford 3 Page 39 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. BAM Pump B is powered from the A train of electrical distribution. This pump will not be available because of the loss of offsite power and the loss of EDG A. Plausible because the applicant could assume that BAM Pump B is powered from the B train of electrical distribution.

B. CORRECT: Emergency boration is required because greater than one CEA is not inserted into the core. Gravity feed valves are powered from B train of electrical distribution and are available to perform Emergency Boration.

C. Incorrect. This action is contained in the W3 Station Blackout Procedure (OP-902-005). EDG B is still available and entry into OP-902-005 is not required.

D. Incorrect. This action is performed in the functional recovery procedure (RC-3) if boration is not greater than 40 gpm. The applicant would choose this distractor if it is determined that boration through the charging pumps is not available.

Technical Reference(s): OP-002-005 page 203 Rev. 64 (Attach if not previously provided) OP-901-103 pages 5 Rev. 4 (including version/revision number) OP-902-000 page 5 Rev. 16 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 obj. 10 (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 X 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 40 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000024 AK2.04 Importance Rating 2.6 K/A Statement Knowledge of the interrelations between Emergency Boration and the following: Pumps Proposed Question: RO 21 Rev: 1 Given:

Power is 100%

Charging Pump A is running

VCT Level Transmitter CVC-ILT-0227 fails to 0%

Both ____(1)____ must be declared inoperable due to ___(2)___.

(1) (2)

A. boric acid gravity feed the head of the RWSP valves seating downstream check valve, BAM-115 B. boric acid gravity feed un-isolating safety piping to valves non-safety piping C. boric acid makeup tanks the head of the RWSP seating downstream check valve, BAM-115 D. boric acid makeup tanks un-isolating safety piping to non-safety piping Revision 0 Facility: Waterford 3 Page 41 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: CR-2018-2016 recognized if CVC-507 is opened, BAM-113A(B) boric acid gravity feed valves will not perform their design function because the head of the RWSP would seat downstream check valve BAM-115. The K/A is met because there is a relation to the BAM pumps in the question. The BAM pumps are not declared inoperable because there discharge pressure, when running, will not allow the downstream check valve to seat.

B. Incorrect. Part 1 is correct. Part 2 is plausible because there are instances where RWSP piping must be isolated due to being non-safety (RWSP purification during a SIAS C. Incorrect. The failed level instrument will cause CVC-183 (VCT outlet) to close and CVC-507 (RWSP to Charging) to open. CR-2018-2016 recognized if CVC-507 is opened, BAM-113A(B) boric acid gravity feed valves will not perform their design function because the head of the RWSP would seat downstream check valve BAM-115. The boric acid makeup pumps can overcome check valve, BAM-115. Therefore the BAMTs are not inoperable when CVC-507 is opened. Part 2 is correct.

D. Incorrect. CR-2018-2016 recognized if CVC-507 is opened, BAM-113A(B) boric acid gravity feed valves will not be able to perform their design function. This is because the head of the RWSP would seat downstream check valve BAM-115. The boric acid makeup pumps can overcome check valve, BAM-115. Therefore the BAMTs are not inoperable when CVC-507 is opened. Part 2 is plausible because there are instances where RWSP piping must be isolated due to being non-safety (RWSP purification during a SIAS).

Technical Reference(s): OP-901-113 page 6 Revision 305 (Attach if not previously provided) CR-WF3-2018-2016 (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 X 10 CFR Part 55 Content: 55.41 7,10 55.43 Comments: Free Review question. Comment: Ensure the question is RO knowledge.

Resolution: The objective related to the question is an RO objective and the guidance is a note in OP-901-113, VCT Level Control Malfunction. Can also determine the correct answer by knowing CVC system dynamics.

Revision 0 Facility: Waterford 3 Page 42 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000036 G2.2.44 Importance Rating 4.2 K/A Statement Fuel Handling Incidents 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

Proposed Question: RO 22 Rev: 0 Given:

A Fuel shuffle in the Spent Fuel Pool is in progress

Crew received a report from the Spent Fuel Handling Machine of a damaged fuel assembly and has implemented OP-901-405, Fuel Handling Incident The crew will verify a Fuel Handling Accident (FHA) signal occurs when the ___(1)___

radiation monitor(s) reaches the Hi-Hi alarm setpoint. To monitor the radioactive release, the crew will be required to start ___(2)___.

(1) (2)

A. Fuel Handling Building PIG a FHB Normal Supply and Exhaust Fan B. Fuel Handling Building PIG the FHB WRGM sample pump C. Fuel Handling Building a FHB Normal Supply and Exhaust Fan Isolation Area D. Fuel Handling Building the FHB WRGM sample pump Isolation Area Revision 0 Facility: Waterford 3 Page 43 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is plausible because FHB Normal Exhaust Fan is normally running and is being monitored for radioactive release by the FHB PIG radiation monitors. However, upon a FHA signal, the FHB Normal Exhaust Fan will secure. Part 2 is plausible because OP-901-405 section E2 will direct the crew to restart a FHB Normal Supply and Exhaust fan following the FHA signal. The reason is to provide cooling to the Fuel Pool Cooling pumps and to reduce leakage from contaminated areas to non-contaminated areas.

B. Incorrect. Part 1 is plausible because FHB Normal Exhaust Fan is normally running and is being monitored for radioactive release by the FHB PIG radiation monitors. However, upon a FHA signal, the FHB Normal Exhaust Fan will secure. Part 2 is correct.

C. Incorrect. Part 1 is correct. Part 2 is plausible because OP-901-405 section E2 will direct the crew to restart a FHB Normal Supply and Exhaust fan following the FHA signal. The reason is to provide cooling to the Fuel Pool Cooling pumps and to reduce leakage from contaminated areas to non-contaminated areas.

D. CORRECT: The Fuel Handling Building Ventilation System will receive a Fuel Handling Accident (FHA) Signal when the FHB area radiation monitors reach their Hi-Hi alarm setpoint.

The interpreting portion of the K/A is met because the applicant is determining which rad monitor to look at to know when the Fuel Handling Accident signal should occur. To monitor the radioactive release following the FHS signal, the crew will be required to start the FHB WRGM sample pump manually from the control room.

Technical Reference(s): OP-901-405 section E2 Rev. 8 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO40 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 11,13 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 44 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000037 AK3.07 Importance Rating 4.2 K/A Statement Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Leak: Actions contained in EOP for S/G tube leak Proposed Question: RO 23 Rev: 0 Given:

A Steam Generator Tube Leak is in progress

Crew is performing actions in accordance with OP-901-202, Steam Generator Tube Leakage or High Activity

The condenser is not available The crew will commence a normal plant cooldown to obtain a Hot leg temperature of less than or equal to 520°F using _____(1)_____. The reason for the cooldown to 520°F is to _____(2)_____ release.

(1) (2)

A. the atmospheric dump valve on the ensure RCP operating curves are S/G with the lowest indicated activity met during the subsequent RCS depressurization B. the atmospheric dump valve on the prevent opening the atmospheric S/G with the lowest indicated activity dump valve or Main Steam safety valves on the affected SG C. both atmospheric dump valves ensure RCP operating curves are met during the subsequent RCS depressurization D. both atmospheric dump valves prevent opening the atmospheric dump valve or Main Steam safety valves on the affected SG Revision 0 Facility: Waterford 3 Page 45 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Part 1 is correct. Part 2 is plausible because there is a subsequent depressurization step in OP-901-202 to minimize RCS leakage through the SG tubes. Also, it is desired that the crew maintain RCPs running, therefore, RCP operating curves must be met.

B. CORRECT: OP-901-202 step 20.5 directs the crew to reduce Th to < 520°F using the atmospheric dump valve on the S/G with the lowest activity. This is performed if the condenser is unavailable. Per the Tech Guide for SG Tube Rupture Recovery Procedure, Thot is reduced to < 520°F to prevent opening the atmospheric dump valve or lifting the main steam safety valves on the affected SG after isolation. For K/A match. Waterford 3 EOPs due not have guidance for a SG Tube Leak, W3 has an off-normal for this event. The K/A is met because the guidance for the reason for the cooldown can only be found in the Tech Guide for the EOP which has been incorporated into the question.

C. Incorrect. OP-901-202 step 20.5 directs the crew to reduce Th to < 520°F using the atmospheric dump valve on the S/G with the lowest activity. This is performed if the condenser is unavailable. OP-902-007, S/G Tube rupture directs the crew to cooldown to <

520°F using both ADVs in manual. (that is not the case for a tube leak). Part 2 is plausible because there is a subsequent depressurization step in OP-901-202 to minimize RCS leakage through the SG tubes. Also, it is desired that the crew maintain RCPs running, therefore, RCP operating curves must be met.

D. Incorrect. OP-901-202 step 20.5 directs the crew to reduce Th to < 520°F using the atmospheric dump valve on the S/G with the lowest activity. This is performed if the condenser is unavailable. OP-902-007, S/G Tube rupture directs the crew to cooldown to <

520°F using both ADVs in manual. (that is not the case for a tube leak). Part 2 is correct.

Technical Reference(s): OP-901-202 page 20 Rev. 15 (Attach if not previously provided) TG-OP-902-007 step 11 on page 32 Rev. 309 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 46 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000060 AK1.04 Importance Rating 2.5 K/A Statement Knowledge of the operational implications of the following as they apply to an Accidental Gaseous Radwaste Release: Calculation of offsite doses due to a release from the power plant.

Proposed Question: RO 24 Rev: 0 Given:

An accidental Gaseous Release is occurring due to a ruptured pipe while discharging the Gas Decay Tanks

Crew is determining protective action requirements in accordance with EP-002-052, Protective Action Guidelines

The duration of the release is not known The default duration used when calculating dose will be ____(1)_____ hour(s).

When determining protective action requirements for a General Emergency, EP-002-052 states the preferred action is to evacuate immediately two miles _____(2)_______.

(1) (2)

A. one downwind B. one in all directions C. two in all directions D. two downwind Revision 0 Facility: Waterford 3 Page 47 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. One hour is plausible because dose is usually given per hour (mr/hour).

But, if the release duration is unknown, the crew will be required to double the dose because the default duration is two hours when making PAR recommendations. Part 2 is plausible because the guidance for 2-5 miles is to evacuate these sectors that are downwind.

B. Incorrect. One hour is plausible because dose is usually given per hour (mr/hour).

But, if the release duration is unknown, the crew will be required to double the dose because the default duration is two hours when making PAR recommendations. Part 2 is correct.

C. CORRECT: EP-002-050 step 5.34 states if the duration of the release is unknown then default duration when calculating the dose is two hours. This is important because doubling the dose rate (mr/hr) could make the difference on whether to shelter or evacuate the general public. EP-002-052 step 5.1.6 states that while determining protective action requirements for a General Emergency, the preferred action is to evacuate immediately 2 miles in all directions D. Incorrect. Part 1 is correct. Part 2 is plausible because the guidance for 2-5 miles is to evacuate these sectors that are downwind.

Technical Reference(s): EP-002-050 step 5.3.4 Rev. 308 (Attach if not previously provided) WLP-OPS-EP02 slide 73 (including version/revision number) EP-002-052 step 5.1.6 Rev. 26 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-EP02 obj. 22 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 48 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 00068 AA1.12 Importance Rating 4.4 K/A Statement AA1 Ability to operate and monitor the following as they apply to Control Room Evacuation: Auxiliary Shutdown panel controls and indicators Proposed Question: RO 25 Rev: 0 Given:

A Control Room Evacuation has occurred

Controls have been established at LCP-43 and the crew has commenced a controlled cooldown in accordance with OP-901-502, Control Room Evacuation The crew is alerted to reset the RPS/ESFAS PZR Press Low setpoint by a

_____(1)_____. To reset the setpoints, the reset pushbutton is depressed at

_____(2)_____.

(1) (2)

A. pretrip light and annunciator LCP-43 B. pretrip light only Local ESFAS cabinets C. pretrip light and annunciator Local ESFAS cabinets D. pretrip light only LCP-43 Revision 0 Facility: Waterford 3 Page 49 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is plausible because the operator will know to reset the RPS/ESFAS PZR Press Low setpoint in the control room by both an annunciator and a pretrip light. In fact, in the control room the operator will mostly rely on the annunciator to alert them of the opportunity to reset.

B. Incorrect. Part 1 is correct. Part 2 is plausible because there is a reset pushbutton for Pzr pressure Lo at the local ESFAS cabinet, but it is to reset the actuation signal if required.

C. Incorrect. Part 1 is plausible because the operator will know to reset the RPS/ESFAS PZR Press Low setpoint in the control room by both an annunciator and a pretrip light. In fact, in the control room the operator will mostly rely on the annunciator to alert them of the opportunity to reset. Part 2 is plausible because there is a reset pushbutton for Pzr pressure Lo at the local ESFAS cabinet, but it is to reset the actuation signal if required.

D. CORRECT: There is no annunciator at LCP-43 to alert the operator that the RPS/ESFAS PZR Press Low setpoint is capable of being reset (unlike the control room). This is important because the RO has to pay close attention to only a pretrip light. If it is missed, the crew will allow a SIAS to actuate which will complicate the event. The trip reset button is located at LCP-43.

Technical Reference(s): OP-901-502 page 30 Rev. 35 (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. 13 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 50 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # CE/A16 AK2.1 Importance Rating 3.2 K/A Statement Knowledge of the interrelations between the (Excess RCS Leakage) and the following:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Proposed Question: RO 26 Rev: 0 Given:

Plant is at 100% power

CCW Surge Tank level is rising slowly

VCT level is slowly lowering

The following alarms are received:

o CCW A ACTIVITY HIGH o CCW B ACTIVITY HIGH No other alarms are received.

The location of the RCS leak is in the __(1)__. As level rises in the CCW Surge Tank, the overflow will be directed to the __(2)__.

(1) (2)

A. 1B RCP Seal Cooler the in-service waste tank B. Letdown Heat the in-service waste tank Exchanger C. Letdown Heat Industrial waste sump Exchanger D. 1B RCP Seal Cooler Industrial waste sump Revision 0 Facility: Waterford 3 Page 51 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. If the leak is in the 1B RCP seal cooler, the RX COOLANT PUMPS CCW ACTIVITY HI annunciator would be in. The initiating device for this alarm is the CCW AB Radiation Monitor (PRM-IRE-5700) whose sample is taken directly downstream of the RCP seal coolers. There would also be other annunciators such as RCP CCW SEAL COOLER Pressure HI or RCP 1B SEAL CLR CC-VALVES CLOSED alarmed. Part 2 is correct.

B. CORRECT: The Letdown Heat Exchanger would be the choice as the crew eliminates the seal cooler by verifying annunciators that should be in are not alarmed. The overflow of the CCW surge tank is routed to the in-service waste tank.

C. Incorrect. Part 1 is correct. Part 2 is plausible because most equipment outside of the RCA areas are routed to the Industrial Waste Sump. The CCW Surge Tank is located outside the RCA.

D. Incorrect. If the leak was in the 1B RCP seal cooler, the RX COOLANT PUMPS CCW ACTIVITY HI annunciator would be in. The initiating device for this alarm is the CCW AB Radiation Monitor (PRM-IRE-5700) whose sample is taken directly downstream of the RCP seal coolers. There would also be other annunciators such as RCP CCW SEAL COOLER Pressure HI or RCP 1B SEAL CLR CC-VALVES CLOSED alarmed. Part 2 is plausible because most equipment outside of the RCA areas are routed to the Industrial Waste Sump.

The CCW Surge Tank is located outside the RCA OP-500-008 Att.4.90 Rev. 26 OP-500-011 Att. 4.32 Technical Reference(s): Rev 27 (Attach if not previously provided) OP-901-411 page 3 Rev. 2 (including version/revision number) SD-CC page 43 and Fig 12 Rev. 25 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO40 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 X 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 52 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # CE/E09 EK3.1 Importance Rating 3.5 K/A Statement Knowledge of the reasons for the following responses as they apply to Functional Recovery: Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

Proposed Question: RO 27 Rev: 0 Given:

Crew is performing actions in OP-902-002, Loss of Coolant Accident Recovery Procedure when a steam leak occurred causing an excessive cooldown

Crew is transitioning to OP-902-008, Functional Recovery Procedure

The following conditions are observed:

o RCS pressure is 1500 psia o ATC reports that reactor power is dropping o Only Charging Pump A is running due to Charging Pump B tripping on overcurrent During the uncontrolled cooldown, Emergency Boration is _______?

A. required and is aligned because adequate HPSI flow exists B. required and is aligned because adequate Charging flow exists C. not required to be aligned because all CEAs are fully inserted D. not required to be aligned because Reactor power is dropping Revision 0 Facility: Waterford 3 Page 53 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Part 1 is correct. The second part of the distractor is plausible because if adequate HPSI flow exists, it would meet the requirements of Emergency Boration. But, RCS pressure is above HPSI shutoff head, therefore, the requirement of 40 gpm emergency boration flow cannot be met by HPSI.

B. CORRECT: Even though the Reactivity Control Safety Function Criteria in the Resource Assessment Tree is met, Emergency Boration is required anytime there is an excessive cooldown per OP-901-103, Emergency Boration. To meet the emergency boration flow requirement of 40 gpm as required by OP-901-103, Emergency Boration, only one charging pump is required to be running even though the crew would expect two to be running anytime there is a SIAS.

C. Incorrect. Even though the Reactivity Control Safety Function Criteria in the Resource Assessment Tree is met, Emergency Boration is required anytime there is an excessive cooldown per OP-901-103, Emergency Boration. The second part of the distractor is plausible because all CEA fully inserted is part of the requirement to meet reactivity control. But, emergency boration is still required due to the uncontrolled cooldown.

D. Incorrect. Even though the Reactivity Control Safety Function Criteria in the Resource Assessment Tree is met, Emergency Boration is required anytime there is an excessive cooldown per OP-901-103, Emergency Boration. The second part of the distractor is plausible because Reactor Power dropping is part of condition 2 for reactivity control. But, emergency boration is still required due to the uncontrolled cooldown per OP-901-103 Emergency Boration..

Technical Reference(s): OP-902-009 Attachment 2-E Rev. 319 (Attach if not previously provided) OP-902-008 page 14 Rev. 30 (including version/revision number) OP-901-103 step 5 on page 3 Rev. 4 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO10 obj. 3 (As available)

WLP-OPS-PPE08 obj. 2 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 X 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 54 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 003 K1.01 Importance Rating 2.6 K/A Statement Knowledge of the physical connections and/or cause-effect relationships between the Reactor Coolant Pump System and the following systems: RCP lube oil.

Proposed Question: RO 28 Rev: 0 Given:

The reactor was at 100% power RCP 1A trips on overcurrent

__(1)__ RCP 1A Lift Oil Pump(s) started when RCP 1A __(2)__.

(1) (2)

A. One load breaker opened B. Both load breaker opened C. One speed lowered to 600 RPM D. Both speed lowered to 600 RPM Revision 0 Facility: Waterford 3 Page 55 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Both lift oil pumps will start when the RCP breaker opens. Candidate must know the normal alignment of the lift oil pump control switches to eliminate this selection. Part 2 is correct.

B. CORRECT: At 100% power the lift oil pump control switches will be in Auto. The RCP breaker opening causes both lift oil pumps to start immediately. For K/A match, the RCP lift oil pumps is the source of high pressure lube oil during RCP starts and stops. Thrust bearing oil pumping action is the source of main lube oil to the RCPs during normal operation.

C. Incorrect. Wrong number of pumps. The initiating signal is incorrect. Some W3 oil pumps start and stop on shaft RPM. Oil pumps for the main turbine start and stop at 600 rpm.

D. Incorrect. Correct number of pumps start. The initiating signal is incorrect. Some W3 oil pumps start and stop on shaft RPM. Oil pumps for the main turbine start and stop at 600 rpm.

Technical Reference(s): WLP-OPS-RCP00 slide 90 and 102 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-RCP00 obj. 5 (As available)

Question Source: Bank # 29 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2015 NRC RO Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3, 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 56 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 004 K2.06 Importance Rating 2.6 K/A Statement Knowledge of bus power supplies to the following: Control instrumentation.

Proposed Question: RO 29 Rev: 0 A loss of power to the Reactor Regulating System cabinets and Feedwater Control System indication at CP-1 would indicate a loss of _________.

A. PDP 90A B. PDP 91B C. AB-DC D. SUPS AB Revision 0 Facility: Waterford 3 Page 57 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. The effects of a loss of PDP 90A are indicated in step 8 of OP-901-312.

PDP 90A powers various indications in the control room but do not power the Reactor Reg cabinets or FWCS indication at CP-1.

B. Incorrect. The effects of a loss of PDP 91B are indicated in step 9 of OP-901-312.

PDP 91B powers various indications in the control room but do not power the Reactor Reg cabinets or FWCS indication at CP-1 C. Incorrect. OP-901-313 attachment 5 indicates AB-DC bus loads. AB-DC powers various annunciators and indications in the control room but do not power the Reactor Reg cabinets or FWCS indication at CP-1.

D. CORRECT: OP-901-312 page 25 indicates that a loss of SUPS AB will cause a loss of CP-12A and CP-12B (Reactor Regulating Cabinets) and will also cause a loss of Feedwater control indications at CP-1. Loss of the reactor regulating cabinets would affect Pressurizer level control setpoint which would then affect the Charging and Letdown system.

Technical Reference(s): OP-901-312 page 25 Revision 319 (Attach if not previously provided)

(including version/revision number)

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 None Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 58 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 005 K3.01 Importance Rating 3.9 K/A Statement Knowledge of the effect that a loss or malfunction of the Residual Heat Removal System will have on the following: RCS.

Proposed Question: RO 30 Rev: 0 Given:

The plant is in Mode 6

The reactor has been shut down for 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months

Refueling Cavity level is 44 feet

Shutdown Cooling Train A is in service and SDC Train A flow is 2100 gpm

Shutdown Cooling Train B is also in service and SDC Train B flow is 2000 gpm The minimum Shutdown Cooling flow requirements required by Tech Spec 3.9.8.1 is

____(1)____. Per TS 3.9.8.1 basis, Shutdown Cooling flow requirements based on time after the reactor is shutdown ensures sufficient coolant circulation is maintained and

______(2)______.

(1) (2)

A. not met To ensure that the iodine released in the event of a rupture of an irradiated fuel assembly is reduced by a factor of at least 200 B. not met to prevent boron stratification in the core C. met to prevent boron stratification in the core D. met To ensure that the iodine released in the event of a rupture of an irradiated fuel assembly is reduced by a factor of at least 200 Revision 0 Facility: Waterford 3 Page 59 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Part 1 is plausible if the applicant does not determine that the combined flows of both trains of Shutdown Cooling can be used to meet the minimum requirements of TS 3.9.8.1. The required flow for 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months after reactor shutdown is 4000 gpm. Part 2 is plausible because reducing iodine levels by a factor of 200 is the basis for the minimum level in the refueling cavity.

B. Incorrect. Part 1 is plausible if the applicant does not determine that the combined flows of both trains of Shutdown Cooling can be used to meet the minimum requirements of TS 3.9.8.1. The required flow for 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months after reactor shutdown is 4000 gpm. Part 2 is correct.

C. CORRECT: Per TS 3.9.8.1, while in Mode 6 and reactor cavity level greater than 43 feet, at least one SDC train is required to be operable and SDC flow is required to be greater than or equal to 4000 gpm. OP-001-003 precaution 3.1.6 states that the flow from either the operating SDC train or the combined flow of both operating SDC trains may be used. The applicant must determine that the combined flow is greater than 4000 gpm. TS 3.9.8.1 basis and OP-001-003 precaution 3.1.6 specifies the prevention of boron stratification as a reason for the minimum SDC flow. This question is RO knowledge because the flow requirements are located in Tech Spec Logs which the RO logs the readings. The K/A is met because effect of not meeting flow requirements is possible boron stratification in the core. A loss or malfunction would be the only reason we would go below TS flow requirements.

D. Incorrect. Part 1 is correct. Part 2 is plausible because reducing iodine levels by a factor of 200 is the basis for the minimum level in the refueling cavity.

Technical Reference(s): OP-001-003 precaution 3.1.6 Rev. 321 (Attach if not previously provided) TS 3.9.8.1 and 3.9.8.1 basis (including version/revision number) TS 3.9.10 basis Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SDC00 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 X 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 60 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 005 K6.03 Importance Rating 2.5 K/A Statement Knowledge of the effect of a loss or malfunction on the following will have on the RHRS:

RHR Heat Exchanger.

Proposed Question: RO 31 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-415 A, 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 at SI-129A causes the valve to fail open.

Before any manual actions can be taken, Shutdown Cooling Train A flow will (1) and RCS temperature will (2) .

(1) (2)

A. stay the same drop B. stay the same rise C. rise drop D. rise rise Revision 0 Facility: Waterford 3 Page 61 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is plausible because as SI-129A fails OPEN, the applicant could determine that SI-415 will respond to maintain the required flow but it does not. Part 2 is plausible if the applicant does not understand the SDC HX flow path and determines that SI-415 will open to restore flow and allow more SDC to the SDC HX.

B. Incorrect. . Part 1 is plausible because as SI-129A fails OPEN, the applicant could determine that SI-415 will respond to maintain the required flow but it does not. Part 2 is correct.

C. Incorrect. Part 1 is correct. Part 2 is plausible if the applicant does not understand the SDC HX flow path and determines that SI-415 will open to restore flow and allow more SDC to the SDC HX.

D. CORRECT: 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.

Technical Reference(s): OP-901-511 step 4 on page 6 Rev. 17 (Attach if not previously provided) SD-SDC Pages 5 and 6 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SDC00 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 X 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 62 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 006 K4.17 Importance Rating 3.8 K/A Statement Knowledge of Emergency Core Cooling System design feature(s) and/or interlock(s),

which provide for the following: Safety Injection valve interlocks.

Proposed Question: RO 32 Rev: 0 The ESF PUMPS SUCTION SI SUMP, SI-602A(B), receive a ____(1)____.

To override SI-602 closed on an RAS signal, the key switch located on ___(2)___ must be taken to OVERRIDE to allow closure of SI-602A(B) using the control switch on CP-8.

(1) (2)

A. SIAS to close and a RAS Aux Panel 1(2) in the relay room signal to open B. SIAS to close and a RAS CP-8 signal to open C. RAS signal to open only Aux Panel 1(2) in the relay room D. RAS signal to open only CP-8 Revision 0 Facility: Waterford 3 Page 63 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: ESF PUMPS SUCTION SI SUMP, SI-602A(B), receive a signal to close on a SIAS and a signal to open on a RAS. To override SI-602 closed on an RAS signal, the key switch located on the Aux Panels located in the relay room are taken to OVERRIDE to allow closure of SI-602A(B) using the control switch on CP-8.

B. Incorrect. Part 1 is correct. Part 2 is plausible because there are ECCS valves on CP-8 that have key switches and can have override positions (i.e. SIT outlet isolation Valves).

C. Incorrect. Part 1 is plausible because these valves are normally shut and therefore will not cycle during SIAS unless it was open. The RWSP outlet (SI-106A(B)) do not get a signal to close on an RAS so it could be assumed that S-602A(B) does not get a signal to close on a SIAS. Part 2 is correct.

D. Incorrect. Part 1 is plausible because these valves are normally shut and therefore will not cycle during SIAS unless it was open. The RWSP outlet (SI-106A(B)) do not get a signal to close on an RAS so it could be assumed that SI-602A(B) does not get a signal to close on a SIAS. Part 2 is plausible because there are ECCS valves on CP-8 that have key switches and can have override positions (i.e. SIT outlet isolation Valves).

Technical Reference(s): SD-SI page 17 Rev. 18 (Attach if not previously provided) OP-902-009 Attachment 29A(B) Rev. 319 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SI00 obj. 7 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 64 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 007 K5.02 Importance Rating 3.1 K/A Statement Knowledge of the operational implications of the following concepts as they apply to PRTS: Method of forming a steam bubble in the PZR.

Proposed Question: RO 33 Rev: 0 Given:

Crew has entered OP-902-008, Safety Functional Recovery Procedure

Pressurizer Level is 100%

QSPDS Reactor Vessel Level 4 is voided To restore a Pressurizer bubble, crew should vent the ____(1)____ to the ____(2)____

Tank.

(1) (2)

A. Pressurizer Quench B. Pressurizer Reactor Drain C. Reactor Vessel Head Quench D. Reactor Vessel Head Reactor Drain Revision 0 Facility: Waterford 3 Page 65 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Stem provides indication that the bubble has shifted from the Pressurizer to the Head. In some cases, the Pressurizer may need venting, but not when it is showing100% full.

B. Incorrect. See A above. Reactor Drain Tank is plausible for Part 2 since it receives several inputs from the RCS. But the Head is not vented to the RDT.

C. CORRECT: Stem provides indication that the bubble has shifted from the Pressurizer to the Head. Applicant must understand that Reactor Vessel Head level is below that which is required. App. 11, Void Elimination, of OP-902-009, Standard Appendices, provides direction to vent Reactor Vessel Head to the Quench Tank.

D. Incorrect. Reactor Drain Tank is plausible for Part 2 since it receives several inputs from the RCS. But the Head is not vented to the RDT.

Technical Reference(s): OP-902-008 page 94 Rev. 30 (Attach if not previously provided) OP-902-009 page 96 Rev. 319 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE08, EO-4 (As available)

Question Source: Bank # RO34 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 X 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 66 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 008 K4.02 Importance Rating 2.9 K/A Statement Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following:

Operation of the surge tank, including the associated valves and controls.

Proposed Question: RO 34 Rev: 0 Given:

CCW Surge Tank Level Switch CC-ILS-7013B failed low CCW Makeup Pump B Running/Power Lost annunciator is in at CP-8 The BOP reports that CCW A and B surge tank levels are 82% and steady Based on this level switch failure, CCW Makeup Pump B ____________.

A. is de-energized B. will start and run continuously C. will start and auto secure three minutes later D. will not start and requires a manual start from CP-8, if desired Revision 0 Facility: Waterford 3 Page 67 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. The stem indicates that the CCW Makeup Pump B Running/Power Lost annunciator is locked in. Applicant could determine that power is removed to the pump so that it does not run continuously.

B. Incorrect. This answer is plausible because the level switch has failed low and started the makeup pump. Since it is failed low, the pump would run continuously if it does not have the auto stop feature.

C. CORRECT: OP-901-510 Attachment 1 states: For CC-ILS-7013B failing low, CCW Makeup Pump B starts, if in Auto, and runs for 3 minutes. Further operation will require manually starting and stopping the pump.

D. Incorrect. This answer is plausible because there are six level switches for the CCW Surge Tank. Some bring in annunciators without starting equipment. The applicant could determine that the annunciator comes off the level switch but not the start of the CCW Makeup Pump.

Technical Reference(s): OP-901-510 Attachment 1 Rev. 304 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 68 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 010 A1.06 Importance Rating 3.1 K/A Statement Ability to predict and monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: RCS heatup and cooldown effect on pressure.

Proposed Question: RO 35 Rev: 0 Given:

A plant startup is in progress

The Pressurizer is solid and all available heaters are energized in preparation for drawing a bubble in the Pressurizer in accordance with OP-001-001, Reactor Coolant System Fill and Vent During the evolution, the ATC operator maintains RCS pressure by throttling

____(1)____ the Backpressure Regulator Valves, CVC-123A(B).

OP-001-001, Reactor Coolant System Fill and Vent, states that a bubble has been formed when ___(2)___.

(1) (2)

A. closed Pressurizer water temperature reaches saturation temperature for RCS pressure B. closed Pressurizer pressure no longer drops while pressurizer level is being lowered C. open Pressurizer pressure no longer drops while pressurizer level is being lowered D. open Pressurizer water temperature reaches saturation temperature for RCS pressure Revision 0 Facility: Waterford 3 Page 69 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. The applicant will predict that pressurizer temperature will be rising due to heaters energized and no bubble in the pressurizer. The rise in pressurizer temperature will cause a rise in pressurizer pressure which will require the crew to open the backpressure regulating valves to remove water mass from RCS and restore RCS pressure. Part 2 is plausible because the crew is directed to raise pressurizer temperature to the saturation temperature for the RCS pressure. But OP-001-001 concludes an bubble is drawn when Pressurizer pressure no longer drops while pressurizer level is being lowered.

B. Incorrect. The applicant will predict that pressurizer temperature will be rising due to heaters energized and no bubble in the pressurizer. The rise in pressurizer temperature will cause a rise in pressurizer pressure which will require the crew to open the backpressure regulating valves to remove water mass from RCS and restore RCS pressure. Part 2 is correct.

C. CORRECT: The applicant will predict that pressurizer temperature will be rising due to heaters energized and no bubble in the pressurizer. The rise in pressurizer temperature will cause a rise in pressurizer pressure which will require the crew to open the backpressure regulating valves to remove water mass from RCS and restore RCS pressure. OP-001-001 includes a note in section 6.6, Drawing a Pressurizer Bubble, which states that a bubble is drawn when Pressurizer pressure no longer drops while pressurizer level is being lowered.

D. Incorrect. Part 1 is correct. Part 2 is plausible because the crew is directed to raise pressurizer temperature to the saturation temperature for the RCS pressure. But OP-001-001 concludes a bubble is drawn when Pressurizer pressure no longer drops while pressurizer level is being lowered.

Technical Reference(s): OP-001-001 section 6.6 Rev. 40 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PLC00 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 X 10 CFR Part 55 Content: 55.41 5,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 70 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 012 A2.01 Importance Rating 3.1 K/A Statement Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulty bistable operation.

Proposed Question: RO 36 Rev: 0 Given:

The plant is in Mode 1

Channel A Narrow Range Pressure transmitter (RC-IPI-0101A) has failed high

Appropriate bistable(s) have been bypassed on Channel A The failed pressure instrument affects the RPS ___(1)___ pressurizer pressure trip.

If another Narrow Range Pressure Instrument fails high on a different channel, the associated bistable(s) is/are placed in the ___(2)___ condition in accordance with OP-009-007, Plant Protection System.

(1) (2) tripped A. low low bypassed B.

bypassed C. high tripped D. high Revision 0 Facility: Waterford 3 Page 71 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. The Pressurizer pressure Narrow range instrument is the input to the RPS Pressurizer pressure Hi trip. The Pressurizer pressure Wide range instrument is the input to the RPS Pressurizer pressure Lo trip. Part 2 is correct.

B. Incorrect. The Pressurizer pressure Narrow range instrument is the input to the RPS Pressurizer pressure Hi trip. The Pressurizer pressure Wide range instrument is the input to the RPS Pressurizer pressure Lo trip. Another failed Narrow range instrument in another channel would require the crew to place its associated bistable to the tripped condition in accordance with OP-009-007. If the second channel was attempted to be put in bypass, both channels would come out of bypass and the reactor would trip.

C. Incorrect. Part 1 is correct. Another failed Narrow range instrument in another channel would require the crew to place its associated bistable to the tripped condition in accordance with OP-009-007. If the second channel was attempted to be put in bypass, both channels would come out of bypass and the reactor would trip D. CORRECT: The Pressurizer pressure Narrow range instrument is an input to the RPS Pressurizer pressure Hi trip. Another failed Narrow range instrument in another channel would require the crew to place its associated bistable to the tripped condition in accordance with OP-009-007. If the second channel was attempted to be put in bypass, both channels would come out of bypass and the reactor would trip.

OP-009-007 precaution 3.1.2 and page 56 Rev.

Technical Reference(s): 20 (Attach if not previously provided) SD-PPS page 27 Rev. 19 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPS00 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 X 10 CFR Part 55 Content: 55.41 7,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 72 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 012 K4.02 Importance Rating 3.9 K/A Statement Knowledge of Reactor Protection System design feature(s) and/or interlock(s) which provide for the following: Automatic reactor trip when RPS setpoints are exceeded for each RPS function; basis for each.

Proposed Question: RO 37 Rev: 0 Given:

Plant is operating at 100% with NOT and NOP Performance of OP-903-107, Plant Protection System Channel A Functional Test, is to be performed The NPO reports that he inadvertently depressed the LOW PZR PRESS Setpoint Reset pushbutton before the surveillance was started.

Which of the following pressures (PSIA) indicates the approximate value at which Channel A would generate a trip on the low Pressurizer pressure trip bistable?

A. 1850 B. 1684 C. 1484 D. 1284 Revision 0 Facility: Waterford 3 Page 73 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. The manual RESET pushbutton will only lower the existing setpoint of a maximum of 400 PSIA below existing RCS pressure. The setpoint has a ceiling of 1684 PSIA. This number would be plausible if the candidate believes that an aux trip on low pressurizer pressure would trip the bistable for low pressurizer pressure. The aux trip would trip the LPD and DNBR bistable.

B. CORRECT: The manual RESET pushbutton will only lower the existing setpoint of a maximum of 400 PSIA below existing RCS pressure. The setpoint has a ceiling of 1684 PSIA. This information is provided in the basis for TS 2.2.1 specifically for the Pressurizer Pressure-Low Trip.

C. Incorrect: The manual RESET pushbutton will only lower the existing setpoint of a maximum of 400 PSIA below existing RCS pressure. The setpoint has a ceiling of 1684 PSIA. This number is 200 psia below existing setpoint and would be plausible if the candidate believes that it works like the Steam Pressure Lo setpoint which is 200 psia and uses the setpoint instead of process pressure to determine the new setpoint.

D. Incorrect. The manual RESET pushbutton will only lower the existing setpoint of a maximum of 400 PSIA below existing RCS pressure. The setpoint has a ceiling of 1684 PSIA. This number is 400 psia below given setpoint and is plausible if the candidate uses the setpoint vs. process pressure to determine the new setpoint Technical Reference(s): SD-PPS pg. 33 Rev. 19 (Attach if not previously provided) TS Basis page B2-3 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPS00 obj. 3 (As available)

Question Source: Bank # RO11 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2010 NRC RO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 74 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 013 A3.01 Importance Rating 3.7 K/A Statement Ability to monitor automatic operation of the ESFAS, including: Input channels and logic.

Proposed Question: RO 38 Rev: 0 Given:

Plant has experienced an Excess Steam Demand event

Following the Main Steam Isolation Signal (MSIS), indications are:

Steam Generator 1 pressure is 650 PSIA Steam Generator 2 pressure is 500 PSIA Steam Generator 1 level is 20% NR and lowering Steam Generator 2 level is 8% NR and lowering Currently, ________ is/are initiated?

A. only EFAS-1 B. only EFAS-2 C. both EFAS-1 and EFAS-2 D. neither EFAS-1 nor EFAS-2 Revision 0 Facility: Waterford 3 Page 75 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: Only EFAS 1 is initiated because SG #1 pressure is 123 psia greater than SG #2 pressure and SG #1 level is less than 27.4% NR. The logic for EFAS is level less than 27.4% NR and SG pressure greater than 666 psia or SG pressure 123 psia greater than the other SG.

B. Incorrect. Only EFAS 2 is plausible because it has the lowest level of the two steam generators. However EFAS #2 does not meet the SG pressure requirements.

C. Incorrect. Both EFAS 1 and EFAS 2 initiated is plausible because both steam generators meet the level requirement of less than 27.4% NR. Although, only SG #1 meets the pressure requirement (123 psid above SG #2).

D. Incorrect. Neither EFAS 1 nor EFAS 2 initiated is plausible because both S/G #1 and S/G #2 pressures do not meet the 666 PSIA requirement but S/G #1 pressure is 123 psid greater than S/G #1 pressure which does meet the EFAS 1 requirement.

Technical Reference(s): SD-PPS page 36 Rev. 19 (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. 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 X 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 76 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 022 A4.02 Importance Rating 3.2 K/A Statement Ability to manually operate and/or monitor in the control room: CCS pumps Proposed Question: RO 39 Rev: 0 Given:

Plant is operating at 100% power with A, C and D Containment Fan Coolers operating

A LOCA occurs

Containment Pressure is 17.5 PSIA Which ONE of the following describes the CCW flow configuration to the Containment Fan Coolers?

A. CCW flow of 1400 GPM on both the A header and the B header.

B. CCW flow of 2700 GPM on both the A header and the B header.

C. CCW flow of 1400 GPM to each Containment Fan Cooler.

D. CCW flow of 2700 GPM to each Containment Fan Cooler.

Revision 0 Facility: Waterford 3 Page 77 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Plausible because this would be the flow rate on each train if all four of the CFCs were operating in the non-emergency mode.

B. CORRECT: Following a SIAS (which occurs at 17.1 psia in containment) the TCVs, CC-835A(B), fully opens to supply 2700 gpm to each train (each train supplies two CFCs).

C. Incorrect. Plausible because all four CFCs have CCW flow indication on CP-18. It could be assumed that each CFC has its own TCV that repositions on a SIAS.

Before the SIAS, Train A was being supplied 1400 gpm and Train B was being supplied 700 gpm. After the SIAS, all four CFCs are operating in slow speed.

Therefore, it is plausible that all four of the CFCs are receiving 1400 gpm.

D. Incorrect. Plausible because all four CFCs have CCW flow indication on CP-18. It could be assumed that each CFC has its own TCV that repositions on a SIAS.

Following a SIAS the TCVs, CC-835A(B), fully opens to supply 2700 gpm to each train (each train supplies two CFCs). After the SIAS, all four CFCs are operating in slow speed. Therefore, it is plausible that all four of the CFCs are receiving 2700 gpm Technical Reference(s): SD-CCS page 9, 10 Rev. 8 (Attach if not previously provided) WLP-OPS-CCS00 page 53 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CCS00 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 X 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 78 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 026 G2.4.46 Importance Rating 4.2 K/A Statement Containment Spray System 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

Proposed Question: RO 40 Rev: 0 Given:

An RCS heatup and pressurization is in progress

RCS temperature is 330°F and RCS pressure is 390 psia

During a board walkdown, the BOP identifies the following annunciator in alarm:

CS 111A/117A NOT FULLY OPEN For the present conditions, Containment Spray Train A _______________.

A. is inoperable and Technical specification 3.6.2.1 Containment Spray System, is applicable B. must be properly aligned before raising RCS temperature above 350°F only C. is properly aligned for continued heatup and pressurization to Mode 1 D. must be properly aligned before raising RCS temperature to above 350°F or raising RCS pressure above 400 psia Revision 0 Facility: Waterford 3 Page 79 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Plausible if the applicant is not aware of the asterisk in the Mode 4 applicability for TS 3.6.2.1 that states with Reactor Coolant System pressure > 400 psia.

B. Incorrect. Plausible if the applicant is not aware of the asterisk in the Mode 4 applicability for TS 3.6.2.1 that states with Reactor Coolant System pressure > 400 psia.

C. Incorrect. Plausible if the applicant determines that both CS-111A or CS-117A are not required to be open at Mode 1. With CS-111A or CS-117A not fully open, the CS train is not operable. These valves are closed when SDC is placed in service.

D. CORRECT: The applicability for TS 3.6.2.1 states that two independent containment spray systems are required to be operable in Modes 1-4. Mode 4 has an asterisk stating that with Reactor Coolant System pressure > 400 psia. Therefore, the crew cannot raise temperature above 350°F (Mode 3) nor can they raise RCS pressure above 400 psia to be in compliance with the applicability of TS 3.6.2.1. With CS-111A or CS-117A not fully open, the CS train is not operable. These valves are closed when SDC is placed in service or to comply with TS 3.6.3 for CS-125A.

Technical Reference(s): TS 3.6.2.1 (Attach if not previously provided) OP-010-003 page 51 Rev. 351 (including version/revision number) OP-500-011 Attachment 4.44 Rev. 27 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CS00 obj. 7 (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 X 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 80 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 039 A4.04 Importance Rating 3.8 K/A Statement Ability to manually operate and/or monitor in the control room: Emergency feedwater pump turbines Proposed Question: RO 41 Rev: 0 Given:

EFW Pump AB has tripped due to an electrical overspeed Which ONE of the following are the minimum actions required to align EFW Pump AB for a restart, without causing another overspeed?

A. Close MS-416, depressurize the steam header, then reopen MS-416.

B. Close MS-416, depressurize the steam header, reset the trip locally, then reopen MS-416.

C. Close both Pump AB TURB STM Supply valves MS-401A and MS-401B, depressurize the steam header, then close and reopen MS-416.

D. Close both Pump AB TURB STM Supply valves MS-401A and MS-401B, depressurize the steam header, close MS-416, reset the trip locally, then reopen MS-416.

Revision 0 Facility: Waterford 3 Page 81 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Plausible because these steps would reset the electrical overspeed. But, not closing MS-401A and B would cause an overspeed of EFW Pumps AB when MS-416 is re-opened.

B. Incorrect. Plausible because closing MS-416 would isolate Main Steam to EFW Pump AB. But not closing MS-401A and B would cause an overspeed of EFW Pumps AB when MS-416 is re-opened. On an electrical overspeed of EFW Pump AB, resetting the trip locally is not required (only for mechanical overspeed).

C. CORRECT: The correct sequence to reset EFW Pump AB following an electrical overspeed is to close both Pump AB TURB STM Supply valves MS-401A and MS-401B, depressurize the steam header, then close and reopen MS-416.

D. Incorrect. On an electrical overspeed of EFW Pump AB, resetting the trip locally is not required. This answer is plausible because the trip would have to be reset locally if a mechanical overspeed had occurred. The stem asks for the minimum actions required.

Technical Reference(s): OP-902-006 step 9 Rev. 19 (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. 10 (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 X 10 CFR Part 55 Content: 55.41 4,7,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 82 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 039 A1.05 Importance Rating 3.2 K/A Statement Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MRSS controls including: RCS T-ave.

Proposed Question: RO 42 Rev: 0 Given:

Reactor Coolant System Tcold is 490°F and lowering Reactor Coolant Pumps (RCPs) 1B and 2B are running 15 minutes ago the Reactor Coolant System Tc was 510°F when a controlled cool down was established The cool down is being controlled using MS-319A, Main Steam Bypass 1A, in manual At the present cooldown rate, the maximum allowed cool down rate will ___(1)____.

Tcold should be determined as the average of all Tcold indications measured by the instruments located ___(2)_____.

(1) (2)

A. not be exceeded in RC loops with operating RCPs B. be exceeded in RC loops with operating RCPs C. not be exceeded in all four cold legs D. be exceeded in all four cold legs Revision 0 Facility: Waterford 3 Page 83 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: The maximum cooldown rate allowed by TS 3.4.8.1 is 100°F/hr. The cooldown rate in this instance is 20°F in the first 15 minutes. Calculated out to one hour, the cooldown rate would be 80°F/hr, which is within TS required limits. Limitation 3.2.23 in OP-010-005, Plant Shutdown, states that Tcold should be determined as the average of all Tcold indications measured by the instruments located in the RCS loops with operating RCPs B. Incorrect. The maximum cooldown rate allowed by TS 3.4.8.1 is 100°F/hr. The cooldown rate in this instance is 20°F in the first 15 minutes. Calculated out to one hour, the cooldown rate would be 80°F/hr which is within TS required limits. Limitation 3.2.23 in OP-010-005, Plant Shutdown. TS being exceeded is plausible becuause the applicant could do the calculation wrong or could determine that 60°F/hr is being exceed, which is the maximum limit on heatup rate.

C. Incorrect. Part 1 is correct. Part 2 is plausible because there are four cold legs and all cold legs will have some flow with two RCPs running.

D. Incorrect. The maximum cooldown rate allowed by TS 3.4.8.1 is 100°F/hr. The cooldown rate in this instance is 20°F in the first 15 minutes. Calculated out to one hour, the cooldown rate would be 80°F/hr which is within TS required limits. Limitation 3.2.23 in OP-010-005, Plant Shutdown. TS being exceeded is plausible because the applicant could do the calculation wrong or could determine that 60°F/hr is being exceed, which is the maximum limit on heatup rate. Part 2 is plausible because there are four cold legs and all cold legs will have some flow with two RCPs running.

Technical Reference(s): OP-010-005 page 42 Rev. 337 (Attach if not previously provided) OP-010-005 page 9 Limitation 3.2.23 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPN02 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 X 10 CFR Part 55 Content: 55.41 5,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 84 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 059 A3.04 Importance Rating 2.5 K/A Statement Ability to monitor automatic operation of the MFW, including: Turbine driven feed pump.

Proposed Question: RO 43 Rev: 0 Given:

Plant is at 42% power

Condensate Pumps A, B and C are in operation

Both Main Feedwater Pumps are operating Condensate Pumps A and B trip.

The Main Feedwater Pump Turbine Condensate Pump Interlock will trip Main Feedwater Pump _____(1)_____. This trip is active if the Main Feedwater Pump Turbine High Pressure (HP) governor valves are ______(2)_____.

(1) (2)

A. A not fully closed B. A fully closed C. B fully closed D. B not fully closed Revision 0 Facility: Waterford 3 Page 85 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. If Condensate Pump C is the only pump left running, then Main Feedwater Pump B will trip. Part 2 is correct.

B. Incorrect. If Condensate Pump C is the only pump left running, then Main Feedwater Pump B will trip. both HP governor valves must be not closed for the Main Feedwater Pump turbine condensate pump interlock to be active C. Incorrect. If Condensate Pump C is the only pump left running, then Main Feedwater Pump B will trip. both HP governor valves must be not closed for the Main Feedwater Pump turbine condensate pump interlock to be active D. CORRECT: Per OP-003-033 automatic action 9.1.7, both HP governor valves must be not closed for the Main Feedwater Pump turbine condensate pump interlock to be active. If Condensate Pump C is the only pump left running, then Main Feedwater Pump B will trip.

Technical Reference(s): OP-003-033 automatic action 9.1.15 Rev. 326 (Attach if not previously provided) SD-FWP pg. 10, revision 4 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-FWP00 obj. 2 (As available)

Question Source: Bank # RO44 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 X 10 CFR Part 55 Content: 55.41 4,7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 86 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 061 A2.05 Importance Rating 3.1 K/A Statement Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Automatic control malfunction.

Proposed Question: RO 44 Rev: 0 Given:

Plant is at 100% power

A Steam Generator #1 WR level indicator has failed high In the event of an EFAS-1 actuation signal, _____(1)_____ flow capacity is available to feed Steam Generator #1. Per OP-100-014, TS and TRM Compliance procedure, the crew ______(2)_____ be required to enter TS 3.6.3 Containment Isolation, for the failure of this level indicator.

(1) (2)

A. 50% will B. 50% will not C. 100% will D. 100% will not Revision 0 Facility: Waterford 3 Page 87 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is plausible because it is reasonable to assume that if one flow leg is isolated then the flow would be reduced to less than 100% (e.g. 50%). However, TS 3.7.1.2d Basis explicitly states that either of the two parallel legs in a steam generator flow path is capable of supplying 100% of the flow required. Part 2 is plausible because TS 3.6.3, Containment Isolation Valves, entry would be required if the EFW isolation valves were declared inoperable. These valves are positioned just downstream of the EFW flow control valves.

B. Incorrect. Part 1 is plausible because it is reasonable to assume that if one flow leg is isolated then the flow would be reduced to less than 100% (e.g. 50%). However, TS 3.7.1.2d Basis explicitly states that either of the two parallel legs in a steam generator flow path is capable of supplying 100% of the flow required. Part 2 is correct.

C. Incorrect. Part 1 is correct. TS 3.6.3, Containment Isolation Valves, entry would be required if the EFW isolation valves were declared inoperable. These valves are positioned just downstream of the EFW flow control valves.

D. CORRECT: The basis for TS 3.7.1.2d states that operable valves in only one flow leg (2/SG) per flow path (1/SG) are capable of supplying 100% flow to their respective SG. In this case 1 flow leg remains operable. OP-100-014, TS and TRM Compliance procedure, requires the crew to enter TS 3.7.1.2d and TS 3.3.2 (not TS 3.6.3). The EFW isolation valve (located just downstream of the FCV) is a containment isolation valve.

Technical Reference(s): OP-100-014 page 67 Rev. 353 (Attach if not previously provided) TS 3.7.1.2d basis (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-EFW00 objs. 6 and 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 88 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 061 K5.05 Importance Rating 2.7 K/A Statement Knowledge of the operational implications of the following concepts as they apply to the AFW: Feed line voiding and water hammer.

Proposed Question: RO 45 Rev: 0 OP-903-001, Technical Specification Surveillance Logs, requires the crew to verify Emergency Feedwater Pump discharge temperature every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The limit specified in OP-903-001 is __________.

A. greater than 120 ºF to verify that the line is fully pressurized from the Main Feedwater system B. less than 120 ºF to ensure that back-leakage of Main Feedwater through the EFW discharge check valve is not occurring C. greater than 230 ºF to verify that the line is fully pressurized from the Main Feedwater system D. less than 230 ºF to ensure that back-leakage of Main Feedwater through the EFW discharge check valve is not occurring Revision 0 Facility: Waterford 3 Page 89 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. The line downstream of the EFW Pump discharge check is maintained pressurized and full of water to prevent water hammer upon an EFAS. The line is kept full by the Main Feedwater System. However, this is not what is being verified when logging the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months readings.

B. CORRECT: OP-903-001, Technical Specification Surveillance Logs, requires the crew to verify Emergency Feedwater Pump discharge temperature less than 120 ºF every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ..

The limit on the logs is <120 ºF. The note (37) for this reading states that the reading is to indicate back-leakage of Main Feedwater through the EFW discharge check valves. The question meets the K/A because the verifying no back leakage through the EFW discharge check valves is to limit feed line voiding and water hammer.

C. Incorrect. The 230 ºF temperature is part of note 37.0. However, the limit in the TS logs is 120 ºF.

D. Incorrect. The 230 ºF temperature is part of note 37.0. However, the limit in the TS logs is 120 ºF. This is not a subset because the stem asks what is the limit specified in OP-903-001.

The line downstream of the EFW Pump discharge check is maintained pressurized and full of water to prevent water hammer upon an EFAS. The line is kept full by the Main Feedwater System. However, this is not what is being verified when logging the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months readings.

Technical Reference(s): OP-903-001 page 35 and 52. Rev. 83 (Attach if not previously provided) SD-EFW page 29 Rev. 17 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-EFW obj. 9 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 90 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 062 A1.03 Importance Rating 2.5 K/A Statement Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: Effect on instrumentation and controls of switching power supplies Proposed Question: RO 46 Rev: 0 Static Uninterruptable Power Supply SA (SUPS A) experiences an inverter under-voltage condition.

The Manual Bypass Switch is in the NORMAL OPERATION position.

PDP-90A loads will _______________.

A. remain energized from the DC supply through the rectifier B. remain energized due to an automatic transfer to the Bypass AC supply C. de-energize until the manual transfer to the Bypass AC supply is performed D. de-energize until the manual transfer to the DC supply is performed Revision 0 Facility: Waterford 3 Page 91 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Plausible because DC power can supply PDP-90A through the SUPS A inverter during a loss of all AC. On an inverter under-voltage condition with the Manual Transfer Switch in the NORMAL position, PDP-90A will remain energized because SUPS A will automatically swap to its bypass AC supply.

B. CORRECT: On an inverter under-voltage condition with the Manual Transfer Switch in the NORMAL position, PDP-90A will remain energized because SUPS A will automatically swap to its bypass AC supply.

C. Incorrect. On an inverter under-voltage condition with the Manual Transfer Switch in the NORMAL position, PDP-90A will remain energized because SUPS A will automatically swap to its bypass AC supply. Plausible because the SUPS Manual Transfer Switch has a Bypass to Load position that will manually transfer power to PDP-90A to the alternate AC supply.

D. Incorrect. On an inverter under-voltage condition with the Manual Transfer Switch in the NORMAL position, PDP-90A will remain energized because SUPS A will automatically swap to its bypass AC supply. Plausible because DC power can supply PDP-90A through the SUPS A inverter during a loss of all AC.

Technical Reference(s): SD-ID page 6 and Figure 2 Rev. 10.

(Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-ID00 obj. 16 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 92 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 063 K4.02 Importance Rating 2.9 K/A Statement Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following: Breaker interlocks, permissives, bypasses and cross-ties.

Proposed Question: RO 47 Rev: 0 Given:

A Loss of all Offsite Power has occurred

Crew has entered OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery Procedure The CRS has directed the auxiliary operator to secure TGB loads in accordance with 3 of OP-902-009, Standard Appendices.

With no turbine building battery chargers energized and no operator action, the maximum discharge time for the turbine building battery is ____(1)____ minutes.

Securing TGB loads will preserve the remote operation of the ____(2)____ bus feeder breakers.

(1) (2)

A. 30 2 B. 30 1 C. 90 1 D. 90 2 Revision 0 Facility: Waterford 3 Page 93 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Attachment 33-B of OP-902-009 states With the turbine building battery chargers not energized and no operator action, the maximum discharge time for the Turbine Building battery is 90 minutes (not 30 minutes). 30 minutes is the time requirement to finish stripping safety related DC loads during a SBO. Part 2 is correct.

B. Incorrect. Attachment 33-B of OP-902-009 states With the turbine building battery chargers not energized and no operator action, the maximum discharge time for the Turbine Building battery is 90 minutes (not 30 minutes). 30 minutes is the time requirement to finish stripping safety related DC loads during a SBO. DC control power for the 2 Bus feeder breakers is TGB-DC. The control power for the 1 Bus feeder breakers is from safety related A and B DC.

C. Incorrect. Part 1 is correct. DC control power for the 2 Bus feeder breakers is TGB-DC. The control power for the 1 Bus feeder breakers is from safety related A and B DC.

D. CORRECT: Attachment 33-B of OP-902-009 states With the turbine building battery chargers not energized and no operator action, the maximum discharge time for the Turbine Building battery is 90 minutes. DC control power for the 2 Bus feeder breakers is TGB-DC.

Technical Reference(s): OP-902-009 Attachment 33-B Rev. 319 (Attach if not previously provided) TGOP-902-009 pages 92 Rev. 313 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE05 obj. 6 (As available)

Question Source: Bank # RO16 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2015 NRC RO Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 94 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 064 K6.07 Importance Rating 2.7 K/A Statement Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: Air receivers.

Proposed Question: RO 48 Rev: 0 Given:

An earthquake has occurred at Waterford 3 A loss of offsite power has occurred Emergency Diesel Generator A and B are supplying the safety busses A support beam in the A Emergency Diesel Generator room has fallen on and damaged both Air compressors A1 and A2 Both air receiver pressures are 0 PSIG Emergency Diesel Generator A develops an oil leak requiring it to be shutdown What action is required to shutdown Emergency Diesel Generator A?

A. Depress the Emergency Shutdown push buttons on CP-1.

B. Select STOP on the local Emergency Diesel Generator control panel.

C. Pull the Overspeed Trip Plunger located on the Overspeed Governor.

D. Pull and hold the manual Fuel Rack Override lever to the no fuel position.

Revision 0 Facility: Waterford 3 Page 95 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect: Emergency pushbutton on CP 1 is not Active in the Emergency Mode.

B. Incorrect. Emergency pushbutton on Local EDG control panel is not Active in Emergency Mode.

C. Incorrect. Due to no air available the manual overspeed trip will not function.

D. CORRECT: The fuel rack must be pulled and held down until the diesel comes to a rest to shutdown the EDG.

Technical Reference(s): OP-009-002 page 61 and 62 Rev. 353 (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. 2 (As available)

Question Source: Bank # RO50 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2011 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 96 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 073 K4.01 Importance Rating 4.0 K/A Statement Knowledge of Process Radiation Monitoring System design feature(s) and/or interlock(s),

which provide for the following: Release termination when radiation exceeds setpoint.

Proposed Question: RO 49 Rev: 0 Given:

The plant is at 40% power

Blowdown discharge to Circ Water is in progress

BD-303, Blowdown to Circ Water and Metal Waste Pond Isolation Valve, closes Which ONE of the following can cause the valve to close?

A. High radiation on the Blowdown Radiation Monitor B. High Radiation on the Circ Water Radiation Monitor C. Trip of the running Blowdown Pump D. Hi pH alarm on Blowdown Proportional Sampler Revision 0 Facility: Waterford 3 Page 97 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. The blowdown radiation monitor does not send signals for any components to actuate. Alarm only. Plausible because the blowdown radiation monitor is always in service measuring the blowdown stream.

B. CORRECT: High Radiation on the Circ Water Radiation Monitor will automatically close BD-303 isolating blowdown flow to the Circ Water system.

C. Incorrect. Blowdown pump tripping does not send a signal to close BD-303.

Plausible if the applicant determines that the discharge to Circ Water is isolated upon the loss of process flow.

D. Incorrect. Hi pH alarm on Blowdown Proportional Sampler is an actual alarm but does not cause closure of BD-303.

Technical Reference(s): OP-901-414 page 4 Rev. 301 (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 # RO 51 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2015 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7,11 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 98 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 073 A1.01 Importance Rating 3.2 K/A Statement Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including: Radiation levels.

Proposed Question: RO 50 Rev: 0 Given:

Waste Condensate Tank B is being discharged to Circulating Water

WASTE LIQUID DISCH ACTIVITY HI alarm actuates OP-901-412, Liquid Waste Discharge High Radiation, directs crew to verify the alarm is valid by checking radiation levels ______(1)______ . The WCT pump being used for the release is secured by operating the control switch at _______(2)_______.

(1) (2)

A. at the Liquid Waste Discharge CP-4 Monitor (PRM-IRE-0647)

B. on the Liquid Waste Discharge CP-4 Recorder (LWM-IFRR-0647) on CP-4 C. at the Liquid Waste Discharge LCP-42 Monitor (PRM-IRE-0647)

D. on the Liquid Waste Discharge LCP-42 Recorder (LWM-IFRR-0647) on CP-4 Revision 0 Facility: Waterford 3 Page 99 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Radiation levels can be obtained locally at the LWM Radiation Monitor but the discharge of the WCTs are no longer occurring because the discharge isolation valves (LWM-441 and LWM-442) have closed due to the high radiation. The crew can see previous radiation levels on the recorder at CP-4. The WCT pump is secured by the NAO at the local control panel. There is no control switch for the WCT pump at CP-4.

B. Incorrect. Part 1 is correct. The WCT pump is secured by the NAO at the local control panel. There is no control switch for the WCT pump at CP-4.

C. Incorrect. Radiation levels can be obtained locally at the LWM Radiation Monitor but the discharge of the Waste Tanks are no longer occurring because the discharge isolation valves (LWM-441 and LWM-442) have closed due to the high radiation. The crew can see previous radiation levels on the recorder at CP-4. Part 2 is correct.

D. CORRECT: OP-901-412 directs the crew to verify the alarm is valid by checking the Liquid Waste Discharge Recorder. This recorder is located on CP-4. The WCT pump is secured by the NAO at the local control panel.

Technical Reference(s): OP-901-412 page 6 Rev. 2 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO4 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 12 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 100 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 076 K3.02 Importance Rating 2.5 K/A Statement Knowledge of the effect that a loss or malfunction of the Service Water System will have on the following: Secondary closed cooling water.

Proposed Question: RO 51 Rev: 0 Given:

The BOP reports rising Turbine Cooling Water (TCW) temperatures

The crew enters OP-901-512, Loss of Turbine Cooling Water Section E3: High System Temperature The Turbine Cooling Water Heat Exchanger requires a backflush if ___ _____.

A. Turbine Cooling Water T is high and Circulating Water T is low B. Turbine Cooling Water T is high and Circulating Water T is high C. Turbine Cooling Water T is low and Circulating Water T is high D. Turbine Cooling Water T is low and Circulating Water T is low Revision 0 Facility: Waterford 3 Page 101 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. The partial loss of cooling in the TCW heat exchanger is due to debris accumulating on the tube (CW) side of the HX from the Mississippi River. This means that the CW flow is reduced in the HX (T goes up) causing cooling to the TCW to lower (T goes down).

B. Incorrect. The partial loss of cooling in the TCW heat exchanger is due to debris accumulating on the tube (CW) side of the HX from the Mississippi River. This means that the CW flow is reduced in the HX (T goes up) causing cooling to the TCW to lower (T goes down).

C. CORRECT: The partial loss of cooling in the TCW heat exchanger is due to debris accumulating on the tube (CW) side of the HX from the Mississippi River. This means that the CW flow is reduced in the HX (T goes up) causing cooling to the TCW to lower (T goes down).

D. Incorrect. The partial loss of cooling in the TCW heat exchanger is due to debris accumulating on the tube (CW) side of the HX from the Mississippi River. This means that the CW flow is reduced in the HX (T goes up) causing cooling to the TCW to lower (T goes down).

Technical Reference(s): OP-901-512 section E3 step 3 (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 X 10 CFR Part 55 Content: 55.41 4, 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 102 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 078 K2.01 Importance Rating 2.7 K/A Statement Knowledge of bus power supplies to the following: Instrument air compressor.

Proposed Question: RO 52 Rev: 0 Instrument Air Compressor A is powered from which bus?

A. SWGR 211A B. SWGR 31A C. SWGR 32A D. SWGR 21A Revision 0 Facility: Waterford 3 Page 103 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Switchgear 211A is a 480V bus. The 211A MCC is located in the Turbine Building Switchgear near the IA compressors and serves many Turbine Building loads, but does not power the IA compressor A.

B. CORRECT: Instrument air compressor A is powered from the 31A bus.

C. Incorrect. The 32A switchgear is also a 480V switchgear and is located in the same room as the 31A bus but is not the switchgear that power IA compressor A.

D. Incorrect. Switchgear 21A is a 480V bus. The 21A switchgear is located in the Turbine Building Switchgear near the IA compressors and serves many Turbine Building loads, but does not power the IA compressor A.

Technical Reference(s): OP-003-016 page 163 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-AIR00 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 104 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 078 A3.01 Importance Rating 3.1 K/A Statement Ability to monitor automatic operation of the IAS, including: Air pressure.

Proposed Question: RO 53 Rev: 0 Given:

Plant is at 100% power

Crew has entered OP-901-511, Instrument Air Malfunction, due to lowering Instrument Air pressure The crew will verify the backup Instrument Air compressor that is aligned for Standby automatically starts at ____(1)____ psig. OP-901-511, Instrument Air Malfunction, will require the crew to trip the reactor when Instrument Air pressure lowers to

_____(2)_____.

(1) (2)

A. 105 65 B. 105 80 C. 112 65 D. 112 80 Revision 0 Facility: Waterford 3 Page 105 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: The instrument air compressor that is aligned to standby will get an automatic start signal when instrument air pressure lowers to 105 psig. Step 1 of OP-901-511 directs the crew to trip the reactor when instrument air pressure lowers to 65 psig.

B. Incorrect. Part 1 is correct. At 80 psig instrument air pressure, the crew is directed to perform a plant shutdown Step 1 of OP-901-511 directs the crew to trip the reactor when instrument air pressure lowers to 65 psig.

C. Incorrect. The instrument air compressor will load (supply air to the IA receiver) when Instrument air pressure reaches 112 psig. Part 2 is correct.

D. Incorrect. . The instrument air compressor will load (supply air to the IA receiver) when Instrument air pressure reaches 112 psig. At 80 psig instrument air pressure, the crew is directed to perform a plant shutdown Step 1 of OP-901-511 directs the crew to trip the reactor when instrument air pressure lowers to 65 psig.

Technical Reference(s): OP-901-511 pages 4, 6, 7 Rev. 17 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4,7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 106 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 103 K1.01 Importance Rating 3.6 K/A Statement Knowledge of the physical connections and/or cause-effect relationships between the Containment System and the following systems: CCS.

Proposed Question: RO 54 Rev: 0 Given:

A Loss of Cooling Accident has occurred

SIAS, CIAS, MSIS and CSAS have been initiated

After entering OP-902-002, Loss of Coolant Accident Recovery Procedure, the BOP reports that CFC A has tripped on overcurrent The crew will determine that the ____(1)____ safety function is not met. The crew will

_____(2)_____.

(1) (2)

A. containment temperature and go to OP-902-008, Functional Recovery pressure control procedure B. containment isolation go to OP-902-008, Functional Recovery procedure C. containment isolation remain in OP-902-002, Loss of Coolant Accident Recovery procedure D. containment temperature and remain in OP-902-002, Loss of Coolant pressure control Accident Recovery procedure Revision 0 Facility: Waterford 3 Page 107 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. The containment temperature and pressure control safety function is met due to >

1 CFC in operation and Containment Spray running. The guidance for closing the CFC CCW Isolation Valves is located in OP-902-002 as a contingency step. Therefore, the crew does not have to exit to OP-902-008 even though the Containment Isolation Safety Function is not being met.

B. Incorrect. Part 1 is correct. The guidance for closing the CFC CCW Isolation Valves is located in OP-902-002 as a contingency step. Therefore, the crew does not have to exit to OP-902-008 even though the Containment Isolation Safety Function is not being met.

C. CORRECT: If a SIAS/CIAS is initiated, the crew is to check all CFCs running. If any CFC is not operating, the crew is no longer meeting the Containment Isolation Safety Function until the CFC CCW isolation valves are overridden closed. The guidance for closing the CFC CCW Isolation Valves is located in OP-902-002 as a contingency step. Therefore, the crew does not have to exit to OP-902-008 even though the Containment Isolation Safety Function is not being met.

D. Incorrect. The containment temperature and pressure control safety function is met due to >

1 CFC in operation and Containment Spray running. Part 2 is correct.

Technical Reference(s): OP-902-002 pages 16, 77-78 Rev. 21 (Attach if not previously provided) TGOP-902-002 pages 41, 42 Rev. 20 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE02 obj. 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 X 10 CFR Part 55 Content: 55.41 7,8 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 108 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 013 G2.4.11 Importance Rating 4.0 K/A Statement Engineered Safety Features Actuation System 2.4.11 Knowledge of abnormal condition procedures.

Proposed Question: RO 55 Rev: 0 Given:

Plant is at 100% power

An Inadvertent EFAS-1 has occurred

Crew is performing required actions per OP-901-504 section E5 Inadvertent EFAS

The BOP reports that Steam Generator #1 (SG1) level is 70% NR and stable To reset EFAS-1, the ____(1)____ is/are manually reset. Due to the inadvertent EFAS-1, the expected position of both SG1 Emergency Feedwater Flow control valves are

____(2)_____.

(1) (2)

A. EFAS-1 actuation logic only open B. EFAS-1 actuation logic only closed C. EFAS-1 initiation relays and closed EFAS-1 actuation logic D. EFAS-1 initiation relays and open EFAS-1 actuation logic Revision 0 Facility: Waterford 3 Page 109 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Part 1 is correct. On an EFAS signal, the EFW isolation valves will open and the EFW flow control valves will remain closed until level reaches 55% WR.

B. CORRECT: Unlike all other ESFAS signals, the EFAS initiation relays will reset automatically once SG level is > 68.4% NR. The stem of the question states that SG level is 70% NR. Therefore, the crew will have to reset the actuation relays only. On an EFAS signal, the EFW isolation valves will open and the EFW flow control valves will remain closed until level reaches 55% WR.

C. Incorrect. Unlike all other ESFAS signals, the EFAS initiation relays will reset automatically once SG level is > 68.4% NR. The stem of the question states that SG level is 70% NR. Therefore, the crew will have to reset the actuation relays only. Part 2 is correct.

D. Incorrect. Unlike all other ESFAS signals, the EFAS initiation relays will reset automatically once SG level is > 68.4% NR. The stem of the question states that SG level is 70% NR. Therefore, the crew will have to reset the actuation relays only. On an EFAS signal, the EFW isolation valves will open and the EFW flow control valves will remain closed until level reaches 55% WR.

Technical Reference(s): OP-901-504 section E5 page 32 Rev. 10 (Attach if not previously provided) SD-PPS pages 36-38 Rev. 19 (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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 8,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 110 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 002 K3.03 Importance Rating 4.2 K/A Statement Knowledge of the effect that a loss or malfunction of the Reactor Coolant System will have on the following: Containment.

Proposed Question: RO 56 Rev: 0 Given:

A LOCA has occurred

The following alarm reflashes on Control Room Panel SA:

K-4, CLASS 1E RAD MONITORING SYS ACTIVITY HI-HI

The RO verifies Containment Radiation on ARM-IRE-5400AS, Cntmt Rad Monitor Hi Range A, has spiked to approximately 3500 Rem/Hr

Approximately 4 minutes later, Containment Radiation indication is 300 Rem/Hr and lowering Which ONE of the following describes the reason for the radiation monitor indication?

A. Initiation of Containment Spray has reduced iodine levels.

B. Blowdown phase of the LOCA resulted in high radiation indication. Refill and reflood phases are reducing radiation levels in Containment.

C. Failure of the radiation monitor, as it is not qualified for harsh Containment environment, and not required for safety related use.

D. Thermally induced currents due to harsh Containment environment, location of detector, and length of cabling Revision 0 Facility: Waterford 3 Page 111 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Containment spray would reduce iodine levels. But, containment spray would not give the dramatic rise and fall of radiation levels given in the stem.

B. Incorrect. Blowdown phase of the LOCA would give a higher than normal radiation reading and the subsequent refill would reduce radiation levels. But, nothing as dramatic as the radiation levels given in the stem.

C. Incorrect. The Containment High Range Radiation monitors are safety related and are qualified for harsh Containment conditions.

D. CORRECT: OI-038-000 step 5.5.1 states that Post-Accident Thermally induced currents will cause the Containment High Range RMs to read erroneously high and it will be 15 minutes post event until these same RMs read actual radiation levels in containment. W3 has two containment high range detectors. They are ARM-IR-5400A(B). SD-RMS states that the high peak could be 2000-4000 rem above actual radiation levels within the first minute and then drop down to normal within the next 15 minutes.

Technical Reference(s): SD-RMS page 41 Rev. 15 (Attach if not previously provided) OI-038-000 step 5.5.1 third bullet Rev. 19 (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 # 61 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2008 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7,11 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 112 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 016 K3.04 Importance Rating 2.6 K/A Statement Knowledge of the effect that a loss or malfunction of the Non-nuclear Instrumentation System will have on the following: MFW system.

Proposed Question: RO 57 Rev: 0 Given:

Plant is at 100% power

SG ILR 1111, Steam Generator 1 Downcomer Level, fails high

Crew has entered OP-901-201, Steam Generator Level Control Malfunction Upon a reactor trip, Main Feed Pump A speed will reduce automatically. This design feature was added to reduce the differential pressure across the ____(1)____ valves.

Upon subsequent entry into OP-902-001, Reactor Trip Recovery procedure, the Main Feed Pump A speed controller (FW IHIC1107) will be controlled in the _____(2)_____

mode.

(1) (2)

A. Main Feed Regulating automatic B. Main Feed Isolation automatic C. Main Feed Regulating manual D. Main Feed Isolation manual Revision 0 Facility: Waterford 3 Page 113 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect: The main feed regulating valve is plausible because it also receives a close signal on MSIS and a reactor trip override (RTO), but is not the reason the design feature was added. Main Feed Pump A speed controller will swap to auto upon the reactor trip for 5 seconds. Because there is a level deviation in this instance the controller will swap back to manual.

B. Incorrect. Part 1 is correct. Main Feed Pump A speed controller will swap to auto upon the reactor trip for 5 seconds. Because there is a level deviation in this instance the controller will swap back to manual.

C. Incorrect. The main feed regulating valve is plausible because it also receives a close signal on MSIS and a reactor trip override, but is not the reason the design feature was added. Part 2 is correct.

D. CORRECT: On a reactor trip override (RTO), FWCS will swap the Main Feed Pump speed controllers to auto and drive them to minimum speed if the controller was in manual. If the controller was in manual due to a level deviation, which in this case it is, the controller will still swap to auto but will return to manual after 5 seconds. As stated in the basis for TS 3.7.6.1, this design feature is to ensure rapid closure of a MFIV on a MSIS by ensuring DP across the valve is reduced.

Technical Reference(s): TS 3.7.1.6 basis (Attach if not previously provided) SD-FWC pp.24-25 (Rev 13)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-FWC00 obj. 6 (As available)

WLP-OPS-FW00 obj. 7 Question Source: Bank # RO1 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 X 10 CFR Part 55 Content: 55.41 7,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 114 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 028 K2.01 Importance Rating 2.5 K/A Statement Knowledge of bus power supplies to the following: Hydrogen recombiners.

Proposed Question: RO 58 Rev: 0 The power supply to Hydrogen Recombiner B is the ____(1)_____ bus.

A. 213B B. 313B C. 314B D. 315B Revision 0 Facility: Waterford 3 Page 115 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. The 213B bus is plausible because this bus is a 480V MCC bus just like the 313B bus is.

B. CORRECT: The power supply to Hydrogen Recombiner B is the 313B bus.

C. Incorrect. The 314B bus is plausible because this bus is a 480V MCC bus just like the 313B bus is.

D. Incorrect. The 315B bus is plausible because this bus is a 480V MCC bus just like the 313B bus is.

Technical Reference(s): OP-008-006 page 17 Rev. 301 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-HRA 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 116 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 035 K5.01 Importance Rating 3.4 K/A Statement Knowledge of operational implications of the following concepts as they apply to the Steam Generator System: Effect of secondary parameters, pressure, and temperature on reactivity.

Proposed Question: RO 59 Rev: 0 Given:

Plant is at 90% power

The TURBINE MANUAL pushbutton is illuminated on the DEH panel

A Hi-Hi level in #2 Main Feedwater Heaters has occurred causing ES-205, ES to IP Heaters #2 isolation, to start closing With no operator action, reactor power will ____(1)_____. To restore, momentary taps on the _____(2)____ pushbutton is required.

(1) (2)

A. rise GV lower B. rise TV lower C. lower TV lower D. lower GV lower Revision 0 Facility: Waterford 3 Page 117 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: ES-205, Extraction Steam to IP Heaters #2 Isolation, going closed would reduce the pre-heating of the main feedwater entering the steam generators. The lower main feedwater temperature entering the SG will cause Tcold to drop. Tcold dropping would cause reactor power to rise. OP-901-221, Secondary Plant Transient, will direct the crew to remove 100 MW at 40MW/min to restore Tcold to normal. To raise temperature using the Main Turbine in manual, the crew will need to close governor valves, this is done by depressing the governor valve lower pushbutton on the DEH panel.

B. Incorrect. Part 1 is correct. To raise temperature using the Main Turbine in manual, the crew will need to close governor valves, this is done by depressing the governor valve lower pushbutton on the DEH panel. On this same panel, next to the GV lower pushbutton is the TV lower pushbutton. Using the throttle valves are plausible because throttle valves are used to bring turbine speed up to 1700 rpm during a startup, but are not used to adjust turbine load.

C. Incorrect. ES-205, Extraction Steam to IP Heaters #2 Isolation, going closed would reduce the pre-heating of the main feedwater entering the steam generators. The lower main feedwater temperature entering the SG will cause Tcold to drop. Tcold dropping would cause reactor power to rise. On this same panel, next to the GV lower pushbutton is the TV lower pushbutton. Using the throttle valves are plausible because throttle valves are used to bring turbine speed up to 1700 rpm during a startup, but are not used to adjust turbine load.

D. Incorrect. ES-205, Extraction Steam to IP Heaters #2 Isolation, going closed would reduce the pre-heating of the main feedwater entering the steam generators. The lower main feedwater temperature entering the SG will cause Tcold to drop. Tcold dropping would cause reactor power to rise. Part 2 is correct.

Technical Reference(s): OP-901-221 pages 3, 8 Rev. 5 (Attach if not previously provided) OP-005-007 page 54 Rev. 308 (including version/revision number) SD-DEH Fig. 12 Rev. 11 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 X 10 CFR Part 55 Content: 55.41 4,5 55.43 Revision 0 Facility: Waterford 3 Page 118 of 152

2020 NRC Exam RO Written Exam Worksheet Revision 0 Facility: Waterford 3 Page 119 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 041 K6.03 Importance Rating 2.7 K/A Statement Knowledge of the effect of a loss or malfunction on the following will have on the SDS: Controller and positioners, including ICS, S/G, CRDS.

Proposed Question: RO 60 Rev: 0 Given:

Plant is at 100% power

An instrument air leak has occurred at MS-320C, Steam Bypass Control Valve (SBCV) #6. Instrument air has been isolated to MS-320C and the associated permissive switch taken to the OFF position With the above conditions, total capacity of the Steam Bypass Control Valve is approximately ____(1)_____ of rated steam flow. If a reactor trip occurs, the pressure rise in the steam generators will be limited by _____(2)_____ cycling open.

(1) (2)

A. 60% Steam Bypass Control Valves only B. 60% SBCV and Atmospheric Dump Valves C. 50% SBCV and Atmospheric Dump Valves D. 50% Steam Bypass Control Valves only Revision 0 Facility: Waterford 3 Page 120 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is plausible because it could be determined that total valve capacity is 70%

or it could be determined that the SBCV is still available in manual mode with the controller.

Part 2 is correct.

B. Incorrect. Part 1 is plausible because it could be determined that total valve capacity is 70%

or it could be determined that the SBCV is still available in manual mode with the controller.

Part 2 is plausible because SBCV #6 will not open on the reactor trip. The applicant could determine that not enough SBCV valve capacity is available and Steam Generator pressure will rise to the setpoint of the ADV and open it. On a reactor trip with Tave > 561 (in this case Tave would be 574) the #6 Steam Bypass Control valve is blocked from quick opening any time that the SBCS senses a reactor trip (even if it was available). In this case, only the SBCVs will open and the ADVs will remain closed.

C. Incorrect. Part 1 is correct. Part 2 is plausible because SBCV #6 will not open on the reactor trip. The applicant could determine that not enough SBCV valve capacity is available and Steam Generator pressure will rise to the setpoint of the ADV and open itOn a reactor trip with Tave > 561 (in this case Tave would be 574) the #6 Steam Bypass Control valve is blocked from quick opening any time that the SBCS senses a reactor trip (even if it was available). In this case, only the SBCVs will open and the ADVs will remain closed.

D. CORRECT: The total valve capacity of all six steam bypass control valves is 59.3% of rated steam flow. Each valve has a capacity of 9.88%. Therefore, 59.3% - 9.88% is approximately 50%. With instrument air isolated, the Steam Bypass Control valve is incapable of opening (in manual or auto). On a reactor trip with Tave > 561 (in this case Tave would be 574) the #6 Steam Bypass Control valve is blocked from quick opening any time that the SBCS senses a reactor trip (even if it was available). In this case, only the SBCVs will open and the ADVs will remain closed.

Technical Reference(s): SD-SBC pages 6, 25, 27, 31, 32 Rev. 10 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SBC00 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 X 10 CFR Part 55 Content: 55.41 7 55.43 Revision 0 Facility: Waterford 3 Page 121 of 152

2020 NRC Exam RO Written Exam Worksheet Comments:

Revision 0 Facility: Waterford 3 Page 122 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 045 A1.06 Importance Rating 3.3 K/A Statement Ability to predict and/or monitor changes in parameters to prevent exceeding design limits associated with operation of the Main Turbine Generator System including: Expected response of secondary plant parameters following T/G trip.

Proposed Question: RO 61 Rev: 0 Given:

Plant is at 55% power

Reactor Power Cutback is out of service

The Main Turbine has tripped due to a loss of Main Lube Oil The crew will ____(1)_____. When the steps of OP-901-210 Turbine Trip, have been completed, the crew will verify Steam Generator pressures are equal to approximately

_____(2)_____.

(1) (2)

A. verify an automatic 1070 psig reactor trip has occurred B. verify an automatic 992 psig reactor trip has occurred C. manually trip the reactor 992 psig D. manually trip the reactor 1070 psig Revision 0 Facility: Waterford 3 Page 123 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Plausible because a turbine trip will normally trip the reactor if Reactor Power Cutback is out of service. But not below 65% power as the C explanation below describes.

The applicant must determine that condenser vacuum will be broken if all steps of OP-901-210, Turbine trip, are complete. Condenser vacuum is broken to stop the turbine more quickly because it tripped on a loss of main lube oil. Step 6.5 of OP-901-210 directs the crew verify SG pressure maintained at ~992 psig. 1070 psig is plausible because this is the pressure that the first Main Steam Safety Valve opens.

B. Incorrect. Plausible because a turbine trip will normally trip the reactor if Reactor Power Cutback is out of service. But not below 65% power as the C explanation below describes.

Part 2 is correct.

C. CORRECT: A loss of turbine trip will not trip the reactor if reactor power is below 65% power.

In PPS, a contact closes below 65% power to keep the bistable relays energized for the loss of turbine trip because load can be handled by Steam Bypass Control at this power. The applicant must determine that condenser vacuum will be broken if all steps of OP-901-210, Turbine trip, are complete. OP-901-210 will direct the crew to trip the reactor. Condenser vacuum is broken to stop the turbine more quickly because it tripped on a loss of main lube oil. Step 6.5 of OP-901-210 directs the crew verify SG pressure maintained at ~992 psig by ADVs.

D. Incorrect. Part 1 is correct. The applicant must determine that condenser vacuum will be broken if all steps of OP-901-210, Turbine trip, are complete. Condenser vacuum is broken to stop the turbine more quickly because it tripped on a loss of main lube oil. Step 6.5 of OP-901-210 directs the crew verify SG pressure maintained at ~992 psig. 1070 psig is plausible because this is the pressure that the first Main Steam Safety Valve opens.

Technical Reference(s): OP-901-210 pages 7, 8 Rev. 6 (Attach if not previously provided) SD-PPS page 19 Rev. 19 (including version/revision number) SD-MS page 36 Rev. 19 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 X 10 CFR Part 55 Content: 55.41 5,10 55.43 Revision 0 Facility: Waterford 3 Page 124 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 015 A3.03 Importance Rating 3.9 K/A Statement Ability to monitor automatic operation of the NIS, including: Verification of proper functioning/operability.

Proposed Question: RO 62 Rev: 0 Given:

A Reactor startup is in progress in accordance with OP-010-003, Plant Startup

Reactor Power is 5.5 X 10-8 Startup Channel high voltage is automatically removed when power exceeds approximately _____(1)_____%. When the Reactor has achieved criticality, the crew will perform a Channel Check of Log Power Channels. Acceptable Channel Check is log channels read _____(2)_____ between channels on their meters at CP-7.

(1) (2)

A. 1.0 X 10-4 1/2 linear distance B. 1.0 X 10-4 one decade C. 5.3 X 10-6 one decade D. 5.3 X 10-6 1/2 linear distance Revision 0 Facility: Waterford 3 Page 125 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Part 1 is plausible because automatic actions do occur in the Nuclear Instrument System at 1.0 X 10-4 % power such as CPCs Trip Bypass will automatically be removed. Part 2 is plausible because the channel check for log power in the past for W3 was 1/2 the linear distance between decades until Tech Specs changed.

B. Incorrect. Part 1 is plausible because automatic actions do occur in the Nuclear Instrument System at 1.0 X 10-4 % power such as CPCs Trip Bypass will automatically be removed. Part 2 is correct.

C. CORRECT: Step 9.4.43 of OP-010-003 Plant Startup, directs the crew to verify both Startup Channels deenergize at ~ 5.3 X 10-6 % power. Step 9.4.44 states when Reactor has achieved criticality, then perform a channel check of Log Power Channels. Acceptable Channel Check is One decade. OP-903-001 note 30 states the Log Power channel check comparison should be between Channels A,B,C and D.

D. Incorrect. Part 1 is correct. Part 2 is plausible because the channel check for log power in the past at W3 was 1/2 the linear distance between decades until Tech Specs changed.

Technical Reference(s): OP-010-003 steps 9.4.43, 9.4.44 Rev. 351 (Attach if not previously provided) OP-903-001 page 27 Rev. 84 (including version/revision number) OP-903-001 Note 30 on page 51 Rev. 84 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-ENI00 objs 7 and 11 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 126 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 056 A2.04 Importance Rating 2.6 K/A Statement Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps.

Proposed Question: RO 63 Rev: 0 Given:

Plant is at 100% power

All three Condensate Pumps are running

The crew is required to remove Condensate Pump C from service due to elevated motor temperatures Removal of Condensate Pump C ___(1)___. To ensure Steam Generator Feed Pump suction pressure is maintained above the low suction pressure trip, OP-003-003 Condensate, states that the crew may be required to _____(2)_____ .

(1) (2)

A. will require a load reduction in place additional accordance with OP-901-221, condensate polisher Secondary System Transient vessels in service B. will require a load reduction in throttle open CD-1532, accordance with OP-901-221, Condensate Polisher Secondary System Transient Bypass C. will have no effect on power throttle open CD-1532, generation Condensate Polisher Bypass D. will have no effect on power place additional generation condensate polisher vessels in service Revision 0 Facility: Waterford 3 Page 127 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Part 1 is plausible because W3 normal configuration is three condensate pumps running and OP-901-221 provides load reduction requirements for a loss of heaters, heater drain pumps, etc. Load reduction for Condensate pump is not located in the offnormal because a load reduction is not required. Placing additional condensate polisher vessels in service will help to raise suction pressure at the Main Feed Pump but would not offer precise control and is not the direction provided by OP-003-003 to maintain Steam Generator Feed Pump suction pressure.

B. Incorrect. Part 1 is plausible because W3 normal configuration is three condensate pumps running and OP-901-221 provides load reduction requirements for a loss of heaters, heater drain pumps, etc. Load reduction for Condensate pump is not located in the offnormal because a load reduction is not required. Part 2 is correct.

C. CORRECT: OP-003-003 Limitation 3.2.2.1 states that removing one Condensate Pump from service with three already running will have no effect on power generation. The note prior to step 8.5.1 in OP-003-003 states that CD-1532 may need to be throttled open to maintain Steam Generator Feed Pump suction pressure above the low pressure trip.

D. Incorrect. Part 1 is correct. Placing additional condensate polisher vessels in service will help to raise suction pressure at the Main Feed Pump but would not offer precise control and is not the direction provided by OP-003-003 to maintain Steam Generator Feed Pump suction pressure.

Technical Reference(s): OP-003-003 Limitation 3.2.2.1 Rev. 310 (Attach if not previously provided) OP-003-003 section 8.5 Rev. 310 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CD00 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 128 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 079 G2.4.12 Importance Rating 4.0 K/A Statement 079 Station Air 2.4.12 Knowledge of general operating crew responsibilities during emergency operations.

Proposed Question: RO 64 Rev: 0 Given:

Plant is at 100% power

An instrument air leak has occurred

Crew has entered OP-901-511, Instrument Air Malfunction The BOP directs 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 95 psig,

_____(2)_____ .

(1) (2)

A. raise IA-123, Instrument Air Dryers Bypass solenoid, opens B. raise a plant shutdown in accordance with OP-010-005, Plant Shutdown, is required C. lower IA-123, Instrument Air Dryers Bypass solenoid, opens D. lower a plant shutdown in accordance with OP-010-005, Plant Shutdown, is required Revision 0 Facility: Waterford 3 Page 129 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: The set point on SA-125 must be raised to force the valve open. The set point is the pressure at which the valve will start to open. Usually set at 105 psig.

Raising the set point will make the valve open at a higher pressure. IA-123 is designed to open and bypass the IA dryers at 95 psig.

B. Incorrect. Part 1 is correct. The crew will commence a plant shutdown in accordance with OP-010-005, Plant Shutdown when Instrument Air pressure reaches 80 psig.

C. Incorrect. The set point on SA-125 must be raised to force the valve open. The set point is the pressure at which the valve will start to open. Usually set at 105 psig.

Raising the set point will make the valve open at a higher pressure. Part 2 is correct.

D. Incorrect. The set point on SA-125 must be raised to force the valve open. The set point is the pressure at which the valve will start to open. Usually set at 105 psig.

Raising the set point will make the valve open at a higher pressure. The crew will commence a plant shutdown in accordance with OP-010-005, Plant Shutdown when Instrument Air pressure reaches 80 psig.

Technical Reference(s): OP-901-511 page 6 and 7 Rev. 17 (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 # RO17 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2017 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 130 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 011 K1.05 Importance Rating 3.4 K/A Statement Knowledge of the physical connections and/or cause-effect relationships between the PZR LCS and the following systems: Reactor regulating system.

Proposed Question: RO 65 Rev: 0 Given:

Plant is operating at 100% power

TAVG LOOP SELECTOR switches in RRS Cabinets 1 and 2 are in the BOTH position

RCS temperature Loop 1 Cold Leg (RC-ITI-0111-Y) indicates failed low Letdown flow will initially ____(1)____. In accordance with OP-901-110, Pressurizer Level Control Malfunction, the preferred method of selecting the non-faulted Tcold instrument is to operate the TCOLD LOOP 1 Selector switch located in the

______(2)_____ .

(1) (2)

A. lower RRS local cabinets B. lower rear of CP-2 C. rise RRS local cabinets D. rise rear of CP-2 Revision 0 Facility: Waterford 3 Page 131 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. RCS Temperature Loop 1 Cold Leg failing low will cause the setpoint for the PLCS to lower. Actual level will be greater than setpoint, therefore letdown flow will rise (not lower). The loop selector switch in RRS cabinets is used to swap to an operable Thot instrument and can be used to swap to an operable Tcold instrument.

Although, Operating the TCOLD LOOP selector switch behind CP-2 is the preferred method of selecting the operable Tcold instrument per OP-901-110, section E2.

B. Incorrect. RCS Temperature Loop 1 Cold Leg failing low will cause the setpoint for the PLCS to lower. Actual level will be greater than setpoint, therefore letdown flow will rise (not lower). Part 2 is correct.

C. Incorrect. Part 1 is correct. The loop selector switch in RRS cabinets is used to swap to an operable Thot instrument and can be used to swap to an operable Tcold instrument. Although, Operating the TCOLD LOOP selector switch behind CP-2 is the preferred method of selecting the operable Tcold instrument per OP-901-110, section E2.

D. CORRECT: RCS Temperature Loop 1 Cold Leg failing low will cause the setpoint for the PLCS to lower. Actual level will be greater than setpoint, therefore letdown flow will rise. Operating the TCOLD LOOP selector switch behind CP-2 is the preferred method of selecting the operable Tcold instrument per OP-901-110, section E2.

Technical Reference(s): OP-901-110 section E2 page 9 Rev. 11 (Attach if not previously provided) SD-RR pages 25-26 Rev. 6 (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 # RO59 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2010 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 7,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 132 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 1 K/A # G2.1.20 Importance Rating 4.6 K/A Statement Conduct of Operations: Ability to interpret and execute procedure steps.

Proposed Question: RO 66 Rev: 0 Per OP-100-014, Technical Specification and Technical Requirements Compliance Procedure, the Reactor Coolant System (RCS) Loops Filled is defined as the condition of the RCS after ___________.?

A. 5% Pressurizer Cold Cal level (30 feet) has been obtained B. the RCS has been filled to the top of the hot legs (15.13 feet)

C. venting at the Reactor Coolant Pump seals has been completed in accordance with the RCS fill and vent procedure D. the RCS has been filled and the reactor vent sections of the RCS fill and vent procedure have been completed Revision 0 Facility: Waterford 3 Page 133 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. The 5% Cold Cal level is the level below which the loops are considered not full when draining as defined by step 3.11 of OP-100-014.

B. Incorrect. The top of the hot legs at W3 is 15.13 feet. This distractor is plausible because this is this elevation where the RCS loops are full but is not considered loops filled as defined in OP-100-014.

C. Incorrect. Venting at all four RCPs are performed in accordance with the vent section of OP-001-001. But, OP-100-014 defines the RCS loops filled as the entire vent section is completed.

D. CORRECT: Step 3.11 of OP-100-014 defines the RCS loops filled as the condition of the RCS after the RCS has been filled and the reactor vent section of OP-001-001 has been completed. This question is generic because the condition of the RCS loops filled and RCS loops not filled occur in various TS including TS 3.1.2.9, TS 3.4.1.4, TS 3.4.1.5. This step in OP-100-014 assists the operator in interpreting this condition of the RCS.

Technical Reference(s): OP-001-001 section 6.7 Rev. 40 (Attach if not previously provided) OP-100-014 step 3.11 Rev. 354 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-REQ04 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 134 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 1 K/A # G2.1.41 Importance Rating 2.8 K/A Statement Conduct of Operations: Knowledge of the refueling process.

Proposed Question: RO 67 Rev: 0 Given:

Preparations are in progress to disassemble the reactor for a refueling outage.

During disassembly of the reactor, which of the following is the first evolution that will require completion of the Pre-core alteration checklist prior to commencing?

A. De-tensioning of the reactor head.

B. Removal of the reactor head.

C. Removal of the upper guide structure.

D. Removal of the first assembly from the core.

Revision 0 Facility: Waterford 3 Page 135 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. De-tensioning of the reactor head is plausible because this is the first manipulation for disassembly of the reactor vessel and requires the Entering Mode 6 checklist to be performed in accordance with OP-010-006, Outage operations.

B. Incorrect. Plausible because removing of the vessel head exposes the reactor vessel internals.

C. CORRECT: The first evolution during disassembly of the reactor that is considered a core alteration is the removal of the Upper Guide Structure.

D. Incorrect. Plausible because removal of the first fuel assembly is a core alteration.

The stem of the questions what would first require the precore alteration checklist to be performed. Removal of the upper guide structure occurs before the first assembly is removed Technical Reference(s): OP-010-006 page 32, 34 Rev. 334 (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. 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 136 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 2 K/A # G2.2.15 Importance Rating 3.9 K/A Statement Equipment Control: Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, lineups, or tag-outs.

Proposed Question: RO 68 Rev: 0 A standby valve line-up is being performed following a refueling outage. Per EN-OP-115-05, Operation of Components, which of the following is the minimum requirement for checking the position of a manual handwheel operator valve full open?

A. Apply force in the open direction until firm resistance is met.

B. Observe that the relative height of the valve stem indicates the valve is open.

C. Verify no open component deviation sheets initiated for the valve being verified open.

D. Close the valve until valve movement is observed and then open the valve until the valve is fully open.

Revision 0 Facility: Waterford 3 Page 137 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Plausible because if the manual handwheel was being checked closed the operator would only apply a force in the closed direction (step 5.2.3 of EN-OP-115-05).

B. Incorrect. Plausible because valve position can be identified by observing the relative height of a valve stem. But according to EN-OP-115-05, this method should not be used as a sole determinant of valve position. (step 5.2.1)

C. Incorrect. Plausible because a component deviation sheet is what would be used to document a valve that is out of its standby lineup position.

D. CORRECT: To check a manual handwheel open the operator will grasp the handwheel and apply force in the close direction until valve movement is observed and then apply a force to the valve handwheel in the open direction until the valve is fully open. (step 5.2.4 of EN-OP-115-05).

Technical Reference(s): EN-OP-115-05 step 5.2.4 Rev. 2 (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. 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 138 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 2 K/A # G2.2.17 Importance Rating 2.6 K/A Statement Equipment Control: Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

Proposed Question: RO 69 Rev: 0 In accordance with EN-WM-101, On-line Work Management Process, work in progress that did not finish as scheduled, but instead rolled into the following week ____(1)____

considered Emergent Work.

Fix It Now (FIN) team work _____(2)_____ considered Emergent Work.

(1) (2)

A. is is B. is is not C. is not is D. is not is not Revision 0 Facility: Waterford 3 Page 139 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Definition 4 states that carryover work is not included as emergent work and FIN team work is not considered emergent work.

B. Incorrect. Definition 4 states that carryover work is not included as emergent work.

Part 2 is correct.

C. Incorrect. Part 1 is correct. Definition 4 states that FIN team work is not considered emergent work.

D. CORRECT: EN-WM-101, On-line Work Management Process, defines Emergent Work as work added to the schedule during execution week. Definition 4 states that carryover work is not included as emergent work and FIN team work is not considered emergent work.

Technical Reference(s): EN-WM-101 page 6 Rev. 19 (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. 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 140 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 2 K/A # G2.2.35 Importance Rating 3.6 K/A Statement Equipment Control: Ability to determine Technical Specification mode of operation.

Proposed Question: RO 70 Rev: 0 Given:

RCS average temperature is 325 °F

All control rods are fully inserted What is the current plant Mode as defined in Technical Specifications for these conditions?

A. Cold Shutdown B. Hot Shutdown C. Hot Standby D. Startup Revision 0 Facility: Waterford 3 Page 141 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Mode 5 (Cold Shutdown) is defined as Keff<.99 and tavg<200F.

B. CORRECT: Mode 4 (Hot Shutdown) is defined as Keff <.99 and Tave between 200F and 350F.

C. Incorrect. Mode 3 (Hot Standby) is defined as Keff <.99, tavg >350F.

D. Incorrect. Shutdown Bank control rods would have to be withdrawn for Mode 2 (Startup). W3 enters mode 2 when regulating groups are initially withdrawn or direct dilution has started after initial criticality.

Technical Reference(s): TS Table 1.2 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-TS02 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 142 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 3 K/A # G2.3.11 Importance Rating 3.8 K/A Statement Radiation Control: Ability to control radiation releases.

Proposed Question: RO 71 Rev: 0 The liquid release permits for a discharge of the Boric Acid Condensate Tanks or the Waste Condensate Tanks require a minimum Circulating Water Flow to provide proper dilution of the discharge. If the release permit requires a Circulating Water Flow rate of 750,000 gpm, a minimum of ____________ Circulating Water Pumps is verified running.

A. one B. two C. three D. four Revision 0 Facility: Waterford 3 Page 143 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. One Circulating water pump provides 250,000 gpm CW flow. The applicant may determine that only one circ water pump running is required to discharge a BACT or WCT.

B. Incorrect. Two Circulating water pump provides 500,000 gpm CW flow. The applicant may determine that only two circ water pumps running is required to discharge a BACT or WCT C. CORRECT: Each Circulating Water Pump has a capacity of 250,000 gpm.

Waterford 3 has four Circulating Water Pumps for a total capacity of 1,000,000 gpm.

If the release permit requires 750,000 gpm of flow, the BOP operator will verify a minimum of three Circulating Water Pumps running. The question is comprehensive because the applicant would have to know the flow rate/pump and then multiply by three. Important for the RO because the release request form asks for flow rate available, not how many circ water pumps are running.

D. Incorrect. Four Circulating Water Pumps running would meet the required flow of 750,000 gpm. The stem of the question asks for the minimum amount of CW pumps running to meet the requirement. Three CW pumps would be the minimum required.

Technical Reference(s): CE-003-514 Attachment 1 Rev. 303 (Attach if not previously provided) SD-CW page 13 Rev. 18 (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 #

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 X 10 CFR Part 55 Content: 55.41 4,13 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 144 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 3 K/A # G2.3.12 Importance Rating 3.2 K/A Statement Radiation Control: Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel-handling responsibilities, access to locked high-radiation areas, or alignment of filters, etc.

Proposed Question: RO 72 Rev: 0 In accordance with HP-001-213, Control of RCB Power Entries, which of the following area has been designated a Very High Radiation Area and entry is forbidden when the reactor is in Mode 1?

A. RCB elevator B. RCB -11 elevation C. Pressurizer Cubicle D. Reactor Vessel Annulus Revision 0 Facility: Waterford 3 Page 145 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. This RCB elevator is listed as having a high potential for exceeding dose limits but can be entered with authorization from the RP Manager. Step 5.2.1.

B. Incorrect. This area is listed as having a high potential for exceeding dose limits but can be entered with authorization from the RP Manager. Step 5.2.1.

C. Incorrect. 1This is an area known to have high radiation levels, but is not listed in HP-001-213 as being forbidden in MODE 1.

D. CORRECT: Per HP-001-213, Step 5.2.2, this is a forbidden area in MODE 1.

Technical Reference(s): HP-001-213 Rev. 305, page 7 (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. 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 9,12 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 146 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 4 K/A # G2.4.1 Importance Rating 4.6 K/A Statement Emergency Procedures / Plan: Knowledge of EOP entry conditions and immediate action steps.

Proposed Question: RO 73 Rev: 0 Per OI-038-000, EOP Operations Expectations/Guidance, the steps taken that shall be committed to memory while performing OP-902-000 Standard Post Trip Actions, are verifying Reactivity Control and verifying ____(1)____ .

If all Safety Functions are met in OP-902-000, Standard Post Trip Actions, the crew will go to _____(2)_____.

(1) (2)

A. Turbine Trip OP-902-001,Reactor Trip Recovery B. Turbine Trip Appendix 1, Diagnostic Flowchart C. Maintenance of OP-902-001,Reactor Vital Auxiliaries Trip Recovery D. Maintenance of Appendix 1, Vital Auxiliaries Diagnostic Flowchart Revision 0 Facility: Waterford 3 Page 147 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is correct. Part 2 is plausible because the older revision of the Standard Post Trip actions would allow the crew to go directly to OP-902-001 Reactor Trip Recovery, if all safety functions were met and no contingency actions were taken B. CORRECT: OI-038-000 step 5.2.1 states that steps 1 and 2 of OP-902-000 are immediate action steps and shall be committed to memory. OP-902-000, Standard Post Trip Actions, are to Verify Reactivity Control and to Verify Turbine Trip. Step 10 of OP-902-000 directs the crew to GO TO Appendix 1, Diagnostic Flowchart and diagnose to the appropriate EOP.

C. Incorrect. Part 1 is plausible because verifying the Maintenance of Vital Auxiliaries is the step that verifies the AC and DC safety busses are energized and is step 3 of OP-902-000. This step is vitally important but is not listed as one of the immediate action steps. Part 2 is plausible because the older revision of the Standard Post Trip actions would allow the crew to go directly to OP-902-001 Reactor Trip Recovery, if all safety functions were met and no contingency actions were taken.

D. Incorrect. Part 1 is plausible because verifying the Maintenance of Vital Auxiliaries is the step that verifies the AC and DC safety busses are energized and is step 3 of OP-902-000.

This step is vitally important but is not listed as one of the immediate action steps. Part 2 is correct.

Technical Reference(s): OI-038-000 step 5.2.1 Rev. 19 (Attach if not previously provided) OP-902-000 steps 1, 2, 3 and 10 Rev. 16 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 objs. 4 and 9 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 148 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 4 K/A # G2.4.9 Importance Rating 3.8 K/A Statement Emergency Procedures / Plan: Knowledge of low-power / shutdown implications in accident (e.g., loss-of-coolant accident or loss of residual heat removal) mitigation strategies.

Proposed Question: RO 74 Rev: 0 If a loss of forced flow occurred with the plant in Mode 3, the time to establish natural circulation is expected to be ________(1)_________ minutes.

Once natural circulation has been established, the T between hot leg and representative CET will be ____(2)_____ than 10°F.

(1)

(2)

A. less than 5 less B. less than 5 greater C. greater than 15 less D. greater than 15 greater Revision 0 Facility: Waterford 3 Page 149 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. TG-OP-902-005 states that it takes longer than 15 minutes to establish Natural Circulation when at low power levels. Part 2 is correct.

B. Incorrect. Parts 1 and 2 are incorrect. See Explanation C below.

C. CORRECT: OI-038-000, which applies to all EOPs, states that N/C establishes in about 5-15 minutes following a Loss of Forced Flow. However, TG-OP-902-005 states that it takes longer than 15 minutes to establish Natural Circulation when at low power levels. OP-902-005, step 19 states that the TH/CET T is less than 10°F when Natural Circulation is established.

D. Incorrect. Part 1 is correct. Part 2 is incorrect. See Explanation C above.

Technical Reference(s): OI-038-000 Rev. 19, p 22, step 5.4.15 (Attach if not previously provided) OP-902-005 Rev. 22, step 19 (including version/revision number) TG-OP-902-005 Rev. 311, step 19 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE05 EO-1, EO-6 (As available)

Question Source: Bank # RO73 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2018 NRC RO Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 150 of 152

2020 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 4 K/A # G2.4.35 Importance Rating 3.8 K/A Statement Emergency Procedures / Plan: Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

Proposed Question: RO 75 Rev: 0 Given:

The control room has been evacuated in accordance with OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown, due to a fire at CP-8

Controls have been established at LCP-43

Pressurizer pressure is 690 PSIA To continue depressurizing the RCS, the ________(1)_______ valves are used.

During the depressurization, all four SIT Isol Press Bypass Close Permissive switches located at the SIT Outlet valve breakers are bypassed. This action is required because

_____(2)_____ .

(1) (2)

A. Pressurizer Auxiliary spray SITs cannot be depressurized from LCP-43 B. Pressurizer spray SITs cannot be depressurized from LCP-43 C. Pressurizer spray SIT Outlet Valve close permissive is lower when transferred to LCP-43 D. Pressurizer Auxiliary spray SIT Outlet Valve close permissive is lower when transferred to LCP-43 Revision 0 Facility: Waterford 3 Page 151 of 152

2020 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: This question is generic because the isolation of the SIT outlet valves is required anytime a depressurization is required from LCP-43 and there are many reasons the crew may have to evacuate to LCP-43 (Fire in the cable vault room or control room, security event, toxic chemicals in the control room, etc.) The applicant must determine that there are no reactor coolant pumps running since the evacuation is due to a fire. Therefore, main spray valves cannot be used and auxiliary spray from Charging Pumps discharge is required. SIT outlet valves will not close until RCS pressure is < 415 PSIA due to an interlock. Since there are no vent valves for the SITs to lower SIT pressure during the depressurization at LCP-43, the interlock must be defeated to close them so that SITs are not injected into the RCS.

B. Incorrect. The applicant must determine that there are no reactor coolant pumps running since the evacuation is due to a fire. Therefore, main spray valves cannot be used. Part 2 is correct.

C. Incorrect. The applicant must determine that there are no reactor coolant pumps running since the evacuation is due to a fire. Therefore, main spray valves cannot be used. Part 2 is plausible because various interlocks and setpoints are removed or changed when controls are swapped to LCP-43, the setpoint for SIT outlet valve closure is not one of them.

D. Incorrect. Part 1 is correct. Part 2 is plausible because various interlocks and setpoints are removed or changed when controls are swapped to LCP-43, the setpoint for SIT outlet valve closure is not one of them.

OP-901-502 page 5, 31, 32, 34 and Attachment Technical Reference(s): 11 (Attach if not previously provided) Rev. 36 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO51 objs. 4, 21 (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 X 10 CFR Part 55 Content: 55.41 7,10 55.43 Comments:

Revision 0 Facility: Waterford 3 Page 152 of 152

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000022 AA2.02 Importance Rating 3.7 K/A Statement Ability to determine and interpret the following as they apply to Loss of Reactor Coolant Makeup: Charging pump problems Proposed Question: SRO 1 (Q76) Rev: 0 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 will 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 an available suction source and start a standby charging pump B. E1 Charging Malfunction place all charging pumps to OFF C. E3 Gas Bound Charging secure charging pump A, verify an Pumps available suction source and start a standby charging pump D. E3 Gas Bound Charging place all charging pumps to OFF Pumps Revision 0 Facility: Waterford 3 Page 1 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Entry into E1 Charging Malfunction is plausible because there is indications of a charging malfunction and it could be determined that the problem could be remedied by starting a different charging pump. This section will provide the steps to verify an available suction source and start a standby Charging Pump.

B. Incorrect. Entry into E1 Charging Malfunction is plausible because there is indications of a charging malfunction and it could be determined that the problem could be remedied by starting a different charging pump. Part 2 is correct.

C. Incorrect. Part 1 is correct. Part 2 is plausible if the applicant determines that the problem is voiding in Charging Pump A only and securing it along with starting a standby Charging pump will remedy the problem. But, The Caution is section E3 Gas Bound Charging Pumps states that standby Charging Pumps should not be started until the suction source has been recovered.

D. CORRECT: There are indications of a gas bound charging pump. The Caution is section E3 Gas Bound Charging Pumps states that standby Charging Pumps should not be started until the suction source has been recovered. The crew will be directed to place all charging pumps to OFF and enter TS 3.0.3. This is done to preclude any standby charging pumps to start on pressurizer level deviation. This question is SRO knowledge because it requires an assessment of plant conditions, a course of action in the procedure, and then selection of a procedure section at which to proceed.

Technical Reference(s): OP-901-112 pages 4, 7 and 20 Rev. 8 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PP010 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 X 10 CFR Part 55 Content: 55.41 55.43 5 Revision 0 Facility: Waterford 3 Page 2 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000025 2.2.25 Importance Rating 4.2 K/A Statement Loss of Residual Heat Removal 2.2.25 Knowledge of the bases in TS for limiting conditions for operations and safety limits.

Proposed Question: SRO 2 (Q77) Rev: 0 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 will secure High Pressure Safety Injection Pumps in accordance with the guidance in ____(2)____.

(1) (2)

A. is within OP-901-131, Shutdown Cooling Malfunction B. exceeds OP-901-131, Shutdown Cooling Malfunction C. exceeds OP-901-504, Inadvertent ESFAS Actuation D. is within OP-901-504, Inadvertent ESFAS Actuation Revision 0 Facility: Waterford 3 Page 3 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is correct. Part 2 is plausible due to the issues occurring with the operating SDC Train. OP-901-131, SDC malfunction may be entered but the guidance to secure HPSI pumps is located in the Inadvertent SIAS section of OP-901-504.

B. Incorrect. The basis (TS 3.4.8.3) for the LTOP relief valves states that for conditions where the RCS cold legs are less than 200°F, the capacity of one LTOP exceeds the transient of the simultaneous start of all three HPSI pumps, three charging pumps and all pressurizer heaters. In this case, SDC temperature is less than 200°F. OP-901-131, SDC malfunction may be entered but the guidance to secure HPSI pumps is located in the Inadvertent SIAS section of OP-901-504.

C. Incorrect. The basis (TS 3.4.8.3) for the LTOP relief valves states that for conditions where the RCS cold legs are less than 200°F, the capacity of one LTOP exceeds the transient of the simultaneous start of all three HPSI pumps, three charging pumps and all pressurizer heaters. In this case, SDC temperature is less than 200°F. Part 2 is correct.

D. CORRECT: The basis (TS 3.4.8.3) for the LTOP relief valves states that for conditions where the RCS cold legs are less than 200°F, the capacity of one LTOP exceeds the transient of the simultaneous start of all three HPSI pumps, three charging pumps and all pressurizer heaters. The guidance to secure HPSI pumps is located in the Inadvertent SIAS section of OP-901-504, Inadvertent ESFAS Acuation. This question is SRO knowledge because it requires knowledge of terminology in TS 3.4.8.3 basis.

Technical Reference(s): TS 3.4.8.3 basis (Attach if not previously provided) OP-901-504 pages 9,10 revision 10 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SDC00 obj. 1 and 6 (As available)

WLP-OPS-PPO50 obj. 3 Question Source: Bank # SRO 12 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2015 SRO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 2,5 Revision 0 Facility: Waterford 3 Page 4 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000027 AA2.02 Importance Rating 3.9 K/A Statement Ability to determine and interpret the following as they apply to a Pressurizer Pressure Control Malfunctions: Normal values for RCS pressure.

Proposed Question: SRO 3 (Q78) Rev: 1 Given:

A turbine control system malfunction has caused the turbine to runback from 100%

power. The following indications are present one minute after the turbine stops running back:

PRESSURIZER PRESSURE HI/LO alarm in

PZR Pressure is 2280 psia

Pressurizer pressure controller output is 0%

Pressurizer spray valve controller output is 0%

The CRS should direct the BOP operator to place ____(1)____ controller(s) to manual in accordance with OP-901-120, Pressurizer Pressure Control Malfunction, subsection

____(2)____.

(1) (2)

A. both the pressurizer E2, Pressurizer Pressure pressure and spray valve Controller Malfunction B. only the spray valve E2, Pressurizer Pressure Controller Malfunction C. both the pressurizer E3, Pressurizer Spray Valve pressure and spray valve Malfunction D. only the spray valve E3, Pressurizer Spray Valve Malfunction Revision 0 Facility: Waterford 3 Page 5 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: PZR pressure controller output should be high (>75%) for the given conditions.

The applicant must recognize that a 0% output from the pressure controller will input into the spray valve controller and prevent the spray controller from responding in automatic. Section E2 of OP-901-120 will direct the crew to control the spray valve controller in manual to restore pressure. The PZR pressure controller is also taken to manual because it is not working properly and is an input to the proportional heaters. Therefore, the crew will enter E2, Pressurizer Pressure Control Malfunction. This question is SRO knowledge because it requires an assessment of plant conditions, a course of action in the procedure, and then selection of a procedure section at which to proceed.

B. Incorrect. With PZR pressure at 2280 psia the output of the PZR pressure controller should be >75%. Since the PZR pressure controller output is the process signal to the spray controller, the spray valve is not opening at the correct pressure. IAW OP-901-120, the crew will control pressure with the spray valve controller. The PZR pressure controller is also taken to manual because it is not functioning properly. Part 2 is correct.

C. Incorrect. Part 1 is correct. The spray valve should be open for this RCS pressure but it is not. The applicant will have to determine that the reason the spray valve is not open for this RCS pressure is not a problem with the spray valve controller but is a problem with the pressure controller.

D. Incorrect. With PZR pressure at 2280 psia the output of the PZR pressure controller should be >75%. Since the PZR pressure controller output is the process signal to the spray controller, the spray valve is not opening at the correct pressure. IAW OP-901-120, the crew will control pressure with the spray valve controller. The PZR pressure controller is also taken to manual because it is not functioning properly. The spray valve should be open for this RCS pressure but it is not. The applicant will have to determine that the reason the spray valve is not open for this RCS pressure is not a problem with the spray valve controller but is a problem with the pressure controller.

Technical Reference(s): OP-901-120 section E2, Rev. 302 (Attach if not previously provided) SD-PLC page 28 Rev. 11 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PLC00 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 X 10 CFR Part 55 Content: 55.41 55.43 5 Revision 0 Facility: Waterford 3 Page 6 of 60

2020 NRC Exam SRO Written Exam Worksheet Comment: Sent as a Free Review question. Change "will" to "should" in stem. B does not appear plausible. Why would one go to pressurizer pressure malfunction if the problem is only in the spray valve controller? Resolution: Changed "will" to "should".

Section E2 will direct the crew to place the spray controller to manual and raise output to correct the high pressure that is occurring at the moment. This makes it plausible. This same section will also direct the crew to take the pressurizer pressure controller to manual because it is not operating properly.

Revision 0 Facility: Waterford 3 Page 7 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000057 2.4.17 Importance Rating 4.3 K/A Statement Loss of Vital AC Electrical Instrument Bus 2.4.17 Knowledge of EOP terms and definitions.

Proposed Question: SRO 4 (Q79) Rev: 0 Given:

Plant is at 100% power

Loss of a Vital Instrument Bus has occurred

Reactor Trip Breakers 1, 2, 5 and 6 have opened

CEAC 1 de-energizes The SUPS will be addressed using OP-901-312, Loss of Vital Instrument Bus, section

____(1)____.

The crew will re-energize the Power Distribution Panel (PDP) by aligning SUPS

____(2)____ to service.

(1) (2)

A. E2, Loss of PDP MB A1 B. E2 Loss of PDP MB B1 C. E3, Loss of PDP MC A1 D. E3, Loss of PDP MC B1 Revision 0 Facility: Waterford 3 Page 8 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Part 1 is correct. Part 2 is plausible because SUPS MC failing will de-energize similar equipment. On a SUPS MC failure, CEAC #2 will fail and Reactor Trip Switchgear breakers (3, 4, 7 and 8) will open.

B. CORRECT: The note on page 3 of OP-901-312 states that SUPS A1 can take the place of SUPS MA and MC and SUPS B1 can take the place of SUPS MB and MD.

The conditions given in the stem indicate a loss of SUPS MB. This question is SRO knowledge because it requires an assessment of plant conditions, a course of action in the procedure, and then selection of a procedure section at which to proceed.

C. Incorrect. The note on page 3 of OP-901-312 states that SUPS A1 can take the place of SUPS MA and MC and SUPS B1 can take the place of SUPS MB and MD.

Part 2 is plausible because SUPS MC failing will de-energize similar equipment. On a SUPS MC failure, CEAC #2 will fail and Reactor Trip Switchgear breakers (3, 4, 7 and 8) will open.

D. Incorrect. The note on page 3 of OP-901-312 states that SUPS A1 can take the place of SUPS MA and MC and SUPS B1 can take the place of SUPS MB and MD.

Part 2 is correct.

Technical Reference(s): OP-901-312 page 3, 8-10, 47-48 Rev. 319 (Attach if not previously provided)

(including version/revision number)

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 None Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 0 Facility: Waterford 3 Page 9 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000065 AA2.01 Importance Rating 2.9 K/A Statement Ability to determine and/or interpret the following as they apply to Loss of Instrument Air: Cause and effect of low-pressure instrument air Proposed Question: SRO 5 (Q80) Rev: 0 A grid transient has resulted in a reactor trip and both Emergency Diesel Generators A and B have loaded onto their respective buses.

Following the transition from OP-902-000, Standard Post Trip Actions, the CRS directs the BOP to perform (1) to restore Instrument Air pressure. If plant conditions remain unchanged and Instrument Air cannot be restored, the crew will have 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months before (2) is required.

(1) (2)

A. OP-901-511, Instrument Air use of Pressurizer Auxiliary Spray Malfunction Valve(s)

B. OP-901-511, Instrument Air gagging open of the CCW A or Malfunction CCW B header to the CCW AB header C. OP-902-009, Attachment 18-A, use of Pressurizer Auxiliary Spray Aligning Potable Water to Instrument Valve(s)

Air Compressors D. OP-902-009, Attachment 18-A, gagging open of the CCW A or Aligning Potable Water to Instrument CCW B header to the CCW AB Air Compressors header Revision 0 Facility: Waterford 3 Page 10 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Instrument Air is affected. In this scenario, the information provided supports a Loss of Offsite Power (LOOP) event is in progress. OP-901-511 does not contain the steps to align potable water to the air compressors, which is required due to TCW being loss when a LOOP occurs.

OP-902-009, Att. 18-A, contains the steps to align potable water to the air compressors. Part 2 is plausible since the use of Aux Spray is required in this scenario, but it is immediately required due to the loss of reactor coolant pumps.

B. Incorrect. Part 1 is plausible since OP-901-511 is used by the crew during an event where Instrument Air is affected. In this scenario, the information provided supports a Loss of Offsite Power (LOOP) event is in progress. OP-901-511 does not contain the steps to align potable water to the air compressors, which is required due to TCW being loss when a LOOP occurs.

OP-902-009, Att. 18-A, contains the steps to align potable water to the air compressors. Part 2 is correct.

C. Incorrect. OP-902-009, Att. 18-A, contains the steps to align potable water to the air compressors. This is required due to the loss of TCW when the LOOP occurred. Part 2 is plausible since the use of Aux Spray is required in this scenario, but it is immediately required due to the loss of reactor coolant pumps.

D. CORRECT: OP-902-009, Att. 18-A, contains the steps to align potable water to the air compressors. The applicant will determine the cause of the low IA pressure by determining there was a LOOP because the reactor is tripped (no RCPs). The LOOP means there is no TCW Pumps running which would mean that potable water must be aligned to the Instrument Air Compressors. OP-901-511 directs the crew to take local manual control of CCW A and B loop to CCW AB loop if Instrument Air is, or expected to be, loss for greater 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

Technical Reference(s): OP-901-511 step 11 and 18 Rev. 7 (Attach if not previously provided) OP-902-003 step 12.a.1 Rev. 11 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE ob. 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 X 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 0 Facility: Waterford 3 Page 11 of 60

2020 NRC Exam SRO Written Exam Worksheet Revision 0 Facility: Waterford 3 Page 12 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 0077 2.1.15 Importance Rating 3.4 K/A Statement Generator Voltage and Electric Grid Disturbance 2.1.15 Knowledge of administrative requirements for temporary management direction, such as standing orders, night orders, or operations memos, etc.

Proposed Question: SRO 6 (Q81) Rev: 0 Given:

Generator load is currently 1230 MWe and 50 MVARs Out

230KV BUS voltage is 231 KV

Frequency is 60 Hz On a Saturday morning, the Transmission Control Center (TCC) requests that MVARs be raised to 350 MVARs out and Real Load lowered to 1200 MW in order to maintain grid stability. The crew will implement OP-901-314, Degraded Grid Conditions, section

____(1)______.

The TCC requests that Waterford 3 maintain these values for the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . In accordance with EN-OP-112, Night and Standing Orders, the instruction from operations management to Operations personnel to maintain the requested values will be made via a ______(2)______.

(1) (2)

A. E1, Response to Degraded Grid Night Order B. E2, Response to Transmission Night Order Loading Relief Request C. E1, Response to Degraded Grid Standing Order D. E2, Response to Transmission Standing Order Loading Relief Request Revision 0 Facility: Waterford 3 Page 13 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Section E1, Response to Degraded Grid, provides guidance if any of the critical parameter levels for W3 offsite power supply is outside of prescribes ranges. No entry into section E1 required with the given information, 350 MVAR is still within the administrative upper limit (400 MVAR). Part 2 is correct.

B. CORRECT: OP-901-314 Section E2 covers the actions if a request is made from the TCC to reduce MW or adjust MVARs via a Transmission Loading Relief Request. The applicant must determine that the requested MVAR value is still within the boundary of the Generator Capability Curves. EN-OP-112, Night and Standing Orders, defines when a Night and Standing order is to be used. A Night order is used when an instruction to operation personnel from Operations Management is required and is a short duration (i.e. overnight or through a weekend). This questions time frame is over a weekend and fits the definition of a night order. This question is SRO knowledge because it requires an assessment of plant conditions, and then selection of a procedure section at which to proceed. Knowledge of an administrative procedure is also required.

C. Incorrect. Section E1, Response to Degraded grid, provides guidance if any of the critical parameter levels for W3 offsite power supply is outside of prescribes ranges. No entry into section E1 required with the given information, 350 MVAR is still within the administrative upper limit (400 MVAR).

D. Incorrect. Part 1 is correct. EN-OP-112, Night and Standing Orders, defines when a Night and Standing order is to be used. A Night order is used when an instruction to operation personnel from Operations Management is required and is a short duration (i.e. overnight or through a weekend). This questions time frame is over a weekend and fits the definition of a night order.

Technical Reference(s): OP-901-314 page 6 and section E2 Rev. 5 (Attach if not previously provided) EN-OP-112 page 5 Rev. 3 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO30 obj. 3 (As available)

WLP-OPS-PPA00 obj. 3 Question Source: Bank #

Modified Bank # SRO81 (Note changes or attach parent)

New Question History: Last NRC Exam 2018 NRC SRO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Revision 0 Facility: Waterford 3 Page 14 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 00001 2.1.28 Importance Rating 4.1 K/A Statement Continuous Rod Withdrawal 2.1.28 Knowledge of the purpose and function of major system components and controls.

Proposed Question: SRO 7 (Q82) Rev: 0 Given:

Plant startup is in progress

Current reactor power is 8X10-5%

During withdrawal of a Regulating Group, the control rods continue to withdraw after the shim switch is released.

The automatic trip designed to terminate this event is the _____(1)_____ trip. The CRS will direct the ATC to place the _____(2)______ in accordance with OP-901-102, CEA or CEDMCS Malfunction.

(1) (2)

A. Variable Overpower CEDMCS Mode Select switch to OFF B. Variable Overpower CEA Manual Shim switch to insert C. Logarithmic Power Level-High CEDMCS Mode Select switch to OFF D. Logarithmic Power Level-High CEA Manual Shim switch to insert Revision 0 Facility: Waterford 3 Page 15 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Part 1 is incorrect but plausible since the Variable Overpower Trip (VOPT) purpose is to provide protection against low power CEA bank withdrawal. But, as described in the CPC System Description, the set point for a reactor trip has a floor of 30% power.

The Log power trip would already have tripped the reactor at .257% power if the trip is still in service, which it is. Part 2 is correct.

B. Incorrect. Part 1 is incorrect but plausible since the Variable Overpower Trip (VOPT) purpose is to provide protection against low power CEA bank withdrawal. But, as described in the CPC System Description, the set point for a reactor trip has a floor of 30% power.

The Log power trip would already have tripped the reactor at .257% power if the trip is still in service, which it is. Part 2 is incorrect but plausible since this action could be directed if the operator had manually withdrawn CEAs past a desired height.

C. CORRECT: Technical Specification bases credits the Logarithmic Power Level-High trip protecting the fuel clad and RCS boundary during a reactivity excursion from a shutdown condition. The TS basis also indicates that the Log power trip can be bypassed at 1X10-4%

power. The present power is given in the stem and is not quite at the point which the high log power trip will be removed from service. Placing the CEDMCS Mode Select switch to off should stop all CEA movement and is directed to be performed in OP-901-102, CEA or CEDMCS Malfunction. This question is SRO only because it requires knowledge of TS basis to answer the question (purpose of the log power trip and the set point for manual removal of the trip).

D. Incorrect. Part 1 is correct. Part 2 is incorrect but plausible since this action could be directed if the operator had manually withdrawn CEAs past a desired height.

Technical Reference(s): SD-CPC page 36 and Figure 16 Rev. 18 (Attach if not previously provided) Tech Spec basis B2-3 and B2-6 (including version/revision number) OP-010-003 page 81 Rev. 351 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPS00 obj. 4 (As available)

Question Source: Bank #

(Note changes or attach Modified Bank # parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Revision 0 Facility: Waterford 3 Page 16 of 60

2020 NRC Exam SRO Written Exam Worksheet Comments:

Revision 0 Facility: Waterford 3 Page 17 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000028 AA2.11 Importance Rating 3.6 K/A Statement 000028 Pressurizer (PZR) Level Control Malfunction AA2.11 - Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions: Leak in PZR Proposed Question: SRO 8 (Q83) Rev: 0 Given:

Plant at 100% power

PZR Level Channel X is selected for service

PZR level indicator RC-ILI-110X indicates 55.6% and steady

PZR level indicator RC-ILI-110Y indicates 54% and slowly lowering

Letdown flow is slowly rising These conditions are caused by a reference leg leak in ____(1)____ .

The crew will enter OP-901-110, Pressurizer Level Control Malfunction, section

_____(2)_____ .

(1) (2)

A. RC-ILI-110X E3 Pressurizer Level Controller Malfunction B. RC-ILI-110X E1 Pressurizer Level Control Channel Malfunction C. RC-ILI-110Y E1 Pressurizer Level Control Channel Malfunction D. RC-ILI-110Y E3 Pressurizer Level Controller Malfunction Revision 0 Facility: Waterford 3 Page 18 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Part 1 is correct. Section E3 Pressurizer Level Controller Malfunction is plausible because both the level setpoint and/or a degrading level control channel will affect the proper operation of the level controller as seen in this question. In this case, crew needs to select operable level control channel (Y), and that guidance is found in OP-901-110 section E1.

B. CORRECT: CR-WF3-2012-3047. Actual OE at W3 from June 24, 2012. A reference leg leak in Channel X will cause indicated level on Channel X to fail high (wet reference leg). Since channel X is the controlling channel it will raise letdown flow to keep pressurizer level at 55.6%. This failure affects a level control channel and OP-901-110 section E1 would provide the guidance to swap to the Y channel. This question is SRO knowledge because it requires an assessment of plant conditions, troubleshoot the failure, then select a procedure section at which to proceed.

C. Incorrect. Channel Y could be determined to be the failed channel because it is deviating from setpoint. This instrument is lowering because actual pressurizer level is lowering.

Plausible because it was confusing to the shift and took an FMA team to figure it out. The crew could determine that it is a setpoint malfunction if they do not know that the setpoint supposed to be 55.6% at 100% power.

D. Incorrect. Channel Y looks like the failed channel because it is deviating from setpoint. This instrument is lowering because actual pressurizer level is lowering. Plausible because it was confusing to shift and took an FMA team to figure it out. Section E3 Pressurizer Level Controller Malfunction is plausible because both level setpoint and/or a degrading level control channel could affect the proper operation of the level controller. But, crew needs to select operable level control channel (Y), and that guidance is found in OP-901-110 section E1 Technical Reference(s): OP-901-110 pages 6, 7 and 11 Rev. 11 (Attach if not previously provided) WLP-OPS-PLC00, slides 69-71 Rev. 22 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PLC00 obj. 9 (As available)

Question Source: Bank # SRO83 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2018 NRC SRO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Revision 0 Facility: Waterford 3 Page 19 of 60

2020 NRC Exam SRO Written Exam Worksheet Revision 0 Facility: Waterford 3 Page 20 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000059 2.3.6 Importance Rating 3.8 K/A Statement Accidental Liquid Radwaste Release 2.3.6 Ability to approve release permits.

Proposed Question: SRO 9 (Q84) Rev: 0 Given:

A discharge of Waste Condensate Tank A is ready to be performed in accordance with OP-007-004, Liquid Waste Management System The CRS will ensure that the channel check is performed satisfactorily for the Liquid Waste Management (LWM) Radiation Monitor by verifying the LWM ____(1)____.

The channel check is required to be performed ____(2)____ to service.

(1) (2)

A. discharge flow recorder deflects prior to each release upscale to provide discharge flow indication B. discharge flow recorder deflects quarterly upscale to provide discharge flow indication C. Radiation Monitor passes a quarterly source check by depressing the check source pushbutton on the RM-11 D. Radiation Monitor passes a prior to each release source check by depressing the check source pushbutton on the RM-11 Revision 0 Facility: Waterford 3 Page 21 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: The note prior to step 6.10.13 states that the successful performance of step 6.10.13 satisfies TRM Table 4.3-8, Channel Check. Step 6.10.13 states that the channel check is performed satisfactorily for the Liquid Waste Management (LWM)

Radiation Monitor by verifying the LWM discharge flow recorder deflects upscale to provide discharge flow indication. TRM Table 4.3-8 requires the Channel Check to be performed prior to each release. This question is SRO because the applicant must know the surveillance requirement and frequency for the LWM Radiation Monitor Tech Spec 3.3.3.10. This question meets the K/A because the verification of a channel check is an initial on the release permit and is required to close the release permit.

B. Part 1 is correct. Part 2 is plausible because the Radiation Monitor functional test is required every quarter per TRM Table 4.3-8. The applicant could assume this test is part of the functional test.

C. Part 1 is plausible because a source check must be performed prior to every release in accordance with OP-007-004 and this check is also required by TRM Table 4.3-8.

The applicant could determine that meeting the channel check is verifying that a radiation monitor passes the source check. Part 2 is plausible because the Radiation Monitor functional test is required every quarter per TRM Table 4.3-8. The applicant could assume this test is part of the functional test.

D. Part 1 is plausible because a source check must be performed prior to every release in accordance with OP-007-004 and this check is also required by TRM Table 4.3-8.

The applicant could determine that meeting the channel check is verifying that a radiation monitor passes the source check. Part 2 is correct.

OP-007-004 step 6.10.13 and the note preceding Technical Reference(s): it. Rev. 317 (Attach if not previously provided) TRM Table 4.3-8 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-LWM00 obj. 7 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 Revision 0 Facility: Waterford 3 Page 22 of 60

2020 NRC Exam SRO Written Exam Worksheet 55.43 2,4 Comments:

Revision 0 Facility: Waterford 3 Page 23 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # CE E09 EA2.1 Importance Rating 4.4 K/A Statement Ability to determine and interpret the following as they apply to the (Functional Recovery): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Proposed Question: SRO 10 (Q85) Rev: 0 Given:

Reactor was manually tripped due to a Main Steam Line Break inside of containment coincident with a Steam Generator Tube Rupture

Steam Generator 1 pressure is 500 psia and lowering

Main Steam Line 1 and Blowdown Radiation Monitors are in alarm

RCS pressure is 1300 PSIA and lowering

Pressurizer level is 0%

Containment Spray Pump A is tagged out and Containment Spray Pump B flow is 1500 gpm

OP-902-000, Standard Post Trip Actions have been completed and the crew has diagnosed to OP-902-008, Functional Recovery Procedure During prioritization of Safety Functions, the crew will prioritize A. Containment Isolation as priority #1 and RCS Inventory Control as priority #2.

B. Containment Temperature and Pressure Control as priority #1 and RCS Inventory Control as priority #2.

C. Containment Temperature and Pressure Control as priority #1 and Containment Isolation as priority #2.

D. Containment Isolation as priority #1 and Containment Temperature and Pressure Control as priority #2.

Revision 0 Facility: Waterford 3 Page 24 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. The Containment Isolation (CI) Safety Function is priority #1 due to Steam Generator #1 with high radiation alarms but not isolated yet. RCS Inventory Control as priority

2 is plausible because it would be priority #2 if determined that the Containment Temperature and Pressure Control (CTPC) safety function is met. The CTPC safety function is not met because there is not at least one CS pump delivering 1750 gpm flow.

B. Incorrect. Plausible because the Containment Temperature and Pressure Control safety function would be Priority #1 and the Reactivity Control Safety Function would be priority #2 if determined that the Containment Isolation safety function is met. CI is not met because the SG has not been isolated IAW the EOPs.

C. Incorrect. This answer is plausible if determined that the CTPC safety function and the Containment Isolation safety function are both not met but determined that the CTPC safety function is a higher priority than the CI safety function.

D. CORRECT: The CRS must determine that the Containment Isolation Safety Function is not met. OI-038-000 step 5.4.55 states that the containment isolation safety function should be considered NOT MET if secondary activity exists and all EOP steps for isolating the SG have not been completed. An MSIS is not adequate for meeting this safety function. Therefore, the given conditions indicate a MSIS has occurred but the steps for isolating the SG have not been performed since the crew is just entering OP-902-008. Containment Temperature and Pressure Control is not met because there is not at least one CS pump delivering 1750 gpm flow. Containment Isolation is the higher prioritized safety function. This question is SRO knowledge because it requires an assessment of plant conditions and then the selection of a procedure section at which to proceed.

Technical Reference(s): OI-038-000 step 5.4.55 Rev. 19 (Attach if not previously provided) OP-902-008 pages 13, 33-36 Rev. 30 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE08 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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 5 Revision 0 Facility: Waterford 3 Page 25 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 004 A2.18 Importance Rating 3.1 K/A Statement 004 Chemical and Volume Control, A2.15: Ability to (a) predict the impacts of the following malfunctions on the Chemical and Volume Control System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: High VCT level.

Proposed Question: SRO 11 (Q86) Rev: 0 Given:

Plant is at 100% power

Annunciator VCT LEVEL HI/LO is received

The ATC operator reports VCT level indicates 100% on the PMC and 60% on the indication at CP-4

The ATC also reports the annunciator response procedure lists CVC-ILT-0227 as the source instrument for the locked in alarm The CRS will first direct the crew to _____(1)_____ in accordance with _____(2)_____.

(1) (2)

A. simultaneously secure all OP-901-112, Charging or Letdown Charging Pumps and close Malfunction, Section E2 Letdown the Letdown Stop Valve Malfunction (CVC-101)

B. simultaneously secure all OP-901-113, Volume Control Tank Charging Pumps and close Makeup Control Malfunction, the Letdown Stop Valve Section E0 General (CVC-101)

C. align the VCT Inlet Bypass OP-901-113, Volume Control Tank Valve (CVC-169) to the VCT Makeup Control Malfunction, position Section E0 General D. align the VCT Inlet/Bypass OP-901-112, Charging or Letdown Valve (CVC-169) to the VCT Malfunction, Section E2 Letdown position Malfunction Revision 0 Facility: Waterford 3 Page 26 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Part 1 is plausible because VCT level instrument CVC-ILT-0227 will fail the VCT Inlet/Bypass Valve (CVC-169) to the BMS position thereby diverting Letdown flow from the VCT to the Hold Up Tanks. If VCT-169 could not be overridden to the VCT position there would be a loss of the RCS to the Hold Up Tanks. Therefore, the crew would be required to isolate letdown and close CVC-101. This is actually the actions to be taken if CVC-ILT-0227 were to fail low. Part 2 is plausible because the issue is letdown diverting the VCT which is a letdown malfunction but the guidance is found in OP-901-113 not the Letdown Malfunction section of OP-901-112.

B. Incorrect. Part 1 is plausible because VCT level instrument CVC-ILT-0227 will fail the VCT Inlet/Bypass Valve (CVC-169) to the BMS position thereby diverting Letdown flow from the VCT to the Hold Up Tanks. If VCT-169 could not be overridden to the VCT position there would be a loss of the RCS to the Hold Up Tanks. Therefore, the crew would be required to isolate letdown and close CVC-101. This is actually the actions to be taken if CVC-ILT-0227 were to fail low. Part 2 is correct.

C. CORRECT: The applicant will determine that the VCT level instrument is failed high. VCT level instrument CVC-ILT-0227 will fail the VCT Inlet/Bypass Valve (CVC-169) to the BMS position thereby diverting Letdown flow from the VCT to the Hold Up Tanks. The applicant must be aware that this signal to CVC-169 can be overridden and CVC-169 is aligned to the VCT position using the control switch.

D. Incorrect. Part 1 is correct. Part 2 is plausible because the issue is letdown diverting the VCT which is a letdown malfunction but the guidance is found in OP-901-113 not the Letdown Malfunction section of OP-901-112.

Technical Reference(s): OP-901-113 pages 3, 4 and 6 Rev. 305 (Attach if not previously provided) OP-901-112 page 1, Rev. 8 (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 X 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 0 Facility: Waterford 3 Page 27 of 60

2020 NRC Exam SRO Written Exam Worksheet Revision 0 Facility: Waterford 3 Page 28 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 007 2.1.9 Importance Rating 4.5 K/A Statement Component Cooling Water 2.1.9 Ability to direct personnel activities inside the control room.

Proposed Question: SRO 12 (Q87) Rev: 0 Given:

Plant is operating at 100% power

Component Cooling Water Pump AB is replacing CCW pump A

The following Annunciators in alarm:

o CCW Surge Tank Level LO-LO on Panel M & N

CCW Surge Tank A level is 0%.

CCW Surge Tank B level lowered to 15% but is being restored via the CCW Makeup Pumps

The crew has entered OP-901-510, Component Cooling Water System Malfunction Two minutes into the event, the CRS will first direct the crew to ________.

A. pull Emergency Diesel Generator A Overspeed Trip device and verify ACCW Pump A operating in accordance with OP-901-510 section E1, System Leakage B. restore flow to the CCW AB loop then check CCW Pump AB suction and discharge valve for leaks in accordance with OP-901-510 section E1, System Leakage C. trip the reactor, secure Reactor Coolant Pumps and go to OP-902-000, Standard Post Trip Actions D. trip the reactor, secure Reactor Coolant Pumps and perform OP-902-000, Standard Post Trip Actions and OP-901-510 section E1, System Leakage concurrently Revision 0 Facility: Waterford 3 Page 29 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Plausible because these would be the first steps taken (step 15 of section E1) if the applicant determined that the leak is isolated to the CCW A safety header which would be the case if CCW pump AB was not replacing CCW pump A. When CCW AB is replacing CCW pump A the applicable suction and discharge cross-connect valves are failed open (note on step 13 of section E1), therefore, it cannot be determined that the leak is confined to CCW A safety header.

B. CORRECT: The applicant must determine that the isolations to the CCW AB header on both trains have went closed isolating CCW to the Reactor Coolant Pumps because CCW surge tank A and B went below 16%. CC-200B and CC-563 can be overridden to open to restore flow to the AB header (RCPs). Since CCW pump AB is replacing CCW pump A, the suction and discharge cross-connects are failed open and must be checked locally to verify no leaks (step 13 of section E1)

C. Incorrect. Plausible if the applicant determines that the leak is in the CCW AB loop (step 18 of section E1) due to CCW Pump AB replacing CCW A or if the applicant does not realize that CC-200B and CC-563 can be overridden to open to restore flow to the Reactor Coolant Pumps (step 1 of section E1). GO TO in Waterford 3 procedures means to leave the current procedure and enter the procedure that is directed. Leaning OP-901-510 is plausible if the applicant determines that guidance will be provided in the EOPS to combat the leak in CCW in which there is no guidance.

D. Incorrect. Plausible if the applicant determines that the leak is in the CCW AB loop (step 18 of section E1) due to CCW Pump AB replacing CCW A or if the applicant does not realize that CC-200B and CC-563 can be overridden to open to restore flow to the Reactor Coolant Pumps (step 1 of section E1).

Technical Reference(s): OP-901-510 pages 6, 9, 11-12, 18-19, 21, 25 Rev. 304 (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 X 10 CFR Part 55 Content: 55.41 55.43 5 Revision 0 Facility: Waterford 3 Page 30 of 60

2020 NRC Exam SRO Written Exam Worksheet Revision 0 Facility: Waterford 3 Page 31 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 026 A2.07 Importance Rating 3.9 K/A Statement Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of containment spray pump suction when in recirculation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded cavitation, voiding), or sump level below cutoff (interlock) limit.

Proposed Question: SRO 13 (Q88) Rev: 1 Given:

A large break LOCA has occurred three hours ago

Crew is performing OP-902-002, Loss of Coolant Accident Recovery

Recirculation Actuation Signal has occurred, and the required actions have been taken

RCS is 42°F subcooled and stable

Pressurizer level has been restored and indicates 29%

QSPDS indicates reactor vessel plenum level is full

BOP operator notes that HPSI A and B pump flows and discharge pressures have started to indicate low and erratic The conditions given indicate _____(1)_____. The CRS should _____(2)_____.

(1) (2)

A. the SI Sump Strainers are starting to perform Appendix 15 Hot and Cold Leg clog from debris collection Injection B. the SI Sump Strainers are starting to secure one HPSI and CS pump then clog from debris collection verify Attachment 2-E HPSI Flow Curve is met C. core flow blockage is starting to secure one HPSI and CS pump then occur due to boron precipitation verify Attachment 2-E HPSI Flow Curve is met D. core flow blockage is starting to perform Appendix 15 Hot and Cold Leg occur due to boron precipitation Injection Revision 0 Facility: Waterford 3 Page 32 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect: Part 1 is correct. Step 53 of OP-902-002 will direct the crew to initiate hot and cold leg injection between two and three hours of the event if certain conditions are not met. The applicant must determine that the conditions are met and Hot and Cold leg injection is not required.

B. CORRECT: Step 49 of OP-902-002 (LOCA recovery procedure) directs the crew to secure one HPSI pump and one CS pump if HPSI pump flows or CS flows are indicating low or erratic. The tech guide for this step in OP-902-002 states that the given conditions are indicative of a loss of suction to the HPSI and CS pumps due to possible sump blockage. The step directs the crew to secure one HPSI and one CS Pump even though only HPSI flow is indicating low and erratic because both pumps will have a common suction following a RAS.

(this is what meets the predict the impact on CS in the K/A). This question is SRO knowledge because it requires an assessment of plant conditions, a course of action in the procedure, and then selection of a procedure section at which to proceed C. Incorrect: Part 1 is plausible because HPSI flow and discharge pressure would be affected by core blockage due to boron precipitation. But, the indications given in the stem do not support core blockage occurring. Part 2 is correct.

D. Incorrect: Part 1 is plausible because HPSI flow and discharge pressure would be affected by core blockage due to boron precipitation. But, the indications given in the stem do not support core blockage occurring. Step 53 of OP-902-002 will direct the crew to initiate hot and cold leg injection between two and three hours of the event if certain conditions are not met. The applicant must determine that the conditions are met and Hot and Cold leg injection is not required.

Technical Reference(s): OP-902-002 step 49 and step 53 revision 21 (Attach if not previously provided) TGOP-902-002 page 112 Revision 20 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE02 obj. 17 (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 X 10 CFR Part 55 Content: 55.41 55.43 5 Comments: Sent as Free Review question. Change "will" to "should" in stem. Add "the" before "required" in the third bullet. On the seventh bullet, are both temperature and pressure steady? In the last bullet add "operator" after "BOP" or writeout balance of plant operator. In answer explanation B, edit "an RAS" to be "a RAS." Resolution: Changed "will" to "should". Added Revision 0 Facility: Waterford 3 Page 33 of 60

2020 NRC Exam SRO Written Exam Worksheet "the" before "required" in the third bullet. On the seventh bullet, changed to state "and both are steady". In the last bullet, added "operator" after BOP. Changed this for the rest of the questions also. In answer explanation B, edited "an RAS" to "a RAS".

Revision 0 Facility: Waterford 3 Page 34 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 062 2.2.21 Importance Rating 4.1 K/A Statement A.C. Electrical Distribution 2.2.21 Knowledge of pre- and post-maintenance operability requirements.

Proposed Question: SRO 14 (Q89) Rev: 1 Given:

Breaker Maintenance in the Waterford 3 switchyard is to performed that will render B train Offsite Power A.C. Circuit inoperable Before breaker maintenance is to be performed, the crew should verify Train A Offsite Power A.C. circuit operable and meeting the surveillance requirements of TS 4.8.1.1.1a by performing _____(1)_____. Once the B train Offsite Power A.C. Circuit is declared inoperable, the crew should perform this surveillance requirement within one hour and every _____(2)_____ hours thereafter.

(1) (2)

A. OP-903-066, Electrical Breaker eight Alignment Check B. OP-903-066, Electrical Breaker twelve Alignment Check C. OP-903-001, Attachment 11.14, eight Electrical Distribution Operability Check D. OP-903-001, Attachment 11.14, twelve Electrical Distribution Operability Check Revision 0 Facility: Waterford 3 Page 35 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: TS 3.8.1.1 action a directs the crew to perform TS Surveillance requirement 4.8.1.1.1a within one hour and every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter if one train of offsite power is inoperable. Step 1.2 of OP-903-066 states that successful completion of this procedure demonstrates compliance with Technical Specification Surveillance requirement 4.8.1.1.1.a.

This question is SRO knowledge because it requires application of TS surveillance requirements (section 4).

B. Incorrect. Part 1 is correct. Most Waterford 3 surveillance requirements are every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , but the OP-903-066 is performed every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months C. Incorrect. OP-903-001 Attachment 11.14, Electrical Distribution Operability Check, is performed once every 7 days to meet the requirements of TS surveillance 4.8.1.1.1a and other TS surveillances. It is not the surveillance requirement to be performed as directed by TS 3.8.1.1 action a to verify the remaining offsite train is operable. Part 2 is correct.

D. Incorrect. OP-903-001 Attachment 11.14, Electrical Distribution Operability Check, is performed once every 7 days to meet the requirements of TS surveillance 4.8.1.1.1a and other TS surveillances. It is not the surveillance requirement to be performed as directed by TS 3.8.1.1 action a to verify the remaining offsite train is operable. Most Waterford 3 surveillance requirements are every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , but the OP-903-066 is performed every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Technical Reference(s): TS 3.8.1.1 action a (Attach if not previously provided) OP-903-066 page 6 step 1.2 Rev. 304 (including version/revision number) OP-903-001 page 95 Rev. 83 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-ED00 obj. 9 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Comments: Sent as Free Review. Change will to should.

Resolution: Changed will to should.

Revision 0 Facility: Waterford 3 Page 36 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 064 A2.15 Importance Rating 3.1 K/A Statement Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Water buildup in cyclinders.

Proposed Question: SRO 15 (Q90) Rev: 0 Given:

Emergency Diesel Generator (EDG) A is inoperable due to unplanned maintenance because of water in the cylinders from the fuel oil lines

The Temporary Emergency Diesel (TED) Generator is verified available and aligned as a backup for EDG A at the time EDG A is declared inoperable

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months from when EDG A first became inoperable, the Temporary Emergency Diesel (TED) Generator becomes unavailable and cannot be restored Per TS 3.8.1.1 basis, from the time the Temporary Emergency Diesel (TED) Generator becomes unavailable, the time limit for restoring Emergency Diesel Generator A to service is ___(1)___ hours.

Before performing surveillance testing to restore EDG A operability, the fuel oil will be verified free of water by a ___(1)___ when performing pre-startup checks per OP-009-002, Emergency Diesel Generator.

(1) (2)

A. 42 visual sample of fuel oil taken at the EDG A feed (day) tank B. 42 chemistry sample taken at fuel oil storage tank (FOST) A C. 72 chemistry sample taken at fuel oil storage tank (FOST) A D. 72 visual sample of fuel oil taken at the EDG A feed (day) tank Revision 0 Facility: Waterford 3 Page 37 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Per TS 3.8.1.1 basis, If the TEDG becomes unavailable during the 10 day outage time and cannot be restored to available status, the EDG AOT reverts back to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months begins with the discovery of the TEDG unavailability. 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months is plausible if the applicant determines that the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months reverts back to when EDG A was made inoperable.

Part 2 is correct.

B. Incorrect. Per TS 3.8.1.1 basis, If the TEDG becomes unavailable during the 10 day outage time and cannot be restored to available status, the EDG AOT reverts back to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months begins with the discovery of the TEDG unavailability. 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months is plausible if the applicant determines that the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months reverts back to when EDG A was made inoperable.

Part 2 is plausible because FOST A stores the fuel for EDG A use. FOST A is the fuel oil supply for EDG A feed tank. Also, it is customary at W3 that Chemistry takes samples.

C. Incorrect. Part 1 is correct. Part 2 is plausible because FOST A stores the fuel for EDG A use. FOST A is the fuel oil supply for EDG A feed tank. Also, it is customary at W3 that Chemistry takes samples.

D. CORRECT: Per TS 3.8.1.1 basis, If the TEDG becomes unavailable during the 10 day outage time and cannot be restored to available status, the EDG AOT reverts back to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months begins with the discovery of the TEDG unavailability. OP-902-009 step 6.1.4 has the crew obtain a fuel oil sample from the EDG A feed tank drain valve and visually check it for water.

Technical Reference(s): TS 3.8.1.1 basis (Attach if not previously provided) OP-009-002 pages 14 and 15 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-EDG00 objs. 7 and 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 X 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 0 Facility: Waterford 3 Page 38 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 011 A2.04 Importance Rating 3.7 K/A Statement Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of one, two, or three charging pumps.

Proposed Question: SRO 16 (Q91) Rev: 1 Given:

Plant is at 100% power when a loss of all Charging Pumps has occurred

Attempts to restart a charging pump are unsuccessful

The crew has entered OP-901-112, Charging or Letdown Malfunction The crew will verify letdown flow ___(1)___. If pressurizer level falls below the minimum pressurizer level for operation curve, the crew will perform actions in accordance with

________(2)_______.

(1) (2)

A. isolates the emergency operating procedures only B. isolates OP-901-112 subsection E1, Charging Malfunction concurrent with the emergency operating procedures C. goes to minimum flow OP-901-112 subsection E1, Charging Malfunction concurrent with the emergency operating procedures D. goes to minimum flow the emergency operating procedures only Revision 0 Facility: Waterford 3 Page 39 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Part 1 is correct. The steps for depressurizing and aligning HPSI flow to the RCS is not located in the EOPs, it is located in OP-901-112. Since no charging flow can be established and Pressurizer level has lowered below the minimum required, the crew will trip the reactor and follow the guidance in both the EOP and AOP. Answer A is not a subset of Answer B because Answer A states that the crew will enter the Emergency Operating Procedures only.

B. CORRECT: Letdown Stop Valve (CVC-101) will close on High Regen HX outlet temp if RCS Temp is > 470°F. Charging is the cooling medium for the RHX and it has been lost. RCS temperature is greater than 470°F because Rx power is 100%. Per OP-901-112 subsection E1, if charging cannot be restored, the crew will be required to trip the reactor and lower RCS pressure to less than HPSI shutoff head and inject via a HPSI pump. The crew must enter the Emergency operating procedures whenever the reactor is tripped. The steps for aligning HPSI flow to the RCS is not located in the EOPs, therefore OP-901-112 directs the crew to perform OP-901-112 and the EOPs concurrently. This question is SRO knowledge because it requires an assessment of plant conditions, a course of action in the procedure, and then selection of a procedure section at which to proceed.

C. Incorrect. Letdown flow going to minimum is plausible because on a loss of all charging the input into the pressurizer goes to zero therefore the output of the pressurizer (letdown) would go to minimum (28 gpm) if letdown did not isolate. Also, upon a reactor trip, letdown flow will always go to minimum due to the resultant RCS cooldown. Part 2 is correct.

D. Incorrect. Letdown flow going to minimum is plausible because on a loss of all charging the input into the pressurizer goes to zero therefore the output of the pressurizer (letdown) would go to minimum (28 gpm) if letdown did not isolate. Also, upon a reactor trip, letdown flow will always go to minimum due to the resultant RCS cooldown. The steps for depressurizing and aligning HPSI flow to the RCS is not located in the EOPs, it is located in OP-901-112. Since no charging flow can be established and Pressurizer level has lowered below the minimum required, the crew will trip the reactor and follow the guidance in both the EOP and AOP.

Technical Reference(s): OP-901-112 section E1 step 2 Rev. 8 (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 X 10 CFR Part 55 Content: 55.41 55.43 5 Revision 0 Facility: Waterford 3 Page 40 of 60

2020 NRC Exam SRO Written Exam Worksheet Comments: Question sent as Free Review. C and D do not appear credible. Do not see how one might think letdown would go to "minimum flow" when there is zero charging pump flow. There is no explanation as to how this could be plausible. Answer A is a subset of Answer B and partially correct.

Resolution: (Letdown flow going to minimum is plausible because on a loss of all charging the input into the pressurizer goes to zero therefore the output of the pressurizer (letdown) would go to minimum (28 gpm) if letdown did not isolate on high regen HX outlet temperature. Also, upon a reactor trip, letdown flow will always go to minimum due to the resultant cooldown. Answer A is not a subset of Answer B because answer A says Emergency Operating procedures "only". This would imply that the offnormal procedure is not used. The offnormal procedure must be used to align charging to HPSI. Added the above verbiage to the explanations to explain why "minimum flow" is plausible and why there is not a substep issue between A and B answers.)

Revision 0 Facility: Waterford 3 Page 41 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 033 2.4.8 Importance Rating 4.5 K/A Statement Spent Fuel Pool Cooling 2.4.8 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

Proposed Question: SRO 17 (Q92) Rev: 0 Given:

A Loss of Offsite Power has occurred and the crew has entered OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery Procedure

Emergency Diesel Generator A has tripped on overspeed

Emergency Diesel Generator B sequencer has timed out The CRS will direct the crew to energize Fuel Pool Cooling Pump B in preparation for a start by ___(1)___ and then closing the breaker for Fuel Pool Cooling Pump B in accordance with the applicable attachment located in ___(2)___.

(1) (2)

A. closing the safety to non-safety tie at OP-901-513, Spent Fuel Pool the 314B bus Cooling Malfunction B. closing the safety to non-safety tie at OP-902-009, Standard the 314B bus Appendices C. closing the feeder breaker for the 314B OP-901-513, Spent Fuel Pool bus Cooling Malfunction D. Closing the feeder breaker for the 314B OP-902-009, Standard bus Appendices Revision 0 Facility: Waterford 3 Page 42 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: OP-902-003 step 25 will direct the crew to OP-901-513 if there is an issue with Spent Fuel Pool Cooling. OP-901-513 step 9 will direct the crew to perform Attachment 4, Restore Fuel Pool Pumps to operation via EDG. Attachment 4 of OP-901-513 will provide the guidance to the operator for re-energizing Fuel Pool Pump B by energizing the non-essential portion of MCC-314B.

B. Part 1 is correct. Part 2 is plausible because the crew will be in the Emergency Operating Procedures and it is custom to use an attachment located in the EOP. The attachment in OP-902-009 that is plausible is Attachment 12, Electrical Restoration. OP-902-003 directs the crew to this attachment but the guidance for re-energizing the non-safety portion of the 314 busses cannot be found here.

C. Part 1 is plausible because some 480V busses do not re-energize on the Emergency Diesel Generator. If this was the case for the 314B bus, then the feeder breaker would have to be closed locally. The 314B essential portion of the MCC is powered following sequencing of EDG B. The non-essential portion must be energized manually at the MCC. Part 2 is correct.

D. Part 1 is plausible because some 480V busses do not re-energize on the Emergency Diesel Generator. If this was the case for the 314B bus, then the feeder breaker would have to be closed locally. The 314B essential portion of the MCC is powered following sequencing of EDG B. The non-essential portion must be energized manually at the MCC. Part 2 is plausible because the crew will be in the Emergency Operating Procedures and it is custom to use an attachment located in the EOP. The attachment in OP-902-009 that is plausible is Attachment 12, Electrical Restoration. OP-902-003 directs the crew to this attachment but the guidance for re-energizing the non-safety portion of the 314 busses cannot be found here.

Technical Reference(s): OP-902-003 steps 20, 25 Rev. 11 (Attach if not previously provided) OP-901-513 step 9 and Attachment 4 Rev. 25 (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 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments Revision 0 Facility: Waterford 3 Page 43 of 60

2020 NRC Exam SRO Written Exam Worksheet Revision 0 Facility: Waterford 3 Page 44 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 068 A2.04 Importance Rating 3.3 K/A Statement Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic isolation Proposed Question: SRO 18 (Q93) Rev: 0 Given:

Boric Acid Condensate Tank B is being discharged to the Circ Water system.

The following annunciators are observed in the Control Room:

o BAC CONDENSATE DISCH ACTIVITY HI annunciator in alarm on CP-4 o EFFLUENT RAD MONITORING SYS ACTIVITY HI-HI annunciator in alarm on CP-36 NOTE:

BM-547, Boron Management Discharge to Circulating Water Auto Isolation Valve

BM-549, Boron Management Discharge to Circulating Water Flow Control Valve Per OP-901-412, Liquid Waste Discharge High Radiation, ____(1)____ will close to terminate the Boron Management discharge.

If the Boron Radiation Monitor is determined to be inoperable, _____(2)_____ is a required action per TRM 3.3.3.10, Radioactive Liquid Effluent, to release a Boric Acid Condensate Tank with its associated Radiation Monitor inoperable.

(1) (2)

A. BM-547 only the flow rate is estimated every four hours during the release B. BM-547 only at least two independent samples are analyzed C. BM-547 and BM-549 the flow rate is estimated every four hours during the release D. BM-547 and BM-549 at least two independent samples are analyzed Revision 0 Facility: Waterford 3 Page 45 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is plausible if it is determined that the isolation valve and not the flow control valve isolates on a Hi-Rad signal from the BM Rad Monitor. Part 2 is plausible because estimating flow every fours is an action for TRM 3.3.3.10 (action 1b) but it is for an inoperable flow instrument.

B. Incorrect. Part 1 is plausible if it is determined that the isolation valve and not the flow control valve isolates on a Hi-Rad signal from the BM Rad Monitor. Part 2 is correct.

C. Incorrect. Part 1 is correct. Part 2 is plausible because estimating flow every fours is an action for TRM 3.3.3.10 (action 1b) but it is for an inoperable flow instrument.

D. CORRECT: Per OP-901-412, Automatic Actions, BM-547, Boron Management Discharge to Circulating Water Auto Isolation Valve and BM-549, Boron Management Discharge to Circulating Water Flow Control Valve will close to terminate the Boron Management release upon a high radiation signal on the BM Radiation Monitor. Per TRM 3.3.3.10 action 1a, at least two independent samples are required to be analyzed to continue the release with the BM Radiation Monitor inoperable. This question is SRO because it requires knowledge of TS below the line (greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action requirement).

Technical Reference(s): OP-901-412, page 4 Rev. 2 (Attach if not previously provided) TRM 3.3.3.10 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO40 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

Revision 0 Facility: Waterford 3 Page 46 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 1 K/A # 2.1.36 Importance Rating 4.1 K/A Statement 2.1.36 Knowledge of procedures and limitations involved in core alterations.

Proposed Question: SRO 19 (Q94) Rev: 1 Given:

Core offload is in progress

A failure of Steam Generator Nozzle Dams 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, Refuel SRO should expect a final level of

____(1)____ ft. MSL in the core and _____(2)_____ ft. MSL in the Refueling Cavity.

(1) (2)

A. 13.5 13.5 B. 13.5 20 C. 20 13.5 D. 20 20 Revision 0 Facility: Waterford 3 Page 47 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect: OP-010-006 step 9.23.1.1 states a loss of a nozzle dam, if left uncorrected, will result in a final water level of 13.5 ft. MSL in core and a level of 20 ft. MSL water level in Spent Fuel Pool and north end of the Refueling Cavity. Plausible because applicant must be aware that the refuel cavity will stop draining at 20 ft. (level of the head flange)

B. CORRECT: OP-010-006 step 9.23.1.1 states, a loss of a nozzle dam, if left uncorrected, will result in a final water level of 13.5 ft. MSL in the core and a level of 20 ft. MSL water level in Spent Fuel Pool and north end of the Refueling Cavity. The upper cavity level is 20 ft, (even with the head flange). At this level the cavity will no longer drain and the core will drain to the level of the nozzle dams in the S/G (centerline of the RCS hot leg). This question is SRO knowledge because knowledge of OP-010-006 requirements for a refuel cavity lowering level is an SRO refuel floor responsibility.

C. Incorrect. OP-010-006 step 9.23.1.1 states that a loss of a nozzle dam if left uncorrected, will result in a final water level of 13.5 ft. MSL in the core and a level of 20 ft. MSL water level in Spent Fuel Pool and north end of the Refueling Cavity. Applicant must be aware of the elevation arrangement between the refuel cavity and the core.

D. Incorrect. OP-010-006 step 9.23.1.1 states that a loss of a nozzle dam if left uncorrected, will result in a final water level of 13.5 ft. MSL in the core and a level of 20 ft. MSL water level in Spent Fuel Pool and north end of the Refueling Cavity. Plausible because the applicant must know that the core will continue to drain once the cavity stabilizes at 20 ft Technical Reference(s): OP-010-006 Rev. 334, Attachment 9.23 (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. 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 6 Comments: Question sent as free review. Change "will" to "should" in stem.

Resolution: (Changed "will to should" in the stem).

Revision 0 Facility: Waterford 3 Page 48 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 1 K/A # 2.1.39 Importance Rating 4.3 K/A Statement 2.1.39 Knowledge of conservative decision making practices.

Proposed Question: SRO 20 (Q95) Rev: 0 While inserting CEAs for ASI control during a rapid plant power reduction, the ATC operator identifies that three of four CPC channels indicate an ASI of -0.58. Which of the following is the responsibility of the ATC operator in accordance with EN-OP-115, Conduct of Operations?

A. Immediately trip the reactor.

B. Verify CEAs groups are above their Transient Insertion Limits.

C. Immediately notify the CRS that ASI is outside of the required limits.

D. Monitor ASI closely for several minutes to determine impact of the CEA motion.

Revision 0 Facility: Waterford 3 Page 49 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: TS Basis 2.2.1 states that the DNBR algorithm used in the CPCs is valid only within the limits indicated and operation outside of the limit will result in a CPC generated trip. One of the limits listed is ASI more negative than .5. For the given conditions in the stem a reactor trip should have occurred. EN-OP-115 step 5.1 states that the Reactor operator will immediately trip the reactor if an RPS trip setpoint has been exceeded. This is one of the very few actions that the RO is required to take action without requiring direction from the CRS. This is a generic question since the action would be the same for any type of shutdown. This question is SRO knowledge because the trip setpoint for ASI is an aux trip that is found in TS basis only. This question also requires knowledge of the administrative procedure EN-OP-115.

B. Incorrect. Plausible because section 9.10 of OP-010-005, ASI control guidelines, provides direction for maintaining CEAs above the Transient Insertion Limits.

C. Incorrect. Plausible because this would be the correct action if the limits in TS Basis 2.2.1 had not been exceeded.

D. Incorrect. Plausible because monitoring ASI closely for several minutes after CEA motion to determine the impact of the movement is step 9.10.1.6 in OP-010-005, ASI control guidelines Technical Reference(s): EN-OP-115 step 5.1 on page 24 Rev. 26 (Attach if not previously provided) TS Basis 2.2.1 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CPC00 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 X 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 0 Facility: Waterford 3 Page 50 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 2 K/A # 2.2.12 Importance Rating 4.1 K/A Statement 2.2.12 Knowledge of surveillance procedures.

Proposed Question: SRO 21 (Q96) Rev: 0 Per OP-903-094, ESFAS Subgroup Relay Test-Operating, for stroke time testing of valves, full stroke time is that time interval from ___(1)___ to the end of the actuating cycle. The stroke time recorded on the surveillance data sheet shall be rounded to the nearest ___(2)___ second.

(1) (2)

A. the beginning of valve movement 1/10 B. the beginning of valve movement 1/100 C. initiation of the actuation signal 1/10 D. initiation of the actuation signal 1/100 Revision 0 Facility: Waterford 3 Page 51 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. The beginning of valve movement is plausible since valve stroke time is being recorded but OP-903-094 states that full stroke time is that time interval from initiation of the actuating signal (depressing the actuation button) to the end of the actuating cycle. Part 2 is correct.

B. Incorrect. The beginning of valve movement is plausible since valve stroke time is being recorded but OP-903-094 states that full stroke time is that time interval from initiation of the actuating signal (depressing the actuation button) to the end of the actuating cycle. 1/100 second would be more accurate but is not what the surveillance procedure requires.

C. CORRECT: Per limitation 3.2.6 of OP-903-094, for stroke time testing of valves, full stroke time is that time interval from initiation of the actuating signal to the end of the actuating cycle. This same limitation states the stroke time recorded on the surveillance data sheet shall be rounded to the nearest 1/10 second. This question is generic because this same limitation exists in all surveillances that requires stroke time testing. This question is SRO knowledge because it requires knowledge of the administrative requirements for performing TS surveillances.

D. Incorrect. Part 1 is correct. 1/100 second would be more accurate but is not what the surveillance procedure requires.

Technical Reference(s): OP-903-094 limitation 3.2.6 Rev. 32 (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. 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 3 Comments:

Revision 0 Facility: Waterford 3 Page 52 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 2 K/A # 2.2.43 Importance Rating 3.3 K/A Statement 2.2.43 Knowledge of the process used to track inoperable alarms.

Proposed Question: SRO 22 (Q97) Rev: 0 Per EN-OP-115-08, Annunciator Response Procedure, an annunciator that is non-functional due to a failure must be documented on the Annunciator Removal from Service or Modification form and retained in the annunciator log book if ___________.

A. the annunciator has re-flash capability B. the annunciator card is required to be pulled C. the non-functionality of the annunciator will extend beyond one shift D. the annunciator is not logged in the Equipment Out of Service Index Revision 0 Facility: Waterford 3 Page 53 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Plausible because EN-OP-115-08 refers to annunciator that have re-flash capability such that they should only be removed if severe distractions are occurring. But, if it were to be returned to service before one shift, the annunciator removal form is not required.

B. Incorrect. Pulling the annunciator card is plausible because this is the action that renders the annunciator unavailable. Pulling the annunciator card does not require the attachment to be filled out if it will be returned before the end of shift.

C. CORRECT: Per EN-OP-115-08, an annunciator that is non-functional due to a failure must be documented on the Annunciator Removal from Service or Modification attachment and retained in the annunciator log book if the non-functionality of the annunciator will extend beyond one shift. This question is SRO knowledge because it pertains to knowledge for the administrative requirements for disabling annunciators.

D. Incorrect. Plausible because equipment removed from service are tracked using an EOS form and logged in the EOS index. EN-OP-115-08 does not provide an exception to using the Annunciator removal form if an EOS is prepared.

Technical Reference(s): EN-OP-115-08 page 12 Rev. 5 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPA 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 3 Revision 0 Facility: Waterford 3 Page 54 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 3 K/A # 2.3.14 Importance Rating 3.8 K/A Statement 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Proposed Question: SRO 23 (Q98) Rev: 0 The CROAI Radiation monitors isolate the Control Room Ventilation (HVC) on a high radiation level to prevent Control Room staff from receiving a maximum dose of

___(1)___ for the ___(2)___ of the event.

(1) (2)

A. 5 rem duration B. 5 rem first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months C. 2 rem duration D. 2 rem first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Revision 0 Facility: Waterford 3 Page 55 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: The isolation of the Control Room for the duration of the event ensures no one individual will exceed the Federal Limit of 5 rem. This question is generic because there is varying events that will cause the control room ventilation to isolate and then require re-pressurization. This question is SRO knowledge because it requires knowledge of TS 3.7.6.1 basis.

B. INCORRECT. Part 1 is correct. Part 2 is plausible because the W3 E plan procedure will make PAR recommendations based on two hour dose duration.

C. INCORRECT. Two rem is plausible because this is the W3 administrative dose yearly limit. Part 2 is correct.

D. INCORRECT. Two rem is plausible because this is the W3 administrative dose yearly limit. Part 2 is plausible because the W3 E plan procedure will make PAR recommendations based on two hour dose duration.

Technical Reference(s): TS 3.7.6.1 basis (Attach if not previously provided) 10CFR 50.67 Appendix A criteria 19 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-HVC00 (As available)

Question Source: Bank # SRO83 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2008 SRO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2,4 Comments:

Revision 0 Facility: Waterford 3 Page 56 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 4 K/A # 2.4.4 Importance Rating 4.7 K/A Statement 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

Proposed Question: SRO 24 (Q99) Rev: 0 The RCS Heat Removal Safety Function in OP-902-000, Standard Post Trip Actions, directs the crew to check RCS Tcold greater than or equal to ___(1)___ .

The contingency action for this safety function states, If RCS Tcold is being controlled by an Excess Steam Demand, then stabilize RCS temperature with the least affected SG in accordance with ___(2)___.

(1) (2)

A. 530°F Appendix 13 of OP-902-009, Standard Appendices B. 530°F OP-902-004, Excess Steam Demand Recovery Procedure C. 540°F OP-902-004, Excess Steam Demand Recovery Procedure D. 540°F Appendix 13 of OP-902-009, Standard Appendices Revision 0 Facility: Waterford 3 Page 57 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: The RCS Heat Removal Safety Function in OP-902-000, Standard Post Trip Actions, directs the crew to check RCS Tcold greater than or equal to 530°F. The contingency action for RCS Tcold less than 530°F and being controlled by an Excess Steam Demand is to stabilize RCS temperature with the least affected SG in accordance with Appendix 13 of OP-902-000. The ESD event is the only W3 event that the crew must diagnose and take action before diagnosing into an optimal recovery procedure due to PTS concerns since the steam generator will blow down quickly. This question is generic since the SPTAs are performed on any event that results in a reactor trip. This question is SRO knowledge because it requires the knowledge of an initiating condition and then a selection of a section in the EOP to combat the event.

B. Incorrect. Part 1 is correct. Part 2 is plausible because an ESD is occurring. The ESD event is the only W3 event that the crew must diagnose and take action before diagnosing into an optimal recovery procedure due to PTS concerns since the steam generator will blow down quickly.

C. Incorrect. Part 1 is plausible because 540°F would be on the low end of expected Tcold during an uncomplicated reactor trip. Part 2 is plausible because an ESD is occurring. The ESD event is the only W3 event that the crew must diagnose and take action before diagnosing into an optimal recovery procedure due to PTS concerns since the steam generator will blow down quickly.

D. Incorrect. Part 1 is plausible because 540°F would be on the low end of expected Tcold during an uncomplicated reactor trip. Part 2 is correct.

Technical Reference(s): OP-902-000 page 11 Rev. 16 (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 #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 0 Facility: Waterford 3 Page 58 of 60

2020 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 4 K/A # 2.4.42 Importance Rating 3.8 K/A Statement 2.4.42 Knowledge of emergency response facilities.

Proposed Question: SRO 25 (Q100) Rev: 0 Which of the following offsite communications is transferred from the Control Room to the Emergency Operations Facility (EOF) once the EOF is activated?

A. Continuous communications with the NRC.

B. Requests for offsite medical assistance.

C. Requests for offsite fire-fighting assistance.

D. Updates to the Notification Message Form for Operational Hotline Members.

Revision 0 Facility: Waterford 3 Page 59 of 60

2020 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Step 1.2 of EP-002-100 (TSC Activation, Operation, and Deactivation) lists continuous communications with the NRC as a responsibility assumed by the TSC from the Control Room.

B. Incorrect. Step 1.2 of EP-002-100 (TSC Activation, Operation, and Deactivation) lists Requests for offsite medical assistance as a responsibility assumed by the TSC from the Control Room.

C. Incorrect. Step 1.2 of EP-002-100 (TSC Activation, Operation, and Deactivation) lists Requests for fire-firefighting assistance as a responsibility assumed by the TSC from the Control Room.

D. CORRECT: Step 1.9 and 1.10 of EP-002-102 (EOF Activation, Operation, and Deactivation) lists Notification of OHL members as a responsibility assumed by the EOF from the Control Room. This question is SRO knowledge because it requires knowledge of the E-plan facilities and responsibilities which is required for an individual in the role of the Emergency Director.

Technical Reference(s): EP-002-100 step 1.2 page 10 Revision 50 EP-002-102 step 1.9 and 1.10 page 25 Revision (Attach if not previously provided) 310 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-EP02 obj. 9 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 3 Comments:

Revision 0 Facility: Waterford 3 Page 60 of 60

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