Text

Draft - SRO Written, Oyster Creek 2002 NRC Initial Licensing Exam
	ML021610274
Person / Time
Site:	Oyster Creek
Issue date:	05/31/2002
From:	Hackenberg J; AmerGen Energy Co
To:	Conte R; NRC/RGN-I/DRS/OSB
References
	50-219/02301 2002-301
	Download: ML021610274 (200)
	v • d • e

Oyster Creek 2002 NRC Initial Licensing Exam

01. Given the following conditions:

0 A LOCA has occurred 0 Two Main Core Spray Pumps (NZ01A & NZO1 B) are injecting 0- Two Containment Spray Pumps (51 A & 51 B) are operating

"* Total Containment Spray flow is 5,000 GPM

"* Torus water temperature is 1600 F

"* Torus Pressure is 10 PSIG

"* Torus Water level is 75" Based on these conditions, which of the following is the Maximum Core Spray flow available?

a. 8,000 gpm

b. 9,000 gpm

c. 10,000 gpm

d. 11,000 gpm 01

Oyster Creek 2002

- Question Qeto Data Sheet aaSetNCIiilLcnigEam- NRC Initial Licensing Ex~am Answer Key

1 Choice Basis or Justification Correct: C Requires Support Procedure 4 to answer.

Using Figure A, Core Spray vortex Limit, at 75", max flow is 15,000 gpm; since the Cont Spray Pumps are drawing 5,000, Core Spray can only have 10,000 Distractors: A Plausible distractor B Plausible distractor D Plausible distractor Psychometrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3.5 3 Source Documentation Source: New Exam Item Old NRC Exam 1999 exam #80 Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Support Procedure 4 Figure A; 6231-PGD-2621 845.0003 Learning Objective: (01)03055, (01)00306 Terminal Objective: 20005(01)405 Knowledge/Ability: 295030 EA1.01 Importance: 3.6 / 3.8 Ability to operate and/or monitor the following as they apply to Low Suppression Pool Water level: ECCS systems( NPSH considerations)

Prepared by: Michael Spenser Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

02. Which of the following describes the required vent path to be used to maintain the Torus pressure below the Primary Containment Pressure Limit curve.

"* Hydrogen concentration is 2% in the Containment

"* Containment water level is 150 Inches

"* The off-site release rate is projected to stay below the release rate for an Unusual Event

a. The Drywell hardened pipe vent

b. The Torus hardened pipe vent

c. The Drywell Purge valves

d. The Torus vent valves

Question Data Sheet NRC Initial Licensing Exam Ovster Creek 2002Quso Answer Key

2 Choice Basis or Justification Correct: D Correct, as indicated in Support Procedure 32 Distractors: A Plausible distractor, but the hardened vent is NOT to be used if Hydrogen is present in Containment B Plausible distractor, but the hardened vent is NOT to be used if Hydrogen is present in Containment C Plausible distractor, viable vent path on higher water level in Containment Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 2 Source Documentation Source: New Exam Item Old NRC Exam 1999 exam #89 Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Primary Containment EMG 3200.02; 6231-PGD-2621 845.0008;.0010 Learning Objective: (02)03000; (02)01300 Terminal Objective: 20005 (01)424 34501(02)412 Knowledge/Ability: 500000 EK1.01 Importance: 3.3/3.9 Knowledge of the operational implications of the following concepts as they apply to High Containment H2 concentrations; containment Integrity Prepared by: Joseph M. Milligan

' Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

03. Given the following conditions:

An Instrument Air header line break occurs on the discharge of the Air Receivers

The break can NOT be isolated

Instrument Air pressure as read on Panel 7F is dropping

CONTROL AIR PRESSURE LO annunciator has just alarmed

The direction is now given to manually scram the reactor.

Which of the following systems are available for level / pressure control? (Assume Instrument Air header pressure continues to lower)

a. Bypass Valves, LFRV "A" and/or "C", and CRD

b. EMRV's, CRD, and RWCU letdown

c. Bypass Valves, Feedwater on "A" or "C" block valve, and RWCU letdown

d. EMRV's, Isolation Condensers, and Feedwater using heater string outlet valve(s).

03

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

3 Choice Basis or Justification Correct: D These systems do not require Instrument air to operate; though at some time, makeup to the Isol cond will be required using firewater or manual operation of makeup valves Distractors: A The bypass valves are not available after the outboard MSIV's fail closed B Cleanup letdown will not be available; the valve fails closed on a loss of air C The bypass valves are not available after the outboard MSIV's fail closed Cleanup letdown will not be available; the valve fails closed on a loss of air Metrics Level of Knowledge Difficulty _ _Time Allowance (minutes) SRO H 2.5 3 Source Documentation Source: New Exam Item Old NRC Exam 1999 exam #47 Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): ABN-2000-3200.35; 6231-PGd-2621 828.0043 Learning Objective: (01)(02) 00916,08331,08346,08348,08686 Terminal Objective: 27904(01)403 Knowledge/Ability: 295019 AA1.02 Importance: 3.3 /3.1 Ability to operate and/or monitor the following as they apply to loss of IA: IAsystem Valves Prepared by: Joseph M.Milligan Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam R IiilLcnigEa OytrGek20

04. A continuous fire watch is required for which of the following conditions?

a. Battery Room A & B Halon 1301 System tank at 96% full charge weight and 91 % full charge pressure

b. One Thermal Fire Detection instrument for Emergency diesel Generator #1 is inoperable; all other detectors are operable

c. Emergency Lighting Unit (ELU) #40 has been declared inoperable.

d. The 4160 Volt Switchgear CO 2 roll down fire door has been accidentally damaged and may not be able to perform its designed function.

04

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing NRC Initial Licensing Exam Exam Oyster Creek 2002 Question Data Sheet Answer Key

4 Choice Basis or Justification Correct: D For this question, a copy of 101.2 TRM will be provided. It will require the examinee to know how to use the information provided in the Technical Requirements Distractors: A Plausible; Selected if examinee misinterprets th-e requirements. As written, this distracter is desired conditions of the Halon system B Plausible; Selected if examinee misinterprets the requirements. The Technical Requirements allow 1 detector to be OOS.

C Plausible; Selected if examinee misinterprets the requirements. The Technical Requirements allow a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months period to establish emergency lighting requirements.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2.5 5 Source Documentation Source: New Exam Item Old NRC Exam 1999 exam #99 Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Technical Requirements (Att 101.2-3); 6231-PGD-2621 [2621.830.051 Learning Objective: (01) 00960 Terminal Objective: 34101 (02)411 Knowledge/Ability: G2.4. 25 Importance: 2.9 / 3.4 Knowledge of Fire Protection Procedures Prepared by: Joseph M. Milligan Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

05. Given the following conditions:

Reactor startup has been in progress for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Reactor power 5%

Main turbine warm-up is in progress

° Chemistry just reported reactor the following coolant sample results:

- Conductivity: 8 p.S/cm @ 250 C

- Chlorides: 0.3 ppm Which one of the following describes the required actions, if any?

A. No action is required because a Technical Specification LCO has not been entered.

B. A shutdown must be initiated immediately because the low steaming rate

(< 100,000 lbm/hr) limitations have been exceeded.

C. A shutdown must be initiated immediately because the high steaming rate

(> 100,000 lbm/hr) limitations have been exceeded.

D. No action is required as long as the coolant quality does not maintain these values for greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for this incident.

5

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

5 Choice Basis or Justification Correct: D Tech Spec is required to answer this question.

lAW TS 3.3.E.3, Limits are 10 p.Slcm and 0.5 ppm Chloride (5% power is 363,000 Ibm/hr, based on 100% steaming rate is 7.26 Mlbm/hr)

Limits given are below TS for >100,000 lbm/hr, but are > than limits established in TS 3.3.E.5, hence TS 3.3.E.5 is applicable Distractors: A Plausible, 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months limits are below given and steaming rate > 100, 000 Ibm/hr B Misinterpretation of TS or miscalculation of steaming rate based on 5% power c Misinterpretation of TS or miscalculation of steaming rate based on 5% power Psychometrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 3 X - 43.1 Source Documentation Source: New Exam Item Old NRC Exam 1999 NRC EXAM Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS 3.3.E; 6213-PGD-2621 850.0.0090 Learning Objective: (02) 01658, (02) 01920, (02)01921 Terminal Objective: 34403(02)001 Knowledge/Ability: Generic: Conduct of Ops 2.1.34 Im ortance: 2.3 / 2.9 Ability to maintain primary and Secondary plant chemistry within allowable limits Prepared by: Joseph M. Milligan, distractor a. modified at licensee request and stem clarified to ensure only one correct answer.

I Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

6. Given the following:

"* The plant is operating at full power.

"* The Equipment Operator (EO) reports that the diesel fuel'oil storage tank appears to have a slow leak.

0 There is one foot of fuel oil on the floor of the storage tank room.

"* The level gage indicates 13,800 gallons of fuel'oil.

Which one of the following is correct?

a. The plant may continue operating for up to 7 days, provided the other diesel generator is tested at greater than 80 percent load for at least one hour every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. The plant must be placed in cold shutdown because-there is NOT sufficient fuel oil supply to maintain both diesel generators operating for 3 days in the event of a LOCA and a loss of off site power.

c. The plant may continue operating. The fuel oil required to maintain both diesel generators operating for 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months is only 9790 gallons.

d. The plant must be placed In cold shutdown because there is NOT sufficient fuel oil supply to maintain both diesel generators operating for 4 days in the event of a LOCA and a loss of off site power with a loss of one 4160V bus.

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

6 Choice Basis or Justification Correct: B Correct answer. TS 3.7.C.3 and 4. 14,000 gal. required to consider EDGs operable.

Distractors: A Plausible distracter, continued operation allowed with one EDG OOS.

C Plausible distracter, fuel oil required for 3 days with LOOP, LOCA and loss of one bus.

D Plausible distracter, plant conditions stated require 9790 gallons for 3 days operation. Four days Is not used for this bases in TS.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3.5 2 X-43.2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS 3.7.C and bases; CFR 55.43.2 [2621.828.131 Learning Objective: 00803, 00804 Terminal Objective: 20003(01)04, 26401(01)001, 004 Knowledge/Ability: 295003 G2.2.25 Importance: 2.5/3.7 Knowledge of bases In TS for LCOs and Safety Limits. Partial or complete loss of AC power.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 Oystr Ceek 002NRC Initial Licensino Exam

7. The plant is operating at 100% power when a loss of off-site power occurs.

Under these conditions, a reactor scram is caused by a:

a. load rejection to reduce the expected RPV pressure rise and flux spike.

b. high reactor pressure condition to protect the RPV from overpressure.

c. low reactor water level condition to ensure an adequate RPV water inventory.

d. MSIV closure to maintain an adequate RPV water inventory.

07

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

7 Choice Basis or Justification Correct: A Correct per the UFSAR Transient Analysis.

Distractors: B Plausible distracter, will get high pressure but trip comes from turbine trip which initiates the high pressure.

C Plausible distracter; Feed pumps are lost but level will not be first scram signal.

D Plausible distracter, Closure of MSIVs will lower level but the turbine trip will occur first.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2.5 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): 2000 ABN 3200-36, Loss of Off-Site Power, Para. 2.3 [2621.828.25/38]

Learning Objective: 01187, 01212, 01148, 01157, 01723, 08658 Terminal Objective: 2480401405, 2120501403 Knowledge/Ability: 295003 AK3.05 Importance: 3.7/3.7 Knowledge of the reasons for the following responses as they apply to partial or complete loss of AC power; reactor scram.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licen~sing Oyster Creek 2002 NRC Initial Licensing Exam Exam

8. A reactor scram occurred from 75 percent power and two control rods remained at Notch 48. EMG 3200.01 B, "RPV Control - With ATWS" has been entered. Several automatic initiations and isolations are required to be bypassed.

Which of the following bypasses is required?

a. The ADS timer is bypassed so reactor pressure control can be accomplished by the preferred method, manual operation of the EMRV's.

b. The MSIV automatic isolation is bypassed to prevent the insertion of positive reactivity and possible restart of the reactor.

c. The ADS timer is bypassed to prevent uncontrolled depressurization, preventing insertion of positive reactivity and a possible restart of the reactor.

d. The RBCCW isolation is bypassed to ensure cooling is available for heat removal via the shutdown cooling heat exchangers.

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

8 Choice Basis or Justification Correct: C Correct per EOP users guide.

Distractors: A Plausible, EMRV could be used but would add-heat to Torus and is not the preferred method.

B Plausible, MSIV closure if being used for heat removal would result in a pressure spike and some positive reactivity but would not result in restart.

D Plausible, RBCCW is maintained for heat removal of Drywell, not shutdown cooling.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 2 Source Documentation Source: New Exam Item Old NRC Exam Modified Bank Item X (RQ #2948) Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): EMG 3200.01 B, Level/Power Control. EOP users guide, RPV Control with ATWS, Pgs.

1 B-1 5 and 16. [2621.845.19]

Learning Objective: 02257, 0378, 0379, 01022 Terminal Objective: 21805(01)401, 20005(02)405 Knowledge/Ability: 295006 AA2.01 Importance: 4.5/4.6 Ability to determine and/or interpret the following as they apply to scram, Reactor Power.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Oyster Creek 2002 NRC Initial Licensing Licensing Exam Exam

09. Given the following:

"* The reactor is at 42% power -

"* RPV level and temperature are normal for this power

"* The main turbine trips on low condenser vacuum Which one of the following describes the expected reactor response and the reason for the response?

The reactor will:

a. Scram on main generator trip logic.

b. Scram on main turbine stop valve closure.

c. NOT trip since this is within bypass capacity.

d. NOT trip since the scram is bypassed at this power level.

09

Question Data Sheet NRC Initial Licensing Exam Ovster Creek 2002 Answer Kev

9 Choice Basis or Justification Correct: B Correct, the reactor will scram when above 30 percent.

Distractors: A Plausible, although reactor trips, it is not do to any generator trip logic.

C Plausible, 40% is bypass capacity.

D Plausible, trip is bypassed below 40% power.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): ABN 3200.10 Turbine Trip, and ABN 3200.01, Reactor Scram [2621.828.25/38]

Learning Objective: 01187, 01212, 01157, 08658 Terminal Objective: 2480401405, 2120501403 Knowledge/Ability: 295006 AK2.04 IFimportance: 3.6/3.7 Knowledge of the interrelations between SCRAM and the following. Turbine trip logic: Plant specific.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

10. Initial conditions were:

"* Reactor Power is 100%

"* Turbine Control Valve position is 98%

The reactor operator, while making preparations to backwash the main condenser, inadvertently increased reactor recirculation pump speed on the master controller and increased reactor power to 106%.

Which one of the following correctly describes the plant response with no further operator action?

a. Turbine generator load will increase and the bypass valves will open to maintain turbine inlet pressure at the pre-transient value.

b. Turbine generator load will increase to maintain the turbine inlet pressure at the pre-transient value.

c. Turbine generator load will remain the same and the bypass valves will open to control reactor pressure at the pre-transient value.

d. Turbine generator load will increase and bypass valves remain closed due to normal deadband in the turbine control system.

Oyster Creek 2002 Question Data Sheet NRC Initial Licensina Exam Answer Key

10 Choice Basis or Justification Correct: A Turbine load will increase and bypass valves will open to maintain Turb. inlet pressure at setpoint.

Distractors: B Plausible, applicant may assume small load increase possible but load limit is set to 105%

C Plausible, applicant may assume bypass valves will maintain pressure and load at pre event values.

D Plausible, applicant may assume there is a normal deadband in the turb. cont. sys.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2.5 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): 2611-PGD-2621 System 51, Sect. B, Gen. Description Learning Objective: (01) 02312 Terminal Objective: 24901 (01)003 Knowledge/Ability: 295007 AK1.04 Importance: 2.7/2.8 Knowledge of the operational implications of the following concepts as they apply to High Rx Pressure, Turbine load.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

11. The plant was operating at 75% power when the turbine control EPR failed high.

Which one of the following describes the initial plant response?

a. Reactor pressure lowering, reactor water level lowering, reactor power lowering.

b. Reactor pressure lowering, reactor water level raising, generator output raising.

c. Reactor pressure raising, reactor water level lowering, steam flow lowering.

d. Reactor pressure raising, reactor power raising, generator output raising.

11 \

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

11 Choice Basis or Justification Correct: C. Correct per ABN-3200.09, Electric Pressure Regulator Malfunction failure high.

High failure gives Hi Press, low level, low steam flow, lower generator output.

Distractors: A. Plausible, Conditions are a mix of EPR failure low and high B. Plausible, Conditions are a mix of EPR failure low and high D. Plausible, Conditions are a mix of EPR failure low and high Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): 2611-PGD-2621 System 51, Sect B. and ABN-3200.09 Learning Objective: 9521,2316 Terminal Objective: 2490401002, 2490101003 Knowledge/Ability: 295007 AK3.06 Importance: 3.7/3.8 Knowledge of the reasons for the following responses as they apply to High Reactor Pressure. Reactor/turbine pressure regulating system operation.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

12. Given the following conditions:

"* The reactor has been manually scrammed

"* Reactor Power is 4%

"* EMG-3200.01 b, RPV CONTROL - WITH ATWS, has been entered

Level is being lowered as directed by the EMG

, Reactor Recirculation Pumps have been tripped LEVEL is lowered to:

a. Reduce natural circulation.

b. Reduce boron dilution.

c. Increase core inlet subcooling.

d. Increase natural circulation.

Question Data Sheet NRC Initial Licensing Exam Oyster Creek 2002 Answer Key

12 Basis or Justification Choice Correct: A Per EOP Users Guide, concentration (although it woul Distractors: B Plausible, not mix well), is notlevel but thiswater Reducing the intent the boron would ofraise level reduction.

Plausible, would be accomplished by increased injection C

Plausible, would be accomplished by increased water level.

D Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

13. Given the following:

"* The reactor scrammed from 75% power due to a main turbine generator load rejection.

"* All plant systems functioned normally on the trip.

Which one of the following correctly describes the Feedwater Control System response to this transient?

a. A RPV level change of minus 10 inches from program will change the master controller setpoint to 152. inches to ensure level is returned to normal following the scram.

b. A scram signal and a RPV level change of minus 10 inches will change the master controller setpoint to 142 inches TAF to reduce flow demand and prevent a high water level transient following the scram.

c. A scram signal will change the master controller setpoint to 140 inches TAF to reduce flow demand and prevent a high water level transient following the scram.

d. Level control remains in automatic, the high demand for feedwater results in runout protection of the feedpumps until level returns to 130 inches TAF at which time the runout protection is released.

13

Oyster Creek 2002 Question Development Checklist NRC Initial Licensing Exam Answer Key

13 Choice Basis or Justification Correct: B Correct per Feedwater Control System (FCS), Pgs 17-19.

Distractors: A Plausible, a level change of-10 inches and a scram signal programs level at 142 inches, not 152 inches.

C Plausible, a scram signal and a level change is required to change level set to 142 inches, not 140 inches.

D Plausible, runout protection can be invoked but it will be released at 110 inches for scrams from > 50%.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Procedure [2621.828.181 Learning Objective: 715, 2383 Terminal Objective: 2590501401 Knowledge/Ability: 295009 AA1.02 Importance: 4.0/4.0 Ability to operate and/or monitor the following as they apply to LOW REACTOR WATER LEVEL. Reactor water level control.

Prepared by: Larry Briggs Question Development Checklist

Oyster Creek 2002 NRC Initial Licensing Exam

14. Following a two-week outage, the plant was returned to full power two days ago. Since then, the Drywell pressure and temperature has increased, requiring the Drywell to be vented several times.

Based on the above, which one of the following is the cause of this condition?

a. An increased cycling rate of the containment nitrogen compressors.

b. An increased service water flow rate.

c. A 0.5 GPM increase in the unidentified leakage rate.

d. A 0.5 GPM increase in the identified leakage rate 14

Oyster Creek 2002 Question Data Sheet NRC Initial Licen~sing Exam Answer Key

14 Choice Basis or Justification Correct: C Correct, RCS leak increases the temperature and pressure.

Distractors: A Plausible, Increased Nitrogen use will increase pressure but not temperature B Plausible, Increased service water flow will reduce RBCCW temp and reduce Drywell temperature and pressure.

D Plausible, increased identified leakage goes to equipment drain tank not the drywell like unidentified leakage. Should have no affect on either parameter.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): RAP C-3-f and C-8-h [2621.828.321 Learning Objective: 00432 Terminal Objective: 2230101006 Knowledge/Ability: 295010 AA2.06 Importance: 3.6/3.6 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE, Drywell temperature.

Prepared by: Larry Briggs

Oyster Creek 2002 NRC Initial Licen~sing ienigEa Exam OytrCek 02NCInta

15. The plant is operating at full power when C-3-f, "DW PRESS HI/LOW" annunciates. The Control Room Operator reports the following plant conditions.

0 Time between Drywell sump pump-downs has shortened 0 Containment pressure has increased 0.2 psi

Containment airborne radiation levels have remained constant

Drywell Bulk temperature has increased 50 F Which one of the following is the reason for the conditions stated?

a. An operating drywell cooler has developed a 25 gpm RBCCW leak on the INLET to the cooler.

b. An operating drywell cooler has developed a 25 gpm RBCCW leak on the OUTLET to the cooler.

c. One of the reactor recirculation pump's seal leak-off rate has increased by 0.25 gpm.

d. One of the EMRVs is leaking by and tailpiece temperature is 230 degrees F.

Oy/ster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

15 Choice Basis or Justification Correct: A Only leak that will satisfy all conditions Distractors: B Plausible, but would not result in temperature increase in containment C Plausible, would meet conditions except radiation levels D Plausible, but EMRV valve would leak into Torus water volume.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): RAP C-3-f, DW PRESS HI/LO [2621.828.321 Leaming Objective: 00416, 00418 Terminal Objective: 2230101006 Knowledge/Ability: , 295010 AK3.04 Importance: 3.5/3.8 Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE, Leak investigation.

Prepared by: Larry Briggs

Oyster Creek 2002 NRC InitialI I ina'nc~inr iv~m L..l AI I

16. The plant is at 60% power with 4 Recirculating pumps operating at 7E4 gpm.

Which one of the following describes the operational implications when one of the four Recirculating pumps trips?

The plant will enter the Exclusion Area and which of the following actions must be taken to exit the area?

a. Recirculation flow must be reduced to minimum

b. Cram rods must be inserted

c. Recirculation flow must be increased

d. The reactor must be manually scrammed I

Question Data Sheet NRC Initial Licensing Exam Oyster Creek 2002 Answer Key Choice Basis or Justification Correct: B This question will require use of Power Operation Map The conditions given plot a point just on the exclusion area; loss of feed heating will resulting in a power increase, placing the plant into the Exclusion area.

Inserting CRAM rods to exit the area is requir6d.

Distractors: A Plausible, this would normally reduce power but flow is at minimum allowed C Plausible, this would exit region but a power increase is not allowed to exit the Exclusion area D Plausible, required if power oscillations occur.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2 3 Source Documentation Source: New Exam Item Old NRC Exam X Modified 1999 NRC exam #66 (Revised distractors for op implications.)

Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank 2000-ABN-3200.16; 202.1 Att 202.1-2; 6231-PGD-2621 832.0004 Learning Objective: (01)(02)02022 Terminal Objective: 20001(01)501 Knowledge/Ability: 295014 AK1.06 Importance: 3.8/3.9 Knowledge of the operational implications of the following concepts as they apply to INADVERTENT REACTIVITY ADDITION. Abnormal reactivity additions Prepared by: Joseph M. Milligan Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Oyster Creek 2002 NRC Initial Licensing Exam Exam

17. Given the following:

"* The reactor scrammed from 100% power

"* Seven control rods failed to insert further than notch 04 on the scram

"* Control rods could not be inserted using Control Rod Drive pressure

", Reactor Engineering determined that the reactor would remain shutdown under all conditions without Boron

The plant is currently at 400 psig Which one of the following is correct?

a. Per TS the 7 control rods can be valved out of service and plant operations can be resumed once it is determined that the failures are not due to a failed CRD collet housing.

b. Per TS the 7 control rods must be fully inserted, then valved out of service before plant operations can be resumed.

c. TS require the plant to be placed in the cold shutdown condition and plant restart is not allowed until all 7 control rods are repaired.

d. TS require the plant to be placed in the Shutdown condition and plant restart is not allowed until at least 1 of the 7 control rods is repaired.

17

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

17 Choice Basis or Justification Correct: D TS allow power operation with up to 6 control rods valved out of service, as long as SDM requirements can be met.

Distractors: A Plausible, up to 6 control rods as long as no collet failures.

B Plausible, only 6 allowed C Plausible, does not require cold shutdown, would not have to repair all 7 control rods Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS Section 3.2.A & B [2621.828.111 L Learning Objective: 00005 Terminal Objective: 2100401413 Knowledge/Ability: 295015 G2.1.33 Importance: 3.4/4.0 Incomplete scram: Ability to recognize indications for system operating parameters which are entry-level conditions for Technical Specifications.

Prepared by: Larry Briggs Question Data Sheet

Ov.*t*r flre~k 2002NRIntaLceingam.7-. NRC Initial Licen~sing Exam Cvs, e, ree 20,... ..

18. Given the following:

"* The plant has experienced a LOCA and severe fuel damage.

"* Wind direction is from 900 (E) at 10 MPH

"* There was an electrical problem in the 4160 volt switchgear which has disabled Containment Spray.

"* Electrical maintenance personnel are certain that the Containment Spray System can be repaired in less than 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

"* Containment venting will be required per EMG-3200.02

"* The RAC has informed you that the projected dose at the site boundary will be 1.2 REM (TEDE)

"* A General Emergency has been declared.

Select the required Protective Action Recommendation (PAR)?

a. Evacuate 2 mile radius and WSW, W, and WNW for 5 miles, shelter the rest of the 10 mile EPZ

b. Evacuate 2 mile radius and E, ENE, and ESE for 5 miles, shelter the rest of the 10 mile EPZ

c. Shelter 2 mile radius and E, ENE, and ESE for remainder of 10 mile EPZ

d. Shelter 2 mile radius and WSW, W, and WMW for the remainder of the 10 mile EPZ

NRC Initial Licensing Exam

()-trCrek 2002 Question Data Sheet NCIiilLcnigEa Answer K - j

-iT I1 '

Choice Basis or Justification Correct: A Per EPIP-OC-.02, Exhibit lb. Section 2.0.

Distractors: B Plausible, inverse of actual correct answer C Plausible, Allowed by EPIP if release is less than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months but inverse of wind direction D Plausible, Allowed by EPIP if release is less than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2 4 43.4/5 Source Documentation Source: New Exam Item Old NRC Exam Modified Bank Item X RQ#3375* Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): EPIP-OC-.02, Exhibit lb. [E-Plan]

Learning Objective: 2685.780.07, A, AA, EE Terminal Objective: 2000502401 Knowledge/Ability: 295017 AA2.05 Importance: 2.5/3.8 Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE.

Meteorological data.

Modified stem to reduce release rate and used same distractors and correct ans.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam OytrCek20 R IiilLcnigEa

19. An Equipment Operator reported that there was an Off-Gas explosion at the AOG Recombiner and a loss of power to the AOG building. All AOG system automatic actuations occurred. The operator also reported that when he evacuated the AOG building the exit door would not stay closed and latched.

Which one of the following is correct per ABN-3200.22, AOG Building Loss of Power?

This event will:

a. NOT result in an increase in the stack release rate since all off-gas will now pass through the 30 minute delay line.

b. NOT result in an increased release rate because the AOG system isolates all off-gas release paths.

c. Result in an increase in the stack release rate and an unmonitored release.

d. Result in an increase in the stack release rate with NO unmonitored release.

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

19 Choice Basis or Justification Correct: C Per ABN the AOG system can release into the AOG building. This can allow radioactive material to be released at ground level since the door would not stay closed. Stack activity will go up because AOG system is bypassed and uses the 30 min. delay line only -

Distractors: A Plausible, applicant may not be aware that off-gas normally passes through 30 minute line and AOG.

B Plausible, AOG system does isolate, it also bypasses itself.

D Plausible, Applicant may not be aware that system can release H2 and radioactive gas into AOG build.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 4 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): ABN 3200.22 [2621.828.02 & .041 Learning Objective: 02801,00682 Terminal Objective: 2710401001, 3040101002, 3040101001 Knowledge/Ability: 295017 AK2.03 Importance: 3.3/3.5 Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following. Off-gas system.

Prepared by: Larry Briggs Question Data Sheet

NRC Initial Licensing Ex~am n cfavtr Crnmk 9f9 R niilLiesngEa

20. The plant is in a refueling outage. Source Range Monitor (SRM) indications at the beginning of the shift are:

"* SRM 21 4 CPS

"* SRM 22 7 CPS

"* SRM 23 8 CPS

"* SRM 24 6 CPS During the withdrawal of a control rod during refueling operations, the CRO reports the following count rates:

"* SRM21 34 CPS

"* SRM 22 40 CPS

"* SRM 23 30 CPS

"* SRM 24 35 CPS Which one of the following correctly describes the required action per ABN 3200.07, Unexplained Reactivity Change?

a. Initiate a manual reactor scram.

b. Insert the control rod using normal insertion procedures to "00".

c. Make an announcement to evacuate the 95 foot elevation and the refueling floor immediately.

d. Allow count rate to stabilize and notify reactor engineering before proceeding with any other action.

20

Oyster Creek 2002 ~J~---- Question Qeto Data Sheet aaSetNCIiilLcnigEa NRC Initial Licensing Exam Answer Key

20 Choice Basis or Justification Correct: B Correct per ABN-3200.07, Para 3.1, limit for doublings is 3.

Distractors: A Plausible, applicant could assume runaway reactor.

C Plausible, action for reactivity if moving a fuel assembly. Evacuation is if needed per procedure.

D Plausible, applicant could assume high count rate due to rate of reactivity insertion.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3.5 2 X-43.7 Source Documentation Source: New Exam Item Old NRC Exam Modified Bank Item X (1999 audit #71)* Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): ABN-3200.07, Para 3.1 [2621.812.031 Learning Objective: 00326, 01734 Terminal Objective: 2340401401 Knowledge/Ability: 295023 G2.1.32 Importance: 3.4/3.8 Ability to explain and apply system limits and precautions, REFUELING ACCIDENTS.

Modified starting and final counts in stem and all distractors, two significantly.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

21. Given the following plant conditions:

"* A LOCA has occurred

"* All control rods are at "00"

"* Torus pressure is 14 psig and increasing

", Torus water level is 130 inches and decreasing a Drywell temperature is 248°F

"* CHRMS is reading 2,500 RPhr All systems responded normally to the event and no operator actions have been taken.

Which one of the following operator actions is correct?

a. Emergency depressurize the reactor.

b. Manually initiate Drywell spray.

c. Vent the Torus through Torus vent valves V-28-18 and V-28-47.

d. Vent the Drywell through Drywell vent valves V-23-21 and V-23-22.

21

Question Data Sheet NRC Initial Licensing Exam Answer Key

21 Choice Basis or Justification Correct: B Per EMG 3200.02, start drywell sprays when above 12 psig Distractors: A Plausible, ED is required if Drywell temp cannot be maintained below 281 F, but would not correct to state that it cannot be maintained when temp is at 248F and DW Sprays have not been placed in service.

C Plausible, Several EMG procedure legs call for this vent path D Plausible, With the containment water level provided the applicant could select this vent path.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): EMG-3200.02, Procedure 310, Containment Spray System Operation [2621.845.08 Learning Objective: 03036 Terminal Objective: 2260101002 Knowledge/Ability: 295024 EK2.11 Importance: 4.2/4.2 Knowledge of the interrelations between HIGH DRYWELL PRESSURE and the following. Drywell spray (RHR) logic, Mark I & II [PRA related: Initiation of Containment Cooling]

Prepared by: Larry Briggs

.,Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

22. The reactor was manually scrammed from 30-percent power due to a small unisolable leak on a reactor water level instrument line in the Drywell.

"* Containment pressure is 2.5 psig and slowly increasing.

"* All systems performed normally on the scram.

"* Torus level is normal.

Based on the above, which one of the following is the correct method of containment pressure control?

a. The Drywell should be vented through the 2 inch Drywell vent line to the Reactor Building Ventilation System, as this will provide Torus scrubbing of the airborne radionuclides.

b. The Drywell should NOT be vented as this pressure'ensures the Reactor Building to Torus vacuum breakers will remain seated to prevent de-inerting the containment.

c. The Drywell should be vented via the 12 inch Torus vent line to the SBGTS to ensure that containment pressure can be maintained below 3 psig and will provide Torus scrubbing of airborne radionuclides.

d. The Drywell should be vented through the 2 inch Torus vent line to the Reactor Building Ventilation System, as this will provide Torus scrubbing of the airborne radionuclides.

22

NRC Initial Licensing Ex~am r a, Question Data SheetNRC.nitial.Licens.n..

Answer Key S#99 Choice Basis or Justification Correct: D EOP user's guide, Primary cont. press control, Pg 2 2-55; EGM-3200.02 Distractors: A Plausible, 2 inch vent line available but does not provide Torus scrubbing.

B Plausible, EOP requires venting but basis discusses the delta press, >1 psig to hold vacuum breakers closed.

C Plausible, 12 inch vent does provide scrubbing but is not recommended by EOP Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3.5 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): EOP users guide, pgs 2-27 thru 2-55, and EGM-3200.02 12621.845.08]

Learning Objective: 03000, 09546 Terminal Objective: 2000501435, 2000502410 Knowledge/Ability: 295024 EK3.07 Importance: 3.5/4.0 Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE. Drywell Venting. [PRA related: Containment venting]

Prepared by: Larry Briggs Question Data Sheet 'I,

Oyster Creek 2002 NRC Initial Licensing Exam R IiilLcnigEa OytrCek20

23. Given the following:

The plant is operating at full power.

Torus pressure is 0.8 psig

Drywell pressure is 1.2 psig.

Containment valve line up has been verified in accordance with OPS 2024.06, Containment Ventilation System - Diagnostic and Restoration.

Which one of the following is correct?

a. There is a small steam leak in the Drywell, enter EMG 3200.02, Primary Containment Control and implement Support Procedure 31 to maintain Drywell pressure below 3.0 psig.

b. There is a Nitrogen leak in the Drywell, enter EMG-3200.02, Primary Containment Control and implement Support Procedure 31 to maintain Drywell pressure below 3.0 psig.

c. Torus water level has decreased by about 10 inches, enter Procedure 310, Containment Spray System and restore level to normal.

d. Torus water level has increased by about 10 inches, enter Procedure 310, Containment Spray System and restore level to normal.

23

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

23 Choice Basis or Justification Correct: C Correct, a 10 inch level decrease will lower pressure about 0.5 psig. Restore level per Section 2.5 of Procedure 310.

Distractors: A Plausible, EMG 3200.02 would be entered at 143 inches in Torus or 3 psig B Plausible, Nitrogen leak could increase Drywell pressure but would not explain lower Torus pressure.

D Plausible, Applicant may have direction of pressure change reversed.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3.5 3 X - 43.5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): RAP C-5-e, and Procedure 310 [2621.828.321 Learning Objective: 00418, 00446 Terminal Objective: 2220101503, 2230101006 Knowledge/Ability: 295030 EA2.04 Importance: 3.5/3.7 Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL.

Drywell/suppression chamber differential pressure: Mark I & II Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

24. The reactor was operating at full power when the plant experienced a scram due to a failure in the turbine control oil system.

Plant conditions are:

"* Reactor level is at 90 inches TAF

"* Reactor power is less than 2% and decreasing

"* Alarm H-3-c, RX LVL LO-LO, channel I has annunciated Which one of the following is correct?

a. Diesel Generators and Core Spray Systems are running.

b. Recirculation pumps have tripped and MSIV's are closed.

c. Recirculation pumps have tripped and Diesel Generators are running.

d. MSIVs are closed and Isolation Condensers have initiated.

24

Question Data Sheet NRC Initial Licensing Exam Ovster Creek 2002 Answer Key

24 Choice Basis or Justification Correct: A Per RQP-3024.01, H-3-e, EDGs and Core Spray only require 1 channel to actuate.

Distractors: B Plausible, both actions occur at 90 inches but require both channels to actuate C Plausible, same as "B" and "A" D Plausible, same as "B" Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2.5 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): 2000-RAP-3024.01, H-3-e AND H-4-e [2621.828.37]

Learning Objective: 01157, 01164 Terminal Objective: 2120501403 Knowledge/Ability: 295031 EK2.09 Importance: 3.3/3.4 Knowledge of the interrelations between REACTOR LOWWATER LEVEL and the following. Recirculation system: Plant specific Prepared by: Larry Briggs Question Data Sheet

NRC Initial Licensing Exam Ovster Creek 2002.

25. Given the following:

"* The plant has experienced a LOCA and scram, without ATWS.

"° Containment pressure is 8 psig and slowing increasing.

"* RPV water level is 55 inches TAF and lowering.

"* Electrical faults have resulted in the lockout of 1 C and 1D 4160V buses.

"* Reactor pressure is 250 psig and lowering slowly.

"° Radiation levels in the Reactor Building are 50 mrem/hour Based on the above conditions, which of the following is correct?

a. Line up for injection from the Condensate Storage Tank via Core Spray by opening the Core Spray Inlet Header Valves V-20-1 and V-20-2 in the Reactor Building SW corner room, -19 foot elevation.

b. Line up the Fire Water system for injection to Core Spray Loop 1 by opening V-20-83, fire water supply outside the reactor building, 23 foot, North side.

c. Line up the Standby Liquid Control System to inject demineralized water from the test tank on the 75 foot elevation of the Reactor Building.

d. Line up the Condensate Transfer System to inject via Core Spray System 1 by opening regulator bypass valves on the 23 foot elevation of the Reactor Building.

25

Oyster Creek 2002 Answer Key 125 Choice Basis or Justification Correct: B Correct, quickest to line up, does not require RB entry, and the co rrct valve location is given.

Distractors: A Plausible, Is a valve lineup, however location is incorrect and no power to CS pumps.

C Plausible, Is a valve lineup but elevation is incorrect. SBLC sys. is on 95 foot elev.

D Plausible, Is a valve lineup but elevation is incorrect and system pressure is to high for cond. transfer system.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2.5 4 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Support Procedures 5, 6, 7, and 56 [2621.845.19]

Learning Objective: 03055, 03058 Terminal Objective: 2000501402 Knowledge/Ability: 295031 G2.1.30 Importance: 3.9/3.4 Reactor Low Water Level. Ability to locate and operate components/including local controls. [PRA related: Core Spray (manual initiation or injection with fire water]

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 Oystr Ceek 002NRC Initial Licensing Exam

26. The reactor experienced a reactor scram due to a load rejection from 100%

power. The CRO reports the following plant conditions:

"* Reactor pressure is 1060 psig

"* All recirculation pumps have tripped

"* Reactor water level is at 100 inches TAF and being lowered

Eight control rods are at notch 48

"* Reactor power is 3%

To manually insert the control rods, place the Mode Selector Switch in 1, Bypass the Rod Worth Minimizer, and 2, the CRD Drive Water Pressure Control Valve (NC-18)

a. (1) Startup (2) Close

b. (1) Startup (2) Open

c. (1) Refuel (2) Close

d. (1) Refuel (2) Open

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

26 Choice Basis or Justification Correct: C Correct for manual insertion Per Support Procedure 21.

Distractors: A Plausible, but the startup mode is incorrect -

B Plausible, but the startup mode is incorrect D Plausible, but the valve must be closed Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2.5 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): EMG-3200.01 b (Power Leg) and Support Procedure 21 [2621.845.19]

Learning Objective: 02257 Terminal Objective: 2000501411 Knowledge/Ability: 295037 EA1.07 Importance: 3.9/4.0 Ability to operate and/or monitor the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN. RMCS: Plant-Specific.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

27. Technical Specifications provide an Off-Gas system isolation setpoint 15 minutes after a high radiation signal.

The bases for the high radiation setpoint is to prevent a plume cloud passing over the individual from causing the individual to exceed:

a. 10mRem a year Gamma dose.

b. 10 mRem a year Gamma and Beta dose.

c. 100 mRem a year Gamma dose.

d. 100 mRem a year Gamma and Beta dose.

97

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

27 Choice Basis or Justification Correct: C Per TS Bases, Section 3.6.E Distractors: A Plausible, Not correct value per IOCFR100 limits.

B Plausible, Not correct value per 10CFR1 00 limits and a Beta dose is not anticipated from shine of a cloud passing over.

D Plausible, Beta dose is not anticipated from shine of a cloud passing over.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 4 5 43.2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS Bases, Section 3.6.E [2621.850.901 Learning Objective: 01661 Terminal Objective: 3410302017, 3410302018 Knowledge/Ability: 295038 EK3.02 Importance: 3.9/4.2 Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE.

System isolations.

Prepared by: Larry Briggs Question Data Sheet

NRC Initial Licensing Exam vltr Creek 2002N Ia e g

28. Given the following: __

"* The plant scrammed from 100% power due to a LOCA with fuel damage.

"* There was leakage of contaminated water into the turbine building

"* An alert has been declared due to an off site release Which one of the following is correct? The turbine building ventilation system.

a. Should be operated normally to maintain Turbine Building temperatures for habitability.

b. Should be secured to prevent a ground level release out the Turbine Building Stack.

c. Should be operated normally to ensure adequate dilution of the gasses discharged through the Main Stack.

d. Should be operated normally to prevent having an unmonitored ground level release.

28

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

28 Choice Basis or Justification Correct: D Per EOP Users Guide, Reactivity Release Control EOP.

Distractors: A Plausible, run to maintain radiological habitability.

B Plausible, securing ventilation will cause radioactivity buildup in building and inhibit personnel access.

C Plausible, normal ventilation concern during routine plant operations.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 3 Source Documentation Source: New Exam Item Old NRC Exam Mod 1999 Exm. #87 Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): EOP Users Guide, Reactivity Release Control EOP. [2621.845.12]

Learning Objective: 01667, 02483 Terminal Objective: 2000502414 Knowledge/Ability: 295038 EA1.06 Importance: 3.5/3.6 Ability to operate and/or monitor the following as they apply to HIGH OFF-SITE RELEASE RATE. Plant ventilation.

Stem and distractors modified extensively.

Prepared by: Larry Briggs Question Data Sheet K

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

29. The plant is at 100% power when annunciator C-8-f,"DW H2/02 SYS A TROUBLE," alarms. The instrumentation technician reports that the "A" H2 analyzer cell has failed. The "B" H2 analyzeris functioning normally. A replacement cell is on order and will be received within 2 weeks.

Which one of the following Technical Specification statements is correct?

a. There is no restriction on plant operations since the "B" H2/02 analyzer was placed into service and is functioning normally.

b. System "A" must be returned to service within 30 days or the plant must be placed into Cold Shutdown within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. System "A" must be returned to service within 7 days or the plant must be placed into Cold Shutdown within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d. Manual H2/02 samples must be taken using the Post Accident Sampling System.

29

Oyster Creek 2002 Answer Key

29 Choice Basis or Justification Correct: B Correct per TS 3.13.F Distractors: A Plausible, Applicant may think no restrictions since repairs will be complete in 2 weeks.

C Plausible, this is condition for both monitors being out of service.

D Plausible, this is specified action in diagnostic procedure if both monitors are OOS Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2 4 X - 43.1 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS 3.13.F [2621.828.651 Leaming Objective: 00930, 00931 Terminal Objective: 2250104501 Knowledge/Ability: 500000 G2.1.12 Importance: 2.9/4.0 HIGH CONTAINMENT HYDROGEN CONCENTRATION. Ability to apply Technical Specifications for a system.

Prepared by: Larry Briggs Question Data Sheet

NRC Initial Licensing Exam vster Creek 2002.

30. Given the following:

"* Reactor power 70%

"* Core flow 9.0 x 10E4 GPM

"* Three Reactor Recirculation loops are operating

Two Reactor Recirculation loops are idle Which one of the following is correct if another Reactor Recirculation Pump (RRP) Trips?

a. lAW ABN-3200.01, Reactor Scram, immediately scram the reactor and trip all RRPs to prevent entering the Exclusion Region.

b. lAW ABN-3200.01, ,Reactor Scram, monitor core flow, if the Exclusion Region is entered then scram the reactor to prevent core power oscillations.

c. lAW ABN-3200.02, Recirculation Pump Trip, monitor core flow, if the Buffer Region is entered then insert Cram Rods to prevent entering the Exclusion Region.

d. lAW ABN-3200.02, Recirculation Pump Trip, verify the tripped RRP discharge isolation valve is open, then close the valve to prevent backflow through the loop.

30

NRC Initial Licensing Exam Answer Key

30 Choice Basis or Justification Correct: A Correct per ABN-3200.02, Recirculation Pump Trip Distractors: B Plausible, Partially correct, insert Cram Rod to-exit Exclusion Region. This is for a trip when 4 or 5 RRPs are operating C Plausible, partially correct for a trip if4 or 5 RRPs running, insert Cram Rods if Exclusion Region is entered.

D Plausible, correct action if a RRP trip when 4 or 5 are running.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 4 4 43.5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): ABN-3200.02, Recirculation Pump Trip [2621.828.381 Learning Objective: 00226 Terminal Objective: 2020402001 Knowledge/Ability: 295001 AK3.04 Importance: 3.4/3.6 Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION. Reactor SCRAM Prepared by: Larry Briggs IC Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

31. Given the following:

"* The plant is at 100% power

"* Alarm 9XF-1 -d, BUS A/B UV has alarmed

"* The MG charger for "B" battery has tripped due to a breaker problem

"* The maximum voltage that the static inverter will supply is 124.0 VDC Which one of the following is correct?

a. TS require that the "B" 125 VDC Battery must be declared inoperable and that the reactor must be placed in cold shutdown within 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. TS allow the reactor to remain in operation for a period not to exceed 7 days out of a 30 day period with one 125 VDC bus inoperable, provided the requirements of TS 3.8 are met.

c. Restore operability of the "B" 125 VDC bus by connecting it to the Static Inverter in accordance with OPS-3024.1 Oc, Electrical Distribution

- 125 VDC Diagnostic and Restoration Actions.

d. Restore operability of the "B" 125 VDC bus by cross connecting the "A" and "B" buses in accordance with System Operating Procedure 340.1, 125 VDC Distribution Systems "A" and "B."

31

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

31 Choice Basis or Justification Correct: A Per TS 3.7.B and 125 VDC diagram, sheet No. 275 Distractors: B Plausible, allowed by TS ifit is the "A" 125 VD-C bus that is inoperable.

C Plausible, the candidate may select this answer because it is a possible action, but the voltage on the Static Inverter is too low to consider the bus operable.

D Plausible, has a cross-tie arrangement but Kirk key interlock prevents both breakers for closing. The breakers are for tying the static charger to either bus.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2.5 3 X-43.1 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): RAP-3024.02, WINDOW 9xf-1-d - TS 3.7 and OPS-3024.10c, 125 VDC Diagnostic &

125 VDC diagram, sheet No. 275. [2621.828.121 Learning Objective: 01117, 01118 Terminal Objective: 2630101004 Knowledge/Ability: 295004 AA2.03 Importance: 2.9/2.9 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C.

POWER. Battery voltage.

Prepared by: Larry Briggs Question Data Sheet

NRC Initial Licensing Exam Ovster Creek 2002NR

32. On a turbine trip, the reheater & intercept valves and the extraction steam check valves isolate.

Which one of the following is the correct reason for these isolations?

a. To prevent moisture carryover from the High Pressure Turbine to the Low Pressure Turbine via the Moisture Separator Reheaters.

b. To minimize cycling of the Auxiliary Flash Tank Drain Pumps due to reheater drain flow control problem on a turbine trip.

c. To prevent the 2nd Stage Reheaters from excessive shell to tube differential temperatures.

d. To prevent turbine overspeed due to backflow from extraction steam and continued steam flow from reheaters.

32 32 :

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam OytrCek20 usinDt SetNCIiilLcnigEa Answer Key

32 Choice Basis or Justification Correct: D Per lesson plan PGD-2621 course 828, lesson 050, Pgs. 22 & 23. Station Procedure 318, Main Steam System and Reheat Steam, Para. 6.2.5, 6.2.8, and Attachment 2.

Distractors: A Plausible, Applicant may assume moisture frofn'the reheater will carryover without continued steam reheat flow.

B Plausible, This is a concern per para. 6.2.8 of Procedure 318.

C Plausible, This is a concern on Startup and low power operation per Procedure 318, Para. 6.2.5 Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): lesson plan PGD-2621 course 828, lesson 050, Pgs. 22 & 23. Station Procedure 318, Main Steam System and Reheat Steam, Para. 6.2.5, 6.2.8, and Attachment 2.

[2621.828.50 & 511 Learning Objective: 01188, 01201,01723 Terminal Objective: 2450101408 Knowledge/Ability: 295005 AK3.05 Importance: 2.5/2.6 Knowledge of the reasons for the following responses as they apply to MAIN TURBINE GENERATOR TRIP.

Extraction steam/moisture separator isolations.

Prepared by: Larry Briggs

,1Qeto Dt he I

Question Data Sheet

NRC Initial Licensing Exam Ovster Creek 2002.N

33. The plant was in the process of reducing power to conduct MSIV surveillance testing. The CRO reports the following:

RPV level has increased to 165 inches TAF

Feed water flow is greater that steam flow

Alarm J-5-d, MFRV LOCK UP (A) has annunciated 0 The auxiliary plant operator reported that an airline in the Feed Pump area has broken and is'leaking air.

Which one of the following is the correct initial response?

a. Implement ABN-3200.35, Instrument Air System Failure Abnormal Operations and repair the broken instrument air line.

b. Reduce reactor power as directed by RAP H-7-e, RX LEVEL HI/LO.

c. Implement OPS-3024.14, Feedwater System - Diagnostic and Restoration Actions, and place MFRV "'A" in local manual operation.

d. Initiate a manual scram lAW ABN-3200.01, Reactor Scram, before a turbine trip occurs at 175 inches TAF.

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

33 Choice Basis or Justification Correct: C Procedure requires taking manual control first then fix air leak Distractors: A Plausible, Applicant may want to fix air leak fir&tbut control of feed is most important and lAW RAP J-5-d.

B Plausible, This will aggravate condition D Plausible, Applicant could take preemptive action but not correct at this point.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 2 X - 43.5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): RAP-J-5-d, MFRV LOCK UP" [2621.828.18]

Leaming Objective: 02194 Terminal Objective: 2590401006 Knowledge/Ability: 295008 AA2.02 Importance: 3.4/3.4 Ability to determine and/or interpret the following as they apply to HIGH REACTOR WATER LEVEL. Steam flow/feed flow mismatch.

Prepared by: Larry Briggs Question Data Sheet'

NRC Initial Licensing Exam r) c~tor flrizk 9002 NCIiilLcnigEa

34. Given the following:

0 The plant is at 75% power and increasing

Alarm C-3-a, PUMP 1-1 TRIP (RBCCW) annunciates 0 RBCCW Pump 1-2 was successfully started

RBCCW temperatures are increasing slowly on Panel 13R Which one of the following is correct?

a. If the condition lasts for more than one minute, scram the reactor and trip all recirculation pumps to prevent damage to the recirculation pumps.

b. Increase Service Water flow to reduce the RBCCW outlet temperature and/or reduce Reactor Water Cleanup System flow rate to reduce heat loads.

c. If one Recirculation Pump CCW FLOW LO alarms, scram the plant immediately, lAW ABN 3200.01, Reactor Scram, to protect the recirculation pump.

d. Monitor Drywell temperature and pressure, vent the Drywell if pressure exceeds 1.6 psig by venting through Drywell Vent Valves V-23-21 and V-23-22 (Panel 12XR) to maintain normal Drywell pressure.

34

Question Data Sheet NRC Initial Licensing Exam Answer Key

34 Choice Basis or Justification Correct: B Per ABN-3200.1 9, RBCCW Failure Response, Section 3.5 Distractors: A Plausible, true if all flow is lost or alarms on m6re than one recirculation pump.

C Plausible, requires alarm on more than one recirculation pump.

D Plausible, This action is taken to maintain pressure between 1.1 and 1.3 psig Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2.5 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): ABN-3200.19, RBCCW Failure Response, RAP C-3-c, PUMP 1-1 TRIP. [2621.828.35]

Learning Objective: 00057, 00065, 07270 Terminal Objective: 2080101403 Knowledge/Ability: 295018 AK3.06 Importance: 3.3/3.3 Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER. Increasing cooling water flow to heat exchangers.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

35. The plant is at full power when a loss of instrument air transient occurs.

In accordance with ABN.3200.35, Instrument Air System Failure, what is the purpose for requiring a reactor scram when Instrument Air pressure reaches 55 psig?

a. To minimize the reactor pressure transient when the MSIVs fail shut.

b. To prevent a hydraulic lock when the Scram Discharge Volume valves fail shut.

c. To prevent uncontrolled rod insertions when the Scram Valves randomly fail open.

d. To ensure sufficient pressure is available to assist the scram before the CRD Flow Control Valve fails shut.

f' I 35

Oyster Creek 2002 Question Data Sheet NRC -Initial Licensing Ex~am Answer Key

35 Choice Basis or Justification Correct: C Per ABN-3200.35, a manual scram is required at 55 psig to prevent uncontrolled rod insertion and avoid fuel damage Distractors: A Plausible, the MSIVs will fail shut, but not until-after the reactor would have scrammed due to low air pressure.

B Plausible, the SDV vent and drain valves will fail shut but this is not the concern.

The actual concern is the Scram Inlet and Outlet valves failing open allowing the rods to scram in a random sequence.

D Plausible, the CRD Flow Control Valve does fail shut, but not until after the rods wvould have already started inserting. Reactor Pressure is adequate at power to insert the rods.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): ABN-3200.35; [2621.828.431 Learning Objective: 00917, 00920 Terminal Objective: 2780401401,2790401403 Knowledge/Ability: 295019 G2.4.48 Importance: 3.5/3.8 Partial or complete loss of Instrument Air. Ability to interpret control room indications to verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions.

Prepared by: Phil Nielsen Question Data Sheet

NRC Initial Licensing Exam Ovster Creek 2002.

36. The plant has recently shutdown for refueling with the following conditions:

"* Shutdown cooling is in operation with the '!C" Shutdown Cooling Pump running

"* "E" Recirculation Loop is in service; all other loops are idle

"* Coolant temperature is 180°F

"* RPV level is 185 inches TAF

"* Torus level 80 inches for Torus coating inspection and maintenance 0 Steam Separator and Dryer have not been removed The following events occur:

4160 VAC bus 1A trips due to a fault on the bus

EDG 1 starts and supplies 4160 VAC bus lC

The CRO reports that reactor temperature is slowly raising.

Which one of the following is the correct action?

a. Per OPS-3024.27, Shutdown Cooling System - Diagnostic and Restoration Actions, Close the "E" recirculation loop discharge isolation valve.

b. Per OPS-3024.27, Shutdown Cooling System - Diagnostic and Restoration Actions, initiate Alternate cooling using one Core Spray pump raise RPV level and open one EMRV to establish core cooling.

c. Per OPS-3024.22, Reactor Recirculation System Diagnostic and Restoration Actions, Start the "A" recirculation pump and open its discharge valve to establish cooling flow.

d. Per OPS-3024.1Oa, Electrical Distribution - 4160 VAC Diagnostic and Restoration Actions, Restore power to Bus 1A lAW Procedure 337, Section 3.2, "Energizing 4160V, Bus 1A From the Startup Transformer."

36

NRC Initial Licensing Exam flster Creek 2002 Question Data SheetN Answer Key

36 Choice Basis or Justification Correct: A Correct per procedure if level is at least 185 inches TAF Distractors: B Plausible, an alternative cooling method in SDC-procedure diagnostic.

C Plausible, viable option but power for recirculation pump is bus 1A D Plausible, viable option except bus 1A tripped due to a fault on the bus.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 4 5 X - 43.5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): OPS-3024.10a, 27, and 22 [2621.828.451 Learning Objective: 00036, 02602 Terminal Objective: 2050101008, 2050401402 Knowledge/Ability: 295021 AA2.07 Importance: 2.9/3.1 Ability to determine and /or interpret the following as they apply to LOSS OF SHUTDOWN COOLING. Reactor Recirculation flow.

Prepared by: Larry Briggs Question Data Sheet

NRC Initial Licensing Exam Oyster Creek 2002 NCIiilLcnigEa

37. Given the following conditions:

"* Plant is shutdown

"* Reactor temperature is 180°F and slowly increasing

"* RPV level is 170 inches above TAF

"* Shutdown cooling has been lost and is not expected to be recovered for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

"* The steam separator and dryer have not been removed

"* All recirculation pumps are secured

"* The "A" recirculation loop suction and discharge valves are open, all other loops are idle

"* Torus level 80 inches for Torus work in progress Which one of the following is the correct action to initiate? Direct the control room operators to:

a. Refer to OPS-3024.27, Shutdown Cooling System - Diagnostic and Restoration Actions, and increase RPV level to greater than 185 inches TAF to establish natural circulation.

b. Refer to OPS-3024.27, Shutdown Cooling System - Diagnostic and Restoration Actions, and establish cooling using the EMRVs.

c. Refer to Procedure 305, Shutdown Cooling System Operation, and close the "A" recirculation loop discharge valve and establish SDC system operation.

d. Refer to Procedure 307, Isolation Condenser System, and reduce RPV level to less than 160 inches TAF and initiate Isolation Condensers.

37

NRC Initial Licensing Exam Answer Key

37 Choice Basis or Justification Correct: A Correct per diagnostic procedure OPS-3024.27. Raising level will allow natural circulation to cool the reactor system.

Distractors: B Plausible, Plausible, a recommended action ifbbove 212°F and Torus level above 90 inches.

C Plausible, a recommended action if "E"loop suction and discharge valves are open and SDC is operable D Plausible, a recommended action ifgreater than 212°F and to augment answer a.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 4 3 43.5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): OPS-3024.27, Shutdown Cooling System - Diagnostic and Restoration Actions

[2621.828.451 Learning Objective: 00036, 02602 Terminal Objective: 2050101008, 2050401402 Knowledge/Ability: 295021 AK1.04 Importance: 3.6/3.7 Knowledge of the operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING. Natural circulation Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Iicensin.,,* , .. m

38. Initially the following conditions exist: -

"* The reactor is at 100% power

"* All control rods are operable

"* CRD hydraulic pump "A" is secured for routine maintenance Then the "B" CRD Pump trips and the following alarms annunciate:

"* Alarm H-2-c, PUMP B OL

"* Alarm H-7-c, CHARG WIR PRESS LO

"* A short time later, Alarm H-8-c, ACCUMULATOR PRESS LO/LEVEL HI annunciates

"* Then an ACCUMULATOR LEVEL/PRESS window energizes on the Rod Block Alarm Display Which one of the following correctly describes the operational implications of this condition?

a. lAW TS, the two control rods with Accumulator trouble alarms are considered inoperable and must be valved out of service.

b. lAW TS, the plant can continue to operate for a period not to exceed 7 days with the CRD hydraulic pumps inoperable.

c. lAW OPS-3024.08, CRD Hydraulic System - Diagnostic and Restoration, one restart of the "B" CRD pump may be attempted.

d. lAW 2000-ABN-3200.01, Reactor Scram, the reactor must be manually scrammed immediately.

38

Question Data Sheet NRC Initial Licensing Exam Oster Creek 2002Q Answer Key

38 Choice Basis or Justification Correct: D An immediate scram is required when the second accumulator trouble alarm is received.

Distractors: A Plausible, rods are considered inoperable ifthey cannot be moved with normal drive pressure B Plausible, This is a true statement, but only ifone CRD pump OOS.

C Plausible, the diagnostic procedures tell the operator to start the stand-by pump.

RAP specifically says not to restart on overload trip of pump.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2 2 X - 43.5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): RAP-H-7-c, TS 3.4.D, OPS-3024.08, Sect. 3.1 [2621.828.11]

Learning Objective: 00020 Terminal Objective: 2010401408 Knowledge/Ability: 295022 AK1.02 Importance: 3.6/3.7 Knowledge of the operational implications of the following concepts as they apply to LOSS OF CRD PUMPS.

Reactivity control.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensina Exam Oyster Creek 2002 NRC Initial Licensina Exam

39. The plant has been taken critical and a heatup is in progress.

"* Plant pressure is 500 psig.

"* Alarm H-7-c, CHARG WTR PRESS LO, has annunciated.

"* The "A" CRD Pump is running.

A significant leak in the common CRD header just before the CRD filters was reported.

"* No Scram Accumulator trouble alarms have annunciated.

Which one of the following is correct?

a. The reactor must be scrammed lAW ABN 3200.01, Reactor Scram, because the CRD seals could be damaged due to loss of cooling flow.

b. The reactor must be scrammed lAW ABN 3200.01, Reactor Scram, while accumulator pressure is sufficient to ensure scram capability.

c. Technical Specifications require the plant temperature to be reduced to less than 212°F under these conditions.

d. Technical Specifications allow continued operation for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to determine if shutdown margin can be met with multiple control rods inoperable.

Question Data Sheet NRC Initial Licensing Exam Oyster Creek 2002 Qeto aaSetNCIiilLcnigEa Answer Key

39 Choice Basis or Justification Correct: B The reactor is required to be scrammed with Reactor Pressure <850 psig and low CRD Charging Water Pressure.

Distractors: A Plausible, should be scrammed but not due to-aconcern for seal damage.

C Plausible, ifthe condition was caused by inoperable CRD pumps. This condition was caused by a leak inthe system.

D Plausible, Multiple Control Rods are not inoperable.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2.5 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): RAP H-7-c [2621.828.111 Learning Objective: 00020 Terminal Objective: 2010401410 Knowledge/Ability: 295022 AK2.07 Imporance: 3.4/3.6 Knowledge of the interrelations between LOSS OF CRD PUMPS and the following. Reactor Pressure (SCRAM assist) Plant Specific.

Prepared by: Larry Briggs Question Data Sheet

NRC Initial Licensing Exam r) ,-tpr Clreek 2002 R nta LcnigEa

40. Given the following:

"* The reactor is operating at 100% power -

"* SBGT System 1 is selected as preferential system

"* Turbine Building Exhaust Fan EF-1-7 is running

"* Radwaste Building Exhaust Fan EF-1-16 is running The following occurs:

"* Alarm 10F-I-f, VENT HI (RADIATION MONITORS PROCESS RX BLDG) annunciates

Both SBGT systems started on the Vent Hi alarm

"* Several minutes later the SBGT System 2 shutdown Which of the following correctly states the operational implications of the above?

a. Shutdown of the SBGT System 2 will result in a significant increase of the radioactive release from the Reactor Building and notification of off site authorities.

b. Verification of the VENT HI alarm will require entry into EMG-3200.11, Secondary Containment Control and entry into EPIP-OC-.01, Classification of Emergency Events.

c. This alarm indicates that a significant release has taken place and will require a Reactor Scram lAW ABN-3200.01, Reactor Scram, and a Reactor Building evacuation.

d. SBGT System 2 must be manually restarted in accordance with Procedure 330, Standby Gas Treatment System, to minimize the Reactor Building release.

1' ! 40

NRC Initial Licensing Exam QuetinDat Seet NRC IuitiaoLcni Exam

40 Choice Basis or Justification Correct: B Per RAP-3024.01, 10F-I-k Distractors: A Plausible, This was normal system response but applicant may not be aware that 2nd system secures once proper operation of preferential system is verified C Plausible, Will require RB evacuation but not a scram based on provided information in stem D Plausible, This not necessary, system is performing properly.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) I SRO H 2.5 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): RAP-3024.01, 1OF-1-k, Procedure 330, Standby Gas Treatment System, Section 4 and 5 [2621.845.111 [2621.828.421 Learning Objective: 01667, 00982 Terminal Objective: 2000501428, 2610501404 Knowledge/Ability: 295034 EK1.02 Importance: 4.1/4.4 Knowledge of the operational implications of the following concepts as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION. Radiation releases.

Prepared by: Larry Briggs

! Question Data Sheet

NRC Initial Licensing Exam Ovster Creek 2002

41. The Reactor Building ventilation is aligned andoperating normally when RB Exhaust Fan EF-1-5 trips.

Which one of the following is correct?

a. Reactor Building supply fans trip and SBGT system automatically initiates at

+1.5 inches water pressure.

b. Reactor Building supply fans will trip and the supply and discharge dampers will close at +1.0 inch of water and the SBGT system must be manually started.

c. The Reactor Building positive pressure spike will the 119 foot elevation blowout panels to fail causing a loss of Secondary Containment integrity.

d. The Reactor Building pressure spike will cause will cause an automatic start of the standby Reactor Building Exhaust Fan EF-1-6 at 1.5 inches of water.

.1 I \

41

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

41 Choice Basis or Justification Correct: B Correct, per lesson plan PGD-2621, Lesson .0042, actions take place at 1.0 inch water.

Distractors: A Plausible, supply fans trip but SBGT system rnut be manually started C Plausible, will get positive pressure spike, but the supply fans will trip limiting the positive pressure.

D Plausible, EF-1-6 does not auto start Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): lesson plan PGD-2621, Lesson .0042 Learning Objective: 00979, 00762 Terminal Objective: 2610501401 Knowledge/Ability: 295035 EK2.02 Importance: 3.6/3.8 Knowledge of the interrelations between SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE and the following. SBGT/FRVS Prepared by: Larry Briggs

- 'I1'f Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

42. Given the following conditions:

"* A rupture of a Core Spray suction line has ocdrred in the NW Corner room.

"* The EO reports that the water level in the NW Corner Room is at least 16 inches deep.

Water levels are normal in all other area.

Which one of the following is correct?

a. One Core Spray loop is inoperable, immediately shutdown the reactor lAW Procedure 203, Plant Shutdown.

b. Two Core Spray loops are inoperable, Scram the reactor and enter EMG 3200.01 a, RPV Control - No ATWS.

c. One Core Spray loop is inoperable; when level is above Max Safe in Two Areas, lAW EMG 3200-11, Secondary Containment Control, then shutdown the reactor.

d. Two Core Spray Subsystems are inoperable, Emergency Depressurization lAW EMG-3200. 11, Secondary Containment Control, is required.

42

Question Data Sheet NRC Initial Licensing Exam n ofi r rn,, k 9flI\ 9 Quesi Data..

biflswer r~uy

42 Choice Basis or Justification Correct: C Inthe No loop for two Max Safes/no primary system discharging. 16" is base of equipment pedestals and the point after which equipment starts to be submerged Distractors: A Plausible, Only one area above max safe.

B Plausible, No primary system discharging into secondary containment.

D Plausible, No primary system discharging into secondary containment.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 2 X - 43.5 Source Documentation Source: New Exam Item Old NRC Exam Modified Bank X #100, 99 audit* Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): EMG-3200.11 Secondary Containment and Radioactivity Release EOP[2621.845.11]

Learning Objective: 03082 Terminal Objective: 2000501431 Knowledge/Ability: 295036 EA2.01 Importance: 3.0/3.2 Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL. Operability of components within the affected area.

Modified all distractors to include procedure reference and bulleted and revised the stem.

Prepared by: S. Sowell, Modified by Larry Briggs Question Data Sheet

Oyster Creek 2002 Oystr Ceek 002NRC Initial Licensing Exam

43. Given the following:

The plant is at full power

Monthly full flow surveillance testing is in progress on Containment Spray System One During testing:

A large ESW leak developed on the inlet piping to the 1-2 Containment Spray heat exchanger

The NE corner room was flooded to a level of 20 inches prior to securing the Containment Spray System (CSS) and the ESW system For the above circumstances, which one of the following is correct?

The TS bases states that to meet the heat removal requirements, flow from one operable CSS pump in:

a. EACH system is required; the LCO allows the reactor to continue to operate for up to 15 days to make repairs.

b. EACH system is required; the LCO allows the reactor to continue to operate for up to 7 days to make repairs.

c. System 2 is sufficient; the LCO allows reactor operation to continue as long as System 2 is fully functional.

d. System 2 is sufficient; the LCO allows the reactor to continue to operate for up to 7 days to make repairs.

Oyster Creek 2002 Question Data Sheet NRC Initial Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Licensing Exam Exam Answer Key

43.

Choice Basis or Justification Correct: D Only one pump required, however LCO does not allow entire system to be OOS Distractors: A Plausible, only one pump in either system OOS operation can continue for 15 days B Plausible, only one pump in either system is necessary for heat removal, 15 days is correct in this case ifthe two pumps are not in the same loop, which they are in this case.

C Plausible, True, only one pump is required, but LCO of 15 days would apply, not unlimited operation.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2 4 X-43.2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS Bases, Section 3.4 and LCO 3.4.C. [2621.828.091 Learning Objective: 00468, 00469 Terminal Objective: 2260104002 Knowledge/Ability: 295036 G2.2.25 Importance: 2.5/3.7 Secondary Containment High Sump/Area Water Level. Knowledge of bases in Technical Specifications for limiting conditions for operations and safety limits.

Prepared by: Larry Briggs I,

Question Data Sheet

Oyster Creek 2002 Oystr Ceek 002NRC Initial Licensing Exam

44. Given the following:

0 There is a fire in the Control Room ventilation system

There is heavy smoke in the control room.

The Halon system has actuated Iftime permits ABN-3200.30, Control Room Evacuation directs the operator to manually scram the reactor and perform the following:

a. Trip all Reactor Recirculation Pumps and close the MSIVs

b. Close the MSIVs and manually start both EDGs

c. Manually start both EDGs and initiate the "A" Isolation Condenser

d. Initiate the "B" Isolation Condenser and trip all BUT one Reactor Feedwater Pump 44

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

44 Choice Basis or Justification Correct: A Correct per ABN-3200.30, Section 3 Distractors: B Plausible, in part correct, EDGs will be verified-to be supplying their loads only if there is a loss of power.

C Plausible, in part correct, the operator is directed to initiate an Iso Condenser but not start the EDGs.

D Plausible, in part correct, should trip ALL feedwater pumps.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): ABN-3200.30, Control Room Evacuation, Section 3. [2621.801.011 Learning Objective: 01408 Terminal Objective: 0180102001 Knowledge/Ability: 600000 AK2.04 Importance: 2.5/2.6 Knowledge of the interrelations between PLANT FIRE ON SITE and the following. Breakers/relays/and disconnects.

Prepared by: Larry Briggs Question Data Sheet

NRC Initial Licensing Exam Oster Creek 2002N

45. Which one of the following, concerning class of fire and the extinguishing agent, is correct.

Class A Class C Class D

a. Water Stream C02 Dry Chemical

b. Water Fog Water Stream Dry Chemical

c. C02 Water Fog Water Stream

d. Dry chemical C02 Water Fog 45

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

45 Choice Basis or Justification Correct: A Correct, only answer where each of the indicated extinguishing agents is acceptable.

Distractors: B Plausible, but would not use a stream of water-tn an electrical fire (Class C)

C Plausible, but would not use a water stream on a burning metal fire (Class D)

D Plausible, but would not use a water fog on a burning metal fire (Class D)

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2 1 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Corporate Safety Book Learning Objective:

Terminal Objective:

Knowledge/Ability: 600000 AAt .08 Importance: 2.6/2.9 Ability to operate and/or monitor the following as they apply to PLANT FIRE ON SITE. Fire fighting equipment used on each class of fire.

Prepared by: Larry Briggs Question Data Sheet

3v.*ter flreek 2002NRIntaLcesnExm~.

NRC Initial Licensing Exam vste Greek 2002....

46. Given the following:

Reactor power 80%

0 Four recirculation loops in service

One recirculation loop is idle The "A" main feedwater pump trips and cannot be restarted.

Which one of the following is correct? Reduce power by:

a. Inserting CRAM rods to avoid exceeding the Minimum Critical Power Ratio.

b. Inserting CRAM rods to avoid entering the Exclusion Region.

c. Reducing Recirculation pump speed as necessary to ensure power is within feedwater pump capacity.

d. Reducing Recirculation pump speed to minimum flow (6.4E4 gpm) to ensure power is within feedwater pump capacity.

46

Oyster Creek 2002 Question Data Sheet Answer Key

46 Choice Basis or Justification Correct: C RAP-3024-01, H-7-e Distractors: A Plausible, could use rods but not fast enough f-omaintain level.

B Plausible, same as "A" D Plausible, reduction to minimum is not recommended and it could cause entry into the Exclusion Region.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): RAP-3024-01, H-7-e and ABN-3200-17, Feedwater System Flow Control Failure S[2621.828.186]

Learning Objective: 00734 Terminal Objective: 2590401006 Knowledge/Ability: 202002 A1.04 Importance: 2.9/2.9 Ability to predict and/or monitor changes in parameters associated with operating the RECIRCULATION FLOW CONTROL SYSTEM controls including. Reactor Water Level.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 Oyster~~ Cre 02NC Initial Licensing F=Y'.m

47. Given the following:

"* Reactor power is 90%.

"* "SPEED CNTRL LOST" annunciates for the "A" Recirculation Pump

"* The red "AIRFAIL" light for the "A" Recirculation Pump illuminates.

Which one of the following is correct for the "A" Recirculation Pump?

a. The I/P converter has failed.

b. The master flow controller has failed.

c. The scoop tube has locked on a loss of control air.

d. The scoop tube has locked on a loss of speed control signal.

47

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

47 Choice Basis or Justification Correct: D Correct, receipt of both alarms indicates a loss of speed control signal per OP 301.2, section 11.0 Distractors: A Plausible, I/P failure will not generate all of the-iTdicated alarms B Plausible, but Master flow controller failure would affect all of the Recirc Pumps.

C Plausible, but you would not receive the "SPEED CONTROL LOST" on a loss of air.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 2 Source Documentation Source: New Exam Item Old NRC Exam Mod. Bank Item #1, NRC audit, 99 Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Op. 301.2, Section 11 [2621.828.401 Learning Objective: 00228 Terminal Objective: 2020101006 Knowledge/Ability: 202002 A3.02 Importance: 3.4/3.4 Ability to monitor automatic operations of the RECIRCULATION FLOW CONTROL SYSTEM including. Lights and alarms.

Modified distractors to eliminate take Local and/or remote control Prepared by: S. Sowell, modified by Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensingi Exam Oyster Creek 2002 NRC Initial Licensinci Exam

48. The following conditions existed at 0800:

"* The plant was operating at 100% power

"* V-14-37, "A" Isolation Condenser (IC) AC Condensate Return valve, was declared inoperable due to a breaker problem.

"* V-14-37 is in its normal position The following conditions occurred at 1000:

"* Alarm C-7-b, SHELL TEMP HI, has annunciated due to a high "A" IC Shell Temperature.

"* Alarm C-6-b, SHELL B LVL HI/LO, annunciated due to a "B" IC level of 7.8 feet Which of the following is required by TS?

a. The "B" IC level must be lowered to normal by 1400 or declare the "B" IC inoperable.

b. The "B" IC isolation valves must be verified operable by 1200 or declare the "B" IC inoperable.

c. V-1 4-37 must be repaired by 1200 or declare the "A" IC inoperable and close all steam inlet and condensate outlet valves.

d. Make-up must be added to the "A" IC to clear the high temperature alarm by 1400 or declare the "A" IC inoperable.

48

NRC Initial Licensing Exam rlvster Creek 2002 Question Data SheetC

48 Choice Basis or Justification Correct: C High temp and a level alarm indicate condensate return valve leakage. TS require the IC to be declared inop within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of V-1 4-37 failure.

Distractors: A Plausible, TS has limitations for level but they &re related to a low-level condition.

B Plausible, "B" IC valves must be verified operable, but the "B" IC would not be declared inop.

D Plausible, system diagnostic procedures require action to clear the high femperature alarm but TS do not.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 2 X - 43.1 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS 3.8 [2621.828.231 Leaming Objective: 02551 Terminal Objective: 2070302401 Knowledge/Ability: 207000 G2.1.33 Importance: 3.4/4.0 Isolation (Emergency) Condenser. Ability to recognize indications for system operating parameters that are entry level conditions for Technical Specifications.

Prepared by: Larry Briggs Question Data Sheet

NRC Initial Licensing Exam Ovster Creek 2002.

49. Given the following:

The reactor was manually scrammed -

Several control rods did not insert

Reactor power remained above 2%

Standby Liquid Control System (SLCS) "A" was manually initiated

G-2-b, "SQUIB VALVE OPEN" has annunciated

No other SLCS alarms have annunciated Which one of the following is correct?

a. SLCS flow is below normal, the required concentration of B-10 will not be injected within the 20 minute design time, reseat the relief valve for the "A" SLCS pump lAW SP-22, Initiating the Liquid Poison System.

b. SLCS flow is below normal, the required concentration of B-10 will not be injected in the 120 minute design time, start the "B" SLCS pump lAW SP-22, Initiating the Liquid Poison System.

c. SLCS flow is normal, the required concentration of B-10 will be injected in the 120 minute design time, no action is necessary.

d. SLCS flow is normal, the required concentration of B-10 will be injected within the 20 minute design time, no action is necessary.

49

NRC Initial Licensing Exam n afa~r (rrok 90l02 Question Data Sheet NCIiilLcnigEa Answer Key

49 Choice Basis or Justification Correct: B Per TS Bases and Support Procedure No. 22.

Distractors: A Plausible, Minimum required injection time is 26minutes not 20 minutes, relief lifting would cause problem as described; however, the procedure requires starting other pump.

C Plausible, Flow is not normal with alarm clear, 120 minute is within the allowable band of times.

D Plausible, Flow is not normal with alarm dear, minimum required injection time is 26 minutes not 20 minutes.

Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Support Procedure 22 and TS Bases 3.2 [2621.828.45]

I *rnnn C'lhi~rfivp" flO3~4_00335.00336. 00338 I mornin C)hum 1..*..1*11 i l I l n*.J V*JVVLI ive:

VV . 00334 I 00335 I 00336 I 00338

..... , ..... l ..... I Terminal Obiective: 2110101004,2110501401,2110502401 Terminal ONective:

Knowledge/Ability: 211000 A2.04 Importance: 3.1/3.4 (b) based on Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTRO SYSTEM; and of those abnormal conditions those predictions, use procedures to correct, control, or mitigate the consequences or operations. Inadequate system flow. [PRA related: Initiation of Boron following ATWS]

Prepared by: Larry Briggs 3.

Question Data Sheet

Oyster Creek 2002 NIP1 Initinl I ir-' r-C

-. *** L*%jI it

" V1 I.- Ai 3 111

50. Given the following:

"* Reactor is at 5 percent power on the Bypass Valves

"* Individual control rod scram time testing is being conducted Procedure 302.2, Control Rod Drive Manual Control System, instructs the operator to immediately remove the scram signal when movement stops or the control rod is fully inserted.

Which one of the following is correct? The individual scram signal is removed:

a. To prevent receiving a scram discharge volume high level scram.

b. To prevent filling the RBEDT through the scram discharge volume vent valves.

c. To allow the scram signal to be reset to drain the scram discharge volume.

d. To allow the brush recorder in the cable spreading room to be secured.

50

Question Data Sheet NRC Initial Licensing Exam Answer Key

50 Choice Basis or Justification Correct: A Correct per Procedure 302.2, Control Rod Drive Manual Control System, Section 9.

Distractors: B Plausible, vent and drain valves remain open, RBEDT would be filling through the drain valves.

C Plausible, SDV drain valves remain open , no scram signal applied.

D Plausible, a normal scram will energize the recorder, but recorder is manually 6ontrolled on individual CRD scram time tests.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Procedure 302.2, Control Rod Drive Manual Control System, Section 9. [2621.828.11 Learning Objective: 00017, 00019 Terminal Objective: 2010101009 Knowledge/Ability: 212000 K4.1 0 Importance: 3.3/3.6 Knowledge of REACTOR PROTECTION SYSTEM design feature(s) and/or interlocks which provide for the following. Individual rod SCRAM testing.

Prepared by: Larry Briggs C,

Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

51. Reactor Protection System (RPS) power supplies are aligned normally when RPS "B" trips due to a fault in the "B" RPS MG Set. Power is restored by taking the POWER SELECT switch to the TRANS position powering RPS "B" from VMCC 1A2.

Operation with this RPS power supply alignment is:

A. Permitted, with no limitations.

B. Permitted, but limited to 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

C. Permitted, but limited to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

D. NOT permitted, RPS "B" must be realigned to VMCC 1B2 immediately.

15 -*, 51

NRC Initial Licensing Exam n os,cmr rrnaL- ?nnq Question Data Sheet NCIiilLcnigEa Answer KeyKey Answer

51 Choice Basis or Justification Correct: C Correct as indicated in GL 91-11 and OPS-3024.10e and Para. 5.2.3 of 408.12 Distractors: A Plausible, lineup is permitted but there are tim6 limitations.

B Plausible, lineup is permitted but there are time limitations. 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months is a standard time used in TS and other procedures.

D IPlausible, since there are limitations but the lineup is permitted.

Metrics Difficulty Time Allowance (minutes) SRO Level of Knowledge F 2.5 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): OPS-3024.1 Ge, Elect. Dist.: RPS Diagnostic and Restoration Actions and Station Procedure 408.12, Oper. of RPS Panel 1-1 and Transformer PS-1, Section 5

[2621.828.37 & .561 Learning Objective: 01167, 02320 Terminal Objective: 2120101001, 2120101301, 2620102001, 2620302401 Knowledge/Ability: ,212000 K1.04 I importance: 3.4/3.b Knowledge of the physical connections and/or cause-effect relationships between REACTOR PROTECTION SYSTEM and the following. A.C. electrical distribution.

Prepared by: Larry Briggs I'

lQuestion Data Sheet

NRC Initial Licensing Exam Ovster Creek 2002

52. Given the following:

"* A reactor startup is in progress

"* Power is in range 7 of the IRMs and steady

"* Source range instruments are being withdrawn as power is increased During the Source Range Monitor (SRM) instrument withdrawal:

"* A fault in SRM "A" drive circuit results in it withdrawing fully from the core

"* SRM "A" indicates 50 CPS Which one of the following is correct?

a. No action is required; control rods can continue to be withdrawn because only two SRM instruments are required during a startup.

b. No action is required; the SRM rod block is bypassed when IRMs are in range 7 or greater because overlap has been verified.

c. A SRM rod block is received due to premature withdrawal of the SRM and the SRM will have to be bypassed so the startup can proceed.

d. A SRM rod block is received to prevent exceeding a local linear heat generation rate in an unmonitored portion of the core; the SRM must be repaired before proceeding.

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

52 Choice Basis or Justification Correct: C Per TS bases, the premature full withdrawal gives a low count rate (<100 CPS) and initiates a rod withdrawal block.

Distractors: A Plausible, Only two SRMs required but will ha)e to take action due to rod block.

B Plausible, bypassed in range 8 D Plausible, rod block is received but not for stated reason.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2.5 3 X - 43.2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS Bases, Pg. 3.1.6, and Station Procedure 401.4, NI Instrumentation - SRM Channel

_ Bypass Operation. [2621.828.29]

Learning Objective: 00023, 00347, 00350, 00356 Terminal Objective: 2150101005 Knowledge/Ability: 215004 G2.1.32 Importance: 3.4/3.8 Source Range Monitor (SRM) System. Ability to explain and apply system limits and precautions.

Prepared by: Larry Briggs QD Question Data Sie et

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

53. Given the following:

"* A reactor startup is in progress

"* Reactor power is 5.5 xl104CPS on all SRMs and slowly increasing Which one of the following correctly describes the operational implications if one of the SRMs cannot be withdrawn?

a. An automatic reactor scram on SRM HI-HI (G-3-d) if the non-coincidence jumpers are installed.

b. A rod withdrawal block will occur at 1 x 105 CPS and remain in effect until one of the IRMs reaches Range 7 AND the affected SRM drawer is placed in INOP.

c. A rod withdrawal block will occur at 1 x 105 CPS and remain in effect until all IRMs are in Range 8 OR the affected SRM is bypassed.

d. The startup must be stopped and held at the current power level until the affected SRM can be repaired by the I&C Technician.

53

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Exam Answer Key

53 Choice Basis or Justification Correct: C Per Station Procedure 401.4, Nuclear Instrumentation - SRM Channels Bypass Operation.

Distractors: A Plausible, SRMs are approaching the 5E5 trip setpoint, but the jumpers are normally installed and must be removed for the non-coincident SRM scram B Plausible, all SRMs must reach range 8 before the SRM rod block is bypassed OR the SRM must be bypassed not placed in INOP.

D Plausible, but startup not required to be stopped Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 2 Source Documentation Source: New Exam Item Old NRC Exam X #18 on 1999 exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Station Procedure 401.4, Nuclear Instrumentation - SRM Channels Bypass Operation.

[2621.828.291 Learning Objective: 00347, 00356, 00358 Terminal Objective: 2150101024, 2150101403 Knowledge/Ability: 215004 K5.03 Importance: 2.8/2.8 Knowledge of the operational implications of the following concepts as they apply to SOURCE RANGE MONITOR (SRM) SYSTEM. Changing detector position.

Used original conditions, stem and all distractor modified.

Prepared by: Joseph M. Milligan, Modified by Larry Briggs I'

/

Question Data Sheet

NRC Initial Licensing Exam Ovster Creek 2002.

54. Given the following:

"* Reactor is operating at 100% power

"* APRMs 1, 2, 3, and 4 indicating lights extinguished on Panels 4F, 3R, and 5R

"* APRMs 1, 2, 3, and 4 indicate downscale on Panels 4F, 3R, and 5R

"* APRM DNSCL OR INOP alarm on Panel 4F Rod Block Display Which one of the following is correct?

a. Power to PSP-1 has been lost; restore 120 VAC lAW OPS-3024.10e, Reactor Protection System - Diagnostic and Restoration Actions.

b. Power to the APRMs has been lost; restore 120 VAC lAW OPS 3024.1 Of, Electrical Distribution - Instrument Power Restoration Actions.

c. Power to the APRMs has been lost; restore the 125 VDC supply lAW OPS-3024.1 Oc, Electrical Distribution - 125 VDC System Diagnostic and Restoration Actions.

d. Power to one channel of Nuclear Instrumentation has been lost; restore 120 VAC power lAW Operating Procedure 403.1, Placing the LPRM-APRM System in Operation.

54 5,*

Question Data Sheet NRC Initial Licensing Exam Answer Key

54 Choice Basis or Justification Correct: A Power to APRMs is from the RPS Distractors: B Plausible, restoration direction is in RPS diagn-otic procedure C Plausible, power is 120 Volt but AC, not DC. DC is supplied to SRM and IRM instruments not APRMs.

D Plausible, Power lost to one channel of APRMs, not the whole NI System.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 4 4 43.5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): OPS-3024.20, NI Diagnostic and OPS-3024.1 0e, Elect. Dist. RPS Diagnostic and Restoration. [2621.828.29]

Learning Objective: 00356, 00360 Terminal Objective: 2150101001,2150101023 Knowledge/Ability: 215005 K2.02 Importance: 2.6/2.8 Knowledge of the electrical power supplies to the following. APRM channels.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

55. The plant was operating at 100% power when the flow transmitter supplying "A" loop flow to the RPS 1 flow summer fails high.

The high flow signal will cause:

a. An APRM half-scram. Refer to OPS-3024.20, Nuclear instrumentation Diagnostic and Restoration to return the flow instrument to service.

b. A Flow Inop half scram. Return to service lAW Plant Operating Procedure 301.2, Reactor Recirculation System.

c. An APRM Downscale Rod Block. Refer to Response Alarm Procedure 3024.01, (G-4-f) APRM DNSCL.

d. A Flow Comparator Mismatch Rod Block. Refer to Response Alarm Procedure 3024.01, (G-5-f) APRM FLO BIAS OFF NORMAL.

55

Question Data Sheet NRC Initial Licensing Exam Ovster Creek 2002 Answer Key

55 Choice Basis or Justification Correct: D RAP G-5-f Distractors: A Plausible, would receive half scram iffailure was downscale B Plausible, would receive half scram iffailure was downscale C Plausible, flow failing upscale would appear that power was lower.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Response Alarm Procedure 3024.01, (G-5-f) APRM Flow Bias Off Normal [2621.828.371 Learning Objective: 01157, 01165, 08658 Terminal Objective: 2120101001/005/310, 2120501403 Knowledge/Ability: 215005 A2.06 Importance: 3.4/3.5 Ability to (a) predict the impacts of the following in the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations. Recirculation flow channels upscale.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial LicensinQ Exam

56. Given the following:

Reactor is operating at 100% power -

Reactor Drywell pressure is 2 psig and slowly increasing

- RX LVL HI/LO (H-7-e) is in alarm

RX LVL LO (Channel II, H-6-e) is in alarm

RE21 B Yarway indicates 130 inches TAF and lowering Which one of the following is correct?

a. There is an instrument variable leg leak in the Drywell, immediately scram the reactor lAW ABN-3200.01, Reactor Scram and enter EMG 3200.01A, RPV CONTROL - NO ATWS.

b. There is an instrument variable leg leak in the Drywell, enter OPS 3024.24, Reactor Pressure Vessel Level Instruments Diagnostic and Restoration Actions and make preparations to shutdown the reactor.

c. There is an instrument reference leg leak in the Drywell, scram the reactor lAW ABN-3200.01, Reactor Scram and enter EMG-3200.02, Primary Containment Control.

d. There is an instrument reference leg leak in the Drywell, enter OPS 3024.24, Reactor Pressure Vessel Level Instruments Diagnostic and Restoration Actions and control RPV level in the normal band.

56

NRC Initial Licensing Exam Answer Key

56 Choice Basis or Justification Correct: B Variable leg leak will give low indication and unisolable leakage will require SD of plant.

Distractors: A Plausible, Scram point is RX LO level of 138.9-inches TAF, however ittakes both channels. An immediate scram is not required.

C Plausible, reference leg leak would give high level reading, primary containment control would be entered at 3.0 psig D Plausible, reference leg leak would give high level reading, there is no actual level decrease.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 3 X - 43.5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): OPS-3024.24, Reactor Pressure Vessel Level Instruments Diagnostic and Restoration Actions and TS Section 3.3.13 L2621.828.55]

Learning Objective: 02042 Terminal Objective: 2160101402 Knowledge/Ability: 216000 G2.4.4 Importance: 4.0/4.3 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures. Nuclear Boiler Instrumentation.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

57. Given the following:

"* The plant is operating at 100% power -

"* I&C reports that High Drywell Pressure Switch PS-RV46A has failed low and a new switch will not be available for at least 2 days Which one of the following is correct?

a. TS requires that ADS capability be restored in one channel within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or reduce reactor pressure to less than 110 psig within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. TS requires that the failed channel initiation signal be placed in the trip condition within 4 days or be less than 110 psig within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. TS permits the affected EMRV to be placed in the "off" position for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to make repairs to the affected EMRV, not to exceed 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months in a 30 day period.

d. TS permits the affected pressure switch to be bypassed per System Operating Procedure 308, Emergency Core Cooling System Operation, for a period not to exceed 7 days in a 30 day period.

57

NRC Initial Licensing Exam 9fl02Question fl~ic4~r Ci~k Data Sheet NCiiilLcnigEa Answer Key

57 Choice Basis or Justification Correct: B TS Table 3.1.1, statement h., and TS 3.4.B.3 Distractors: A Plausible, action if one instr, in each channel ig inop C Plausible, correct statement for EMRV, not inop pressure switch D Plausible, correct procedure for normal lineup of ADS, also MS has lineup for normal operation.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 4 4 43.1 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS Table 3.1.1, statement h., and TS 3.4.B.3 L2621.828.05]

Learning Objective: 00370. 00372 Terminal Objective: 2180101001 Knowledge/Ability: 218000 K6.07 Importance: 3.4/3.5 Knowledge of the effect that a malfunction of the following will have on the AUTOMATIC DEPRESSURIZATION SYSTEM. Primary containment instrumentation.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

58. Given the following:

"* The "A" EMRV lifted due to a spurious signal

"* The operator cycled the EMRV and it appears that the valve has reseated based on tail pipe temperature of 140OF and decreasing Subsequent indications are:

"* Reactor pressure is steady

"* Torus temperature is steady

"* The Alarm SV/EMRV NOT CLOSED has not cleared

"* The "A" EMRV acoustic monitor on panel 15R still indicates that the valve is partially open Based on the above, which one of the following is correct?

a. This is the normal indication for the acoustic monitor following an EMRV actuation.

b. The acoustic monitor has failed and must be repaired within the next 7 days or the reactor must be shutdown within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. The acoustic monitor has failed and must be repaired within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or the reactor must be shutdown within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. The acoustic monitor may be taken out of service without further TS action if the backup EMRV 'Valve Position Indication" is operable.

58

Question Data Sheet NRC Initial Licensing Exam Answer Key

58 Choice Basis or Justification Correct: D Per TS 3.13 Distractors: A Plausible, this is not normal but sensitivity set fob low could cause this.

B Plausible, action if both position systems are inop C Plausible, generic action for failure (TS 3.0.A)

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 4 2 43.1 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS 3.13 and ABN-3200.40, Stuck Open EMRV [2621.828.05]

Learning Objective: 00370, 00372 Terminal Objective: 2180101001 Knowledge/Ability: 218000 A1.02 Importance: 3.7/4.0 Ability to predict and/or monitor changes in parameters associated with operation the AUTOMATIC DEPRESSURIZATION SYSTEM controls including. ADS valve acoustical monitor noise: Plant-Specific.

Prepared by: Larry Briggs Question Data Sheet

NRC Initial Licensing Exam Ovter Creek 2002.

59. Given the following:

Intake temperature is 87 0 F 0 The plant is at 90% power to meet NJ discharge permit temperature limits 0 The "B" EMRV has been leaking by for the last three days

Torus water level is 152 inches

Torus temperature is 950F Which one of the following is correct?

a. Place one Containment Spray System in Torus Cooling per Support Procedure 25.

b. Lower the Torus water level using one Core Spray System lAW Support Procedure 37.

c. lAW TS lower reactor pressure to less than 110 psig within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3

d. lAW TS lower Torus water volume to less than 92,000 ft within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or place the reactor in Cold Shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I I

59

Oyster Creek 2002 Question Data Sheet NRC Initial Licensingl Exam Answer Key

59 Choice Basis or Justification Correct: A Per EMG-3200.02, Primary Containment Control Distractors: B Plausible, this is step to lower level in the Torus C Plausible, would be required if EMRV were inop due to leakage.

D Plausible, true statement if temperature is caused by testing that raises temperature.

Metrics Level of Knowledge IDifficulty Time Allowance (minutes) SRO H 2 3 X- 43.5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): EMG-3200.02, Primary Containment Control [2621.845.061 Learning Objective: 03000 Terminal Objective: 2000501417, 2000502409 Knowledge/Ability: 223002 G2.4.4 Importance: 4.0/4.3 Primary Containment Isolation System/Nuclear Steam Supply Shut-off. Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

Prepared by: Larry Briggs It Question Data Sheet

NRC Initial Licensing Exam Ovster Creek 2002.N

60. Given the following:

"* The reactor was scrammed due to an elevated Drywell pressure

"* Reactor level dropped to 105 inches TAF and is recovering

"* Drywell pressure is 4 psig

"* The high drywell pressure signals to RPS channel II did not actuate.

Which one of the following, concerning the 1-8 sump, is correct?

a. Neither Sump 1-8 isolation valves will close, but the sump pumps trip, preventing the transfer of radioactive liquid outside of the Primary Containment.

b. Both Sump 1-8 isolation valves will close preventing the transfer of radioactive liquid outside of the Primary Containment.

c. Neither Sump 1-8 isolation valves will close, allowing the transfer of radioactive liquid outside of the Primary Containment.

d. One Sump 1-8 isolation valve will close, preventing the transfer of radioactive liquid outside of the Primary Containment.

/ 60

Oyster Creek 2002 Question Data Sheet Answer Key

60 Choice Basis or Justification Correct: C Neither valve will close due to the RPS logic.

Distractors: A Plausible, Applicant may think that one valve i.ý bontrolled by each RPS channel.

B Plausible, Applicant may think the either RPS channel can close both valves.

D Plausible, Applicant may think one valve will close and they are in series..

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3.5 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Drawing 147434 (No. 156) and Dwg. GE 237E566, Sheets 1 thru 6 and Sheets 15 & 16

[2621.828.371 Learning Objective: 02456 Terminal Objective: 2120501401 Knowledge/Ability: 223002 K3.22 Importance: 2.5/2.6 Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on the following. Containment drainage system.

Prepared by: Larry Briggs

.1Qeto Dt he

./ Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

61. Given the following:

The plant experienced a Turbine trip and dri ATWS.

1 EMRV and I Safety valve are open and have failed to reseat

Reactor pressure is 950 psig and rising 0 Reactor level is 158 inches TAF and steady o Two Main Core Spray Pumps and 2 Core Spray Booster Pumps have automatically started

Containment Spray Pump 51A and ESW Pump 52A were started lAW Support Procedure 29, Initiation of Containment Spray System for DRYWELL SPRAY

Containment Spray Pump 51C and ESW Pump 52C were started lAW Support Procedure 25, Initiation of Containment Spray System for TORUS COOLING o Torus water level is 130 inches o Torus water temperature is 100 OF and rising.

Which one of the following is correct for these conditions?

a. Secure Core Spray pumps and start additional Containment Spray pumps as required.

b. Start additional Containment Spray pumps as required in addition to all of the pumps already operating.

c. Secure Containment Spray pumps to allow the continued operation of the Core Spray pumps.

d. Start additional Core Spray pumps as required in addition to all of the pumps already operating.

I6 .* 61

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

61 Choice Basis or Justification Correct: A Only 4 Core Spray/Containment Spray pumps are permitted to operate at one time.

Core Spray pumps are not required for ACC and additional Containment Spray pumps are needed.

Distractors: B Plausible, additional Containment Spray pumps are needed, but only 4 total pumps are permitted C Plausible, conditions require additional Containment Spray pumps, not Core Spray pumps.

D Plausible, but Core Spray pumps are not controlling level with pressure of 950 psig.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3.5 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Support Procedure 29, Initiation of Containment Spray System for Drywell Sprays 1`2621.845.08 & .19]

Learning Objective: 03000, 02257 Terminal Objective: 3450102207, 2090501402 Knowledge/Ability: 226001 K1.01 Importance: 3.4/3.6 Knowledge of the physical connections and/or cause-effect relationships between RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE and the following. Suppression pool.

Prepared by: Larry Briggs Questiori Data Sheet

NRC Initial Licensing Exam Oster Creek 2002

62. Given the following conditions:

The plant has experienced a LOCA inside-containment concurrent with a loss of off-site power

Only one (1) EDG has started and is supplying its 4160 VAC bus Which one of the following combinations of operating equipment is correct for the given conditions?

a. Containment Spray Pump 51A ESW Pump 52A Core Spray Main Pump 1A Core Spray Booster Pump 3C

b. Containment Spray Pump 51 B ESW Pump 52D Core Spray Main Pump 1 D Core Spray Booster Pump 3D

c. Containment Spray Pump 51 B ESW Pump 52A Core Spray Main Pump 1A Core Spray Booster Pump 3D

d. Containment Spray Pump 51 C ESW Pump 52D Core Spray Main Pump 1 B Core Spray Booster Pump 3D I6 62 K.*

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

62 Choice Basis or Justification Correct: C All powered from EDG #1 via Bus 1C and 480 VAC bus 1A2 Distractors: A Plausible, CS Booster Pump 3C powered frorrfEDG2,; all others EDG 1 B Plausible, ESW Pump 52D powered from EDG 2; all others powered from EDG 1 D Plausible, CS Booster Pump 3D powered from EDG 1; all others powered from EDG 2 Metrics Level of Knowledge Difficulty - Time Allowance (minutes) SRO F 2 2 Source Documentation Source: New Exam Item Old NRC Exam X 1999 EX. #61 Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Procedure 341 Section 4.5.3; 6231-PGD-2621 828.0016; 845.0001[2621.828.13]

Learning Objective: 03114, 00814 Terminal Objective: 2620101008, 2640101004, 2640101406 Knowledge/Ability: 226001 K2.02 Importance: 2.9/2.9 RHRILPCI Containment Spray System. Knowledge of electrical power supplies to the following. Pumps Prepared by: Joseph M. Milligan Question Data Sheet

.NRC Initial Licensing Exam Oyster Creek 2002

63. Given the following:

"* The plant experienced a trip that resulted ih a high pressure transient

"* EMRV(s) lifted and appear to have reseated

"* Position 7 on EMRV/Isolation Condenser (IC) Temperature recorder indicates tailpipe temperature reached 250°F and in the last 20 minutes has dropped to 200OF

"* Position 8 temperatures on the EMRV/IC Temperature recorder have remained at 120OF

"* Alarm B-3-g, EMRV OPEN, has cleared

"* Alarm B-4-g, SV/EMRV NOT CLOSED, has cleared You have been directed to determine which EMRVs lifted. Which one of the following is correct?

The EMRV(s) that lifted. can be determined by:

a. Reading the downcomer temperatures recorded on position 7 and 8 of the EMRV/Isolation Condenser recorder on 1 F/2F.

b. Reading the tailpipe temperatures on Panel TE 210 located on the 23 foot elevation in the Reactor Building.

c. Observing the seal-in alarms and listening to the acoustic.monitors at panel 15R.

d. Reading Suppression Pool Bulk Temperature Monitoring System temperature indications at Panel 18R 63

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

63 Choice Basis or Justification Correct: B Panel TE 210 is the only place individual tailpipe temperatures can be monitored.

Distractors: A Plausible, Position 7 reads a common tailpipe temperature for EMRVs A, B & E Position 8 reads C & D C Plausible, lights and acoustics only good while there is steam flow. EMRV not closed alarm comes from acoustics.

D Plausible, EMRV(s) not open long enough to give much increase in pool bulk temperature since tailpipe only went to 250 degrees.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2.5 5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): RAPS B-3-g & B-4-g. Surveillance proc. 602.4.003, 602.4.011, and 604.3.026

[2621.828.051 Learning Objective: 07318 Terminal Objective: 2180404001, 2180201402 Knowledge/Ability: 239002 A4.02 Importance: 3.6/3.7 Ability to manually operate and/or monitor in the control room. Tail pipe temperatures Prepared by: Larry Briggs 1'

Question Data Sheet

,\

Oyster Creek 2002 Oystr Ceek 002NRC Initial Licensing Exam

64. Given the following:

The plant is operating at 50% power -

The turbine inlet pressure is 995 psig

The reactor pressure is 1010 psig Reactor power is being raised to 100 percent with control rods and recirculation flow.

Which one of the following is correct if NO operator action is taken concerning the turbine controls?

a. The Turbine will trip on "25% Load Trip Not Reset" before reaching 100% power.

b. The Turbine Bypass Valves will open before reaching 100% power.

c. An APRM upscale rod block will occur before reaching 100% power.

d. A high pressure reactor scram will occur before reaching 100% power.

64

Oyster Creek 2002 Question Data Sheet NRC Oyster Creek 2002 Question Data Sheet NRC Initial Initial Licensing Licensing Exam Answer Key

64 Choice Basis or Justification Correct: D The reactor will trip on high pressure prior to reaching 100% power Distractors: A Plausible, This will cause a turbine trip on 25%-ibad decrease without resetting, not increasing as stated in this question.

B Plausible, Load Limit is set to greater than 100% when the turbine is started.

C Plausible, APRM rod blocks normally occur when approaching 100% but plant will scram on high pressure before reaching 100%

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3.5 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): [2621.828.511 Learning Objective: 02312, 02313, 02314 Terminal Objective: 2490101003 Knowledge/Ability: 241000 K5.05 Importance: 28129 Knowledge of the operational implications of the following concepts as they apply to REACTOR/TURBINE PRESSURE REGULATING SYSTEM. Turbine inlet pressure vs. turbine load Prepared by: Larry Briggs Question Data Sheet I,

Oyster Creek 2002 Oyste Cree 2002NRC Initial Lirk-n~inr F=~

65. Given the following:

"* The reactor is at 5%, increasing power following a startup

"* RPV level is being controlled on the "A" and "C" Low Flow Regulating Valves (LFRVs)

"* The Master Level Controller (MLC) is in Auto Which one of the following is correct? When the LFRV Manual/Auto (M/A) station is in:

a. MANUAL, the operator sets the LFRV valve position and the MLC maintains the RPV level.

b. AUTO, the operator sets the desired level and the MLC controls level using 3-element control.

c. MANUAL, the operator sets the desired level and the LFRV controller maintains the RPV level.

d. AUTO, the operator sets the desired level and the LFRV controller maintains the RPV level.

65

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

65 Choice Basis or Justification Correct: D LFRV in AUTO controls level at low power Distractors: A Plausible, Operator does set valve position B Plausible, correct except FWCS does not use 3 element at this power C Plausible, in manual the valve position is set, not the level desired.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3.5 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): PGD-2621, 828.0, 0018, pgs 14 & 15 [2621.828.181 Learning Objective: 02389, 02390 Terminal Objective: 2590101008 Knowledge/Ability: 259002 K1.03 Importance: 3.8/3.9 Knowledge of the physical connections and/or cause-effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following. Reactor water level.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

66. Given the following:

"* Alarm 9XF-4-c, "CIP-3 PWR XFER" is in alarm

"* No other alarms are in The electricians have identified and repaired the problem with the motor generator (MG) output breaker and are ready to close it and return the MG set to service.

The IT-3 ABT:

a. Is power seeking and will remain on the alternate source when the MG is returned to service.

b. Is power seeking and will transfer to its normal (MG) source when the MG is returned to service and the ABT is reset.

c. Is normal seeking and will transfer to its normal (MG) source when the MG is returned to service.

d. Is normal seeking and will transfer to its normal (MG) source after the MG is returned to service the ABT is reset.

66

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

66 Choice Basis or Justification Correct: C Correct per lesson PGD-2621-828.0-.0056, Pg. 13 of 21, ABT IT-3 is normal seeking Distractors: A Plausible, Correct for a power seeking ABT B Plausible, correct if a normal seeking ABT D Plausible, Normal seeking does not require reset, power seeking does.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): lesson PGD-2621-828.0-.0056, Pg. 13 of 21 [2621.828.561 Learning Objective: 01066, 01087, 08452 Terminal Objective: 2620101001, 2620101004 Knowledge/Ability: 262001 A3.02 Importance: 3.2/3.3 Ability to monitor automatic operations of the A.C. ELECTRICAL DISTRIBUTION including. Automatic bus transfer.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC R Initial Licensing Exam IiilLcnigEa OytrCek20

67. The plant was operating with no equipment OOS when:

"* A LOCA occurred causing drywell pressure-to rise

"* When the plant was manually scrammed, a loss of off-site power occurred

The EDGs started and supplied power to their emergency busses

Drywell pressure was 5 psig and rising slowly when the EDG 1 ENG TEMP HI annunciator was received.

Which one of the following is correct?

EDG 1 will:

a. Continue to supply the electrical loads on bus 1 C.

b. Immediately trip and deenergize the loads on bus 1 C.

c. Supply the loads on bus 1C for 60 seconds and then deenergize the loads on bus lC.

d. Immediately trip and the loads on bus 1C will be automatically reenergized from EDG 2.

67

NRC Initial Licensing Ex~am r)reek ster 2002 Question Data SheetN Answer Key

67 Choice Basis or Justification Correct: A High Temperature shutdown is bypassed on a fast start so the loads will continue to have power.

Distractors: B Plausible, there is a high temperature trip, but itis bypassed with a fast start C Plausible, there is a high temperature trip, but it is bypassed with a fast start, 60 second time delay exists between the annunciator in the question and an EDG shutdown D Plausible, there is a high temperature trip, but the high temperature shutdown is bypassed on a fast start and bus lC is not auto transferred to EDG 2 Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): PGD-2612, 828.0, No. 13, Emergency Diesel Generators Learning Objective: 00792 Terminal Objective: 2640601001 Knowledge/Ability: 264000 K3.03 Importance: 4.1/4.2 Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESEL/JET) will have on the following. Major loads powered from electrical buses fed by the emergency generator(s).

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Oyster Creek 2002 NRC Initial Licensing Exam Exam

68. Given the following:

"* The plant experienced a LOCA

"* Drywell pressure is 5 psig

"* EDG 1 and 2 are running when the EDG 1 DISABLED annunciator alarms due to low lube oil pressure Which one of the following is correct? The No. 1 EDG will:

a. Shutdown immediately and lockout.

b. Continue to run until the motor is damaged.

c. Idle at 400 RPM for 90 seconds then shutdown.

d. Immediately reduce RPM to idle speed then shutdown.

68

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

68 Choice Basis or Justification Correct: A Correct, the EDG will shutdown because a High Drywell Pressure provides an "Idle Start" signal, not a fast start. Low Lube Oil Pressure provides a trip under these conditions.

Distractors: B Plausible, low lube oil press is NOT bypassed Wvith an "Idle Start" signal.

C Plausible, EDG will be at 400 RPM on hi Drywell pressure start D Plausible, this is correct answer if EDG were supplying the 4160 VAC bus.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) I SRO H 3 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): lesson plan PGD-2621-828-.0013, Pgs. 26-29. [2621.828.131 Learning Objective: 00406, 00792, 00801 Terminal Objective: 2640101004, 2640101406 Knowledge/Ability: 264000 K6.03 Importance: 3.5/3.7 Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEL/JET). Lube oil pumps.

Prepared by: Larry Briggs I,

Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

69. Given the following:

"* Preparations for reactor startup are in progress

"* Plant is cold shutdown The reactor operator adjusts the CRD cooling water pressure for 15 psig above cold shutdown reactor pressure.

As reactor pressure is increased during the startup, how is the cooling water pressure differential maintained?

a. The cooling water flow control valve must be manually adjusted to maintain the 10 to 25 psig delta pressure.

b. The cooling water flow control valve will automatically adjust to maintain the 15 psig delta pressure.

c. The drive header pressure is maintained 250 psig above reactor pressure, which maintains cooling water delta pressure.

d. The drive header pressure automatically maintains 250 psig above reactor pressure, which maintains cooling water delta pressure.

"69

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

69 Choice Basis or Justification Correct: C Once adjusted the cooling water valve acts like a fixed orifice, maintaining the required pressure as long as the drive water delta pressure is maintained.

Distractors: A Plausible, the cooling water flow control valve rs-a manual valve but itdoes not require adjustment to maintain pressure.

B Plausible, the cooling water flow control valve does not automatically adjust the pressure.

D Plausible, pressure is maintained by maintaining drive water delta pressure, but the drive water header pressure control valve must be manually adjusted to maintain pressure.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2.5 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Procedure 302.1, Control Rod Drive Hydraulic System, section 6 and 3. [2621.828.111 Learning Objective: 00018 Terminal Objective: 2010101002 Knowledge/Ability: 201001 A4.05 Importance: 2.7/2.8 Ability to manually operate and/or monitor in the control room. Cooling water header pressure control valve.

Prepared by: Larry Briggs

./ Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

70. Given the following:

"* The first plant startup of the year is in progress

"* Reactor power is 7%

"* Rod withdrawals are in progress to increase power

"* All systems are aligned and operating normally for this power level When the reactor operator selects the next control rod within the group, the Rod Worth Minimizer (RWM) failed.

Which one of the following is correct?

a. The RWM may NOT be bypassed and the plant startup may NOT continue until the RWM is returned to service lAW Procedure 409, Operation of the RWM.

b. The RWM may be bypassed and the startup may continue lAW Procedure 201, Plant Startup. A second licensed operator and additional Reactor Engineering assistance are NOT required.

c. The RWM may be bypassed and the startup may continue lAW Procedure 201, Plant Startup after a second licensed operator is stationed. No additional Reactor Engineering assistance is required.

d. The RWM may be bypassed and the plant startup may continue lAW Procedure 201, Plant Startup after a second licensed operator and a Reactor Engineer are stationed.

K 70

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

70 Choice Basis or Justification Correct: C correct per Procedure 201 and TS 3.2.

Distractors: A Plausible, correct action if less than 12 rods oLt-and 2nd startup of year.

B Plausible, SU may continue but 2nd operator is required.

D Plausible, Same as "B" but RE is not required.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2.5 5 43.5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Procedure 201, Plant Startup and TS 3.2 [2621.828.411 Learning Objective: 01309 Terminal Objective: 2140101003 Knowledge/Ability: 201006 A2.07 Importance: 2.5/2.8 Ability to (a) predict the impacts of the following on the ROD WORTH MINIMIZER SYSTEM (RWH) (PLANT SPECIFIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations. RWM hardware/software failure: Plant specific.

Prepared by: Larry Briggs Ouestion Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

71. Given the following:

"* The reactor is operating on three loops

"* Two loops are Idle

"* All other equipment is operating normally You have directed the CRO to increase recirculation flow to the maximum possible to obtain the maximum reactor power.

While increasing flow the MG OL A (E-3-c) alarm annunciates.

Which one of the following is correct? The "A' Recirculation Pump MG set:

a. Speed must be lowered to reduce the over current condition and clear the OL alarm.

b. Is about to trip, scram the reactor and trip the remaining Recirculation Pumps.

c. Has tripped, scram the reactor and trip the remaining Recirculation Pumps.

d. Has tripped, verify loop isolation valve position and close the "A" loop discharge valve and verify bypass valve is open.

71

Oyster Creek 2002 Question Data Sheet Oystr Ceek200 Quetio Daa SeetNRC Initial Licensing Exam Answer Key

71 Choice Basis or Justification Correct: A Per RAP E-3-c, MG OL A Distractors: B Plausible, same as "C" but anticipating trip with manual action C Plausible, This is action required if pump MG trips when on 3 loops D Plausible, this is action if a recirculation pump trips when more that 3 loops are 6perating Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): RAP E-3-c, MG OL A [2621.828.38i Learning Objective: 00220, 00226 Terminal Objective: 2020101006 Knowledge/Ability: 202001 A3.09 Importance: 3.3/3.3 Ability to monitor automatic operations of the RECIRCULATION SYSTEM including. MG set trip: Plant-Specific.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Ex~am OystrCre202NCniilLcnigEm

72. Given the following:

"* Plant is at 100% power

"* All systems functioning normally A 50 GPM tube leak develops in one of the Regenerative Heat Exchangers.

How will this affect the Reactor Water Cleanup System (RWCU) operation?

a. Water being returned to the reactor coolant system will re-enter the RWCU system and result in lower Demineralizer inlet temperatures.

b. Water entering the RWCU system from the coolant system will bypass the RWCU system resulting in lower Demineralizer inlet temperatures.

c. Water entering the RWCU system from the coolant system will bypass the RWCU system resulting in a 50 GPM flow rate reduction through the cleanup system.

d. Water being returned to the coolant system will re-enter the RWCU system resulting in a 50 GPM flow rate increase through the cleanup system.

/, 72

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

72 Choice Basis or Justification Correct: A Higher pressure on return side of Regen Heat exchanger will put colder water into RWCU lowering temperature through Non Regen and into the demins.

Distractors: B Plausible, Leakage cannot go from inlet to coo]zint system due to delta pressure.

C Plausible, Leakage cannot go from inlet to coolant system due to delta pressure.

D Plausible, but flow rate will not increase due to control valve ND-11 Metrics Level of Knowledge Difficulty iTime Allowance (minutes) SRO H 3.5 6 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): GE 148F144, Clean-up Demineralizer System (Print No. 108) [2621.828.39]

Learning Objective: 00277, 08216 Terminal Objective: 2040101011 Knowledge/Ability: 204000 K5.04 Importance: 2.712.7

'Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER CLEANUP SYSTEM. Heat exchanger operation.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

73. Given the following:

"* The reactor has recently been shutdown

Cool down is in progress

"* Reactor temperature is 340°F

"* Shutdown cooling has just been placed in service

"* "A" recirculation pump is running

"* All other loops are idle The "N' recirculation pump tripped.

Which one of the following is correct?

a. Reactor temperature will increase and loop temperatures will decrease due to flow bypassing the core.

b. Backflow through the idle loops will cause the SDC System to isolate at 350°F loop temperature.

c. SDC system will isolate and the pumps will trip due to high pressure as the pressure increases with the reactor heat up.

d. SDC pumps will trip due to pump low suction pressure when the recirculation pump tripped.

73

Oyster Creek 2002 Question Data Sheet Answer Key

73 Choice Basis or Justification Correct: A Core flow is bypassed when the "A"recirc pump trips, allowing temp. in the reactor to increase and SDC system temps. to decrease.

Distractors: B Plausible, Backflow will happen in idle loops bi-tfit will be cold SDC system water not the hot water in the reactor.

C Plausible, May get a pressure transient from the trip but SDC does not isolate on high pressure.

D Plausible, There is a low suction pressure trip, but well below current plant 6onditions.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Station Procedure 305, Shutdown Cooling System Operation, Section 4[2621.828.451 Learning Objective: 00039, 07234 Terminal Objective: 2050101008 Knowledge/Ability: 205000 K1.03 Importance: 3.4/3.5 Knowledge of the physical connections and/or cause-effect relationships between SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) AND THE FOLLOWING. Recirculation loop temperature.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensing Exam

74. Given the following:

"* The reactor scrammed due to a spurious MSIV closure

"* Pressure is being controlled by use of EMRVs

"* Containment Spray (CS) System 1 (one CS pump and one ESW pump) has been placed in service (Torus cooling mode)

The plant subsequently experienced a loss of off-site power; both EDGs start and energize the 1C and 1D bus.

Which of the following is correct? Containment Spray System 1 and it's associated ESW pump:

a. Will automatically restart immediately after power is restored to their bus.

b. Will automatically restart after a 3 minute (approximate) time delay after power is restored to their bus.

c. May be manually restarted after a 3 minute (approximate) time delay after power is restored to their bus.

d. May be manually restarted immediately after power is restored to their bus.

74

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Ex~am Answer Key

74 Choice Basis or Justification Correct: C Correct per Procedure 341, Emergency Diesel Generator Operation, Section 4.

Distractors: A Plausible, applicant may assume auto restart sinrce pumps were running when power was lost. This restart used to be automatic.

B Plausible , applicant may assume auto restart after time delay since pumps were running when power was lost. This restart used to be automatic.

D Plausible, may assume manual restart OK immediately following restoration of Iower to the bus.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Procedure 341, Emergency Diesel Generator Operation, Section 4. [2621.828.13 & .091 Learning Objective: 00814, 00471, 02221 Terminal Objective: 2640104002, 2260104002 Knowledge/Ability: 219000 K6.01 Importance: 3.2/3.3 Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE. A.C. electrical power.

Prepared by: Larry Briggs Question Data Sheet i

Oyster Creek 2002 NRC Initial Licensina Exam Oyster Creek 2002 NRC Initial Licensina Exam

75. Which one of the following does NOT provide protection for the Main Generator?

a. Stator Cooling Water Failure runback

b. Anti-Motoring trip

_c. Overexcitation trip

d. Stator Ground trip I7

' 75

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

75 Choice Basis or Justification Correct: B Anti-Motoring trip is to protect the prime mover Distractors: A Plausible, protects generator C Plausible, protects generator D Plausible, protects generator Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3.5 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): ABN-3200.1 0, Attachments 1 and 2 and Lesson PGD-2621, .0025 [2621.828.25]

Leaming Objective: 01196, 01201,01212 Terminal Objective: 2480101406 Knowledge/Ability: 245000 K4.06 Importance: 2.7/2.8 Knowledge of MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS design feature(s) and/or interlocks that provide for the following. Generator protection.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensinci Exam

76. Reactor power is 70% when .the "B" feedwater heater string must be removed from service to repair a leaking feedwater heater drain valve.

After the removal of the heater string from service, which of the following describes the response of the:

feedwater temperature to the reactor and

the 1B3 feedwater heater shell pressure

a. " Feedwater temperature to the reactor rises Feedwater heater shell pressure rises

b. Feedwater temperature to the reactor lowers Feedwater heater shell pressure rises

c. Feedwater temperature to the reactor-rises Feedwater heater shell pressure lowers

d. Feedwater temperature to the reactor lowers Feedwater heater shell pressure lowers 76 ,\

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

76 Choice Basis or Justification Correct: D Per Procedure 317.1, Feedwater Heaters Distractors: A Plausible, Feed temp and shell pressure will lower.

B Plausible, Feed temp lowers C Plausible, Shell pressure lowers Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Procedure 317.1, Feedwater Heaters, Section 4 [2621.828.171 Learning Objective: 00727, 00734 Terminal Objective: 2600202005, 2600202402 Knowledge/Ability: 259001 A1.02 Importance: 3.2/3.3 Ability to predict and/or monitor changes in parameters associated with operating the REACTOR FEEDWATER SYSTEM controls including. Feedwater inlet temperature.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensina Exam Oyster Creek 2002 NRC Initial Licensina Exam

77. Given the following:

The plant was operating at 100% power, when -alarm B-5-g, EMRV POWER LOST/DISABLED annunciated. The Equipment Operator reported that breakers 1 and 3 (ADS system feeder breaker to ER-1 8A and B) in Panel DC-F have tripped and cannot be closed.

Which one of the following is correct?

a. TS-require the plant to be placed in the cold shutdown condition due to the loss of DC-F control power.

b. TS Limiting Condition for Operation does not apply since all EMRVs are operable.

c. TS allow continued operation for up to 3 days provided the Isolation Condensers are verified operable.

d. TS require reactor pressure to be reduced to 110 psig or less, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I'"

'I 77

Oyster Creek 2002 Question Data Sheet Answer Key

77 Choice Basis or Justification Correct: B Per RAP B-5-g, the alternate DC supply maintains ADS operability.

Distractors: A Plausible, correct action if panel DC-F is lost.

C Plausible, correct action ifonly 4 ADS valves are operable.

D Plausible, correct action if less than 4 ADS valves are operable.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 4 3 X - 43.1 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS 3.4 and 3.7 and RAP B-5-g [2621.828.051

-Learning Objective: 00370, 00372 Terminal Objective: 2180101001 Knowledge/Ability: 262002 G2.1.33 Importance: 3.4/4.0 Uninterruptible Power Supply (AC/DC). Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

Prepared by: Larry Briggs A Question Data Sheet

NRC Initial Licensing Exam Oster Creek 2002N

78. Given the following:

"* Plant is at 100% power -

"* Normal power to CIP-3 has been lost due to a fault in the generator

"* Auto transfer switch IT-3 failed to automatically transfer Which one of the following is correct?

a. A partial Drywell isolation will occur resulting in a loss of RBCCW to the Recirculation Pump seals.

b. A Reactor Water Level transient should be expected due to loss of control by the Digital Feedwater/Recirculation Control System computer.

c. The reactor will scram due to a loss of main condenser vacuum when the off-gas and condenser off-gas air extraction valves isolate.

d. The reactor will scram due to MSIV closure when solenoid power is lost.

78

Oyster Creek 2002 Question Data Sheet n eNRC Initial Licensin Exam Answer Key

78 Choice Basis or Justification Correct: C Off gas and air extraction valves isolate and will result in a loss of vacuum if power is lost for several minutes.

Distractors: A Plausible, Partial isolation does occur but RBCCW is not isolated.

B Plausible, a level transient is expected when CIP-3 is re-energized, not on a loss of CIP-3.

D Plausible, MSIV position indication is lost, requires DC solenoids to de-energize also to close MSIVs Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3.5 4 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): OPS-3024.1Of, Electrical Distribution - Instrument Power Restoration Actions.

[2621.828.56]

Leaming Objective: 01085, 01101 Terminal Objective: 2620302401 Knowledge/Ability: 262002 K3.14 Importance: 2.8/3.1 Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER SUPPLY (AC/DC) will have on the following. Reactor Power (Plant Specific)

Prepared by: Larry Briggs I',

Question Data Sheet I

,\N

Oyster Creek 2002 NRC Initial Licensing Exam Oyster Creek 2002 NRC Initial Licensina Exam

79. Given the following:

The plant is at full power

125 VDC Power panel DC-2 was lost Which one of the following is correct?

a. CRD pump "A" will trip on low suction pressure, if running.

b. RWCU system will automatically isolate.

c. Main Turbine DC Emergency Bearing Oil pump loses power.

d. "B" Isolation Condenser DC Steam Inlet Valve loses power.

79

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

79 Choice Basis or Justification Correct: D Correct per OPS-3024.1 Oc, page 55.

Distractors: A Plausible, This would occur if 125 VDC panel "F" is lost (pg 40 of 3024.1Oc).

B Plausible, This would occur if 125 VDC panel "F" is lost (pg 40 of 3024.10c)

C Plausible, This is required if 125 VDC panel "AX is lost (pg 9 of 3024.1Oc)

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): OPS-3024.1Oc, Electrical Distribution - 125VDC Diagnostic and Restoration Actions.

[2621.828.12]

Leaming Objective: 01109, 01121 Terminal Objective: 2620401401 Knowledge/Ability: 263000 K2.01 Importance: 3.1/3.4 Knowledge of electrical power supplies to the following. Major D.C. loads.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

80. The Augmented Off Gas (AOG) System alarm BLOWER A H2 HI (10XF-6 e) has annunciated.

Which one of the following is correct concerning the TS Bases for the above alarm limit?

a. The limit is set to ensure that a potentially explosive mixture of Hydrogen is maintained below the flammability limit of H2 in air.

b. The limit is set to ensure that any H2 leakage from the AOG system will not result in an explosive concentration in the AOG building.

c. The H2 limit ensures that a Hydrogen explosion will not occur in the AOG system, which is not designed to withstand a Hydrogen explosion.

d. The H2 limit ensures that Hydrogen concentration will not adversely affect the removal of radioactive effluents by the AOG system.

80

Oyster Creek 2002 Question Data Sheet Answer Key

80 Choice Basis or Justification Correct: A Per TS 3.6 Bases, Page 3.6.6 Distractors: B Plausible, leakage could result in explosive miifure but not in TS basis C Plausible, AOG system is designed to withstand internal explosion D Plausible, but H2 does not affect the removal of radioactive effluents.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 3 X-43.2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS 3.6 Bases, Page 3.6.6 [2621.828.041 Learning Objective: 01661 Terminal Objective: 3040102001 Knowledge/AsbSytem Koldef

. bases Imi ont ins f tio7nsand ey Knowledge/Ability: 271000 G2.2.25Imotne2.37 Offgas System. Knowledge of bases in Technical Specifications for limiting conditions for operations and safety limits.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 Creek Oyster 2002.NRC Inifini I ir'llninr, I=,.-l

81. Given the following:

"* The reactor is operating at 80% power

"* Spent Fuel Pool Cooling is in service on'the "A" SFP Cooling heat exchanger

"* RBCCW surge tank level is increasing slowly

"* Chemistry reports that RBCCW activity has increased

"* F18 was present in the sample Which one of the following is correct? The leak is from:

a. The "A" SFP Cooling Heat Exchanger

b. The Cleanup System Regenerative Heat Exchanger

c. One of the Recirculation. Pump Seal Coolers

d. One of the Shutdown Cooling Heat Exchangers 81

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

81 Choice Basis or Justification Correct: C Per OPS-3024.21, Reactor Building Closed Cooling Water System - Diagnostic and Restoration Actions, the presence of F18 indicates it is primary coolant.

Distractors: A Plausible, would not have F1 8 B Plausible, no RBCCW going to Regenerative Heat exchanger D Plausible, source of leakage but SDC is not in service Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): OPS-3024.21, Reactor Building Closed Cooling Water System - Diagnostic and Restoration Actions, Section -4.1 [2621.828.351 Learning Objective: 00058, 00062 Terminal Objective: 2080101009, 2080401007 Knowledge/Ability: 400000 K1.04 Importance: 2.9/3.1 Knowledge of the physical connections and/or cause-effect relationships between CCWS and the following.

Reactor coolant system, in order to determine source(s) of RCS leakage into CCWS (RBCCW or TBCCW at Oyster Creek).

Prepared by: Larry Briggs i,

Question Data Sheet

Oyster Creek 2002 Oyste Cree 2002NRC Initial Licensint, Exam

82. The Control Rod Drive Mechanism design provides for Rod Position Indication by:

a. Providing an internal wet tube that houses a movable position indication probe that moves reed switches past a fixed magnet.

b. Providing an internal wet tube that houses a fixed position indication probe with a movable magnet attached to the drive piston.

c. Providing an internal dry tube that houses a fixed position indication probe with a movable magnet attached to the drive piston.

d. Providing an internal dry tube that houses a movable position indication probe that moves reed switches past a fixed magnet.

82

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

82 Choice Basis or Justification Correct: C Correct per PGD-2621-828.0-0036, Reactor Manual Control System, page 2 of 9.

Distractors: A Plausible, probe is fixed not movable and is in adry tube.

B Plausible, Same as "A" D Plausible, probe is fixed.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2.5 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): PGD-2621-828.0-0036, Reactor Manual Control System, age 2 of 9. [2621.828.36]

Learning Objective: 00078 Terminal Objective: 2140101003 Knowledge/Ability: 201003 K4.05 Importance: 3.2/3.3 Knowledge of CONTROL ROD AND DRIVE MECHANISM design feature(s) and/or interlocks that provide for the following: Rod position indication.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

83. Given the following:

0 The plant isat 100% power 0 A TIP trace on channel 2 is in progress The following transient occurs:

A LOCA and a plant scram

Two minutes later Drywell pressure is 10 psig and rising

The TIP Channel 2 "IN SHIELD" lamp is out

The TIP Channel 2 "REVERSE" lamp is out

The TIP Channel 2 "BALL VALVE CLOSED" lamp is out

The TIP Channel 2 "PURGE LAMP" is lit Which one of the following, per Procedure 405.2, Operation of the TIP System, is correct?

a. The Control Room Operator (CRO) must place the Channel 2 shear valve keylock switch to "FIRE"

b. The CRO must place the BALL VALVE Manual Control Switch to "CLOSE"

c. No action is required, as long as the PURGE VALVE indicates "CLOSED"

d. The Equipment Operator must manually withdraw the TIP probe "83

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

83 Choice Basis or Justification Correct: A Per Station Procedure 405.2, Operation of the TIP System, Section 5.14.

Distractors: B Plausible, but Ball valve cannot be closed if TIP is not withdrawn.

C Plausible, part of containment isolation took place.

D Plausible, hand crank would be too slow to ensure containment integrity.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 4 2 Source Documentation Source: New Exam Item Old NRC Exam Modified Bank Item X #38 on 1999 audit Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Station Procedure 405.2, Operation of the TIP System, Section 5.14[2621.828.29]

Learning Objective: 09563, 09565, 09566 Terminal Objective: 2150101005 Knowledge/Ability: 215001 K6.04 Importance: 3.1/3.4 Knowledge of the effect that a loss or malfunction of the following will have on the TRAVERSING IN-CORE PROBE. Primary containment isolation system: Mark I&ll (Not BWR1)

Modified Stem and changed two of the distractors.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 Oyster.Creek.2002 NRC Initial Licensing Fvnm

84. Given the following:

"* The Main Turbine shell is being warmed using the No. 2 Stop Valve Internal Bypass

"* The MPR setpoint is being maintained at 100 psig above reactor pressure The operator opens the No. 2 Stop Valve Internal Bypass, which results in the i stage reheater extraction steam pressure reaching 200 psig.

Which one of the following is correct?

a. The Control Valves will automatically close and must be reopened by the operator to continue the main turbine heatup.

b. The main turbine will trip and reactor pressure will be controlled on the Bypass Valves.

c. The operator must throttle the No. 2 Stop Valve Internal Bypass to prevent exceeding the temperature limits of the 1 st stage reheater.

d. The reactor will scram and the operator must close the No.2 Stop Valve Internal Bypass to prevent depressurizing the reactor.

I,/

84 t

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

84 Choice Basis or Justification Correct: D A reactor scram will occur when the Turbine Stop Valve Closure Scram Bypass is un-bypassed because the system senses pressure equivalent to 30% power.

Distractors: A Plausible, although this would limit the transient, control valves will not automatically close B Plausible, because power is <30% in given conditions, however 200 psig on the reheater indicates >30% power and causes a reactor scram.

C Plausible, too late once 200 psig exceeded. In a recent plant event, the operator did close down on the valve before 100 psig was reached and caused a significant level perturbation, but no reactor scram.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Station Procedure 315.1, Turbine Generator Startup, Section 3.3.12 [2621.828.511 Learning Objective: 01202, 01724, 09521 Terminal Objective: 2450101002, 2450101401 Knowledge/Ability: 239001 A1.08 Importance: 3.8/3.9 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including. Reactor Pressure.

Prepared by: Larry Briggs

.1Qeto Dt he

./ Question Data Sheet

Oyster Creek 2002 Question Data Sheet Oystr Ceek200 Quetio Daa SeetNRC Initial Licensina Exam

85. Given the following:

"* The plant was operating at 100% power when a turbine trip occurred

The reactor FAILED to scram on closure of the stop valves

"* The reactor did scram on high neutron flux Which one of the following concerning Technical Specifications and their Bases is correct?

a. The Reactor Coolant Pressure Safety Limit may have been exceeded and the plant must be placed in Cold Shutdown until an analysis can be performed to determine if the pressure Safety Limit was exceeded.

b. A Limiting Safety System Setting was exceeded and the plant must be placed in Cold Shutdown until an analysis can be performed to determine if the fuel cladding integrity Safety Limit was exceeded.

c. The Reactor High Pressure Safety Valve initiation Limiting Safety System setting was exceeded and the plant must be placed in Cold Shutdown until the fuel can be inspected for damage.

d. A fuel integrity safety limit was exceeded and the plant must be placed in Cold Shutdown until the fuel can be inspected and permission to restart has been granted by the NRC.

Question Data Sheet

Oyster Creek 2002 Question Development Checklist Oystr Ceek 002QuesionDeveopmnt CeckistNRC Initial Licensing Exam Answer Key

85 Choice Basis or Justification Correct: B Per TS 2.1 Bases and TS 2.1.C Distractors: A Plausible, Expect a large pressure spike but will not get to Safety Limit C Plausible, Same as "A"but will not get to Safety setpoint.

D Plausible, Safety Limit analysis ifrequired to see if itwas exceeded. Not supposed to by TS Bases.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2 4 X-43.2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS 2.1 Bases and TS 2.1.C [2621.850.90]

Learning Objective: 01658, 01919 Terminal Objective: 3410302017, 3410302018 Knowledge/Ability: 290002 G2.2.25 Importance: 2.5/3.7 Reactor vessel internals. Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

Prepared by: Larry Briggs I'

Question Developr'nent Checklist

Oyster Creek 2002 NRC Initial Licensing Exam

86. Given the following:

"* The plant has been shutdown and the head-removed

"* One control rod is at notch 02 to check refueling bridge interlocks, all others are at "00"

"* SDC is in service

"* A full core offload has been in progress for several hours

"* Workers are in the Drywell.

The following just occurred:

"* One of two operational SRMs failed

"* One of the Criticality Monitors in the Drywell failed

"* The Fuel Pool temperature is reported to be 11 0°F lAW Procedure 205, Reactor Refueling, which one of the following is correct?

a. Defueling may continue if the control rod is inserted to "00".

b. Defueling may continue with criticality monitors out of service.

c. Defueling must be secured until the failed SRM is returned to service.

d. Defueling must be secured until spent fuel pool temperature is reduced.

86

Oyster Creek 2002 Question Data Sheet NRC NRC Initial Initial Licensing Exam Licensing Exam Oyster Creek 2002 Question Data Sheet Answer Key

86 Choice Basis or Justification Correct: C Per Station Procedure 205, Reactor Refueling, Section 7, two SRMs are required for core alterations Distractors: A Plausible, one rod may be withdrawn up to twc- notches, but do not meet SRM requirements.

B Plausible, if the Drywell evacuated, refueling could continue, but do not meet SRM requirements.

D Plausible, there are limitations for fuel pool temperature, but the temperature is in spec.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 4 X - 43.7 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Station Procedure 205, Reactor Refueling, Section 7, Prerequisites and Precautions and Limitations [2621.81:2.031 Learning Objective: 01132 Terminal Objective: 3410302029 Knowledge/Ability: G2.1.32 Importance: 3.4/2.8 Conduct of Operations. Ability to explain and apply system limits and precautions.

Prepared by: Larry Briggs I,

Question Data Sheet I

Oyster Creek 2002 Oystr Ceek 002NRC Initial Licensing Exam

87. Given the following:

The plant was operating at 100% when a control room fire occurred requiring an evacuation. All of the expected operator actions were completed. An Isolation Condenser was NOT placed in service prior to leaving the control room.

You are the Shift Manager. In accordance with ABN-3200.30, Control Room Evacuation, you would report to the:

a. TSC and coordinate activities to place the Remote Shutdown Panel (RSP) in service and initiate a cooldown using the "A" IC.

b. TSC and coordinate activities to place the RSP in service and initiate a cooldown using the "B" IC.

c. 480 Volt room and direct efforts to place the RSP in service and initiate a cooldown using the "A" IC.

d. 480 Volt room and direct efforts to place the RSP in service and initiate a cooldown using the "B" IC.

,.. 87

Oyster Creek 2002 Question Data Sheet NRC Initial Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Licensing Exam Exam Answer Key

87 Choice Basis or Justification Correct: B Per ABN-3200-30, Control Room Evacuation, the SM (& STA) report to the TSC to coordinate activities and place "B" IC in service.

Distractors: A Plausible, the SM.does report to the TSC, but "B" IC is the one placed in service.

C Plausible, Report to TSC not 480 Volt room and the "A" IC cannot be started remotely.

D Plausible, Report to TSC not 480 Volt room Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): ABN-3200-30, Control Room Evacuation [2621.801.011 Learning Objective: 01408 Terminal Objective: 0180102001 Knowledge/Ability: G2.1 .8 Importance: 3.8/3.6 Conduct of Operations. Ability to coordinate personnel activities outside the control room.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

88. Given the following:

9 The reactor is being shutdown lAW Station Procedure 203, Plant Shutdown 0 Reactor power is 10%

0 IRMs have just been inserted and 1 detector reads above 100% on Range 9 0 Reactor pressure is 1010 psig Which one of the following actions is correct lAW Procedure 203, Plant Shutdown?

a. Confirm Recirculation flow is greater than 10.4 X 104 GPM and place the IRM in Range 10.

b. Confirm Recirculation flow is less than 10.4 X 104 GPM and place the IRM in Range 10.

c. Place the Mode switch to Startup and continue the reactor shutdown.

d. Select the IRM and withdraw it from the core until it reads less than 100% on range 9.

88

Oyster Creek 2002 Question Data Sheet Answer Key

88 Choice Basis or Justification Correct: A Per Station Procedure 203, Plant Shutdown, Section 6.47 Distractors: B Plausible, value correct number but flow must be above the value.

C Plausible, one of the following steps after increasing recirc flow.

D Plausible, would have the desired effect, but not recommended in the procedure Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 2 I -

I Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Station Procedure 203, Plant Shutdown, Section 6.47 [2621.832.061 Learning Objective: 00359, 01323 Terminal Objective: 1030102002 Knowledge/Ability: G2.1-.23 Importance: 3.9/4.0 Conduct of Operations. Ability to perform specific system and integrated plant procedures during different modes of plant operations.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam 9

89. Given the following:

e The plant is at 100% power -

"* Two EMRVs have leakage to the Torus and cannot be reseated

"* Torus temperature is 92 0 F and steady

"* One Containment Spray System is in Torus Cooling

"* Reactor Coolant unidentified leakage has increased from 1.5 GPM to 3.8 GPM in the last 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months Which one of the following is correct, based on the above plant conditions?

a. Place a second Containment Spray System in Torus Cooling.

b. Scram the reactor and perform a cooldown.

c. Commence a reactor shutdown to reduce reactor pressure to less than 110 psig within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d. Identify the source of RCS leakage within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or conduct a plant shutdown.

89

Oyster Creek 2002 Question Data Sheet ns DNRC Initial Licensin m Answer Key

89 Choice Basis or Justification Correct: D TS 3.3 requires leakage to be identified within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or SD within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Distractors: A Plausible, but not required until Torus temperature cannot be maintained less than 95 degrees F. Temperature is steady.

B Plausible, but not required under given conditions.

C Plausible, this would be required if 2 EMRVs were inoperable; they are just leaking by.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 4 5 X- 43.1 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS 3.3, TS 3.4.B, TS 3.7, and EMG-3200-02, Primary Containment Control

[2621.850.90]

Learning Objective: 01661 Terminal Objective: 3410302017 Knowledge/Ability: G2.1.6 Importance: 2.1/4.3 Conduct of Operations. Ability to supervise and assume a management role during plant transients and upset conditions.

Prepared by: Larry Briggs Question Data Sheet ,

Oyster Creek 2002 NRC Initial Licensing Exam

90. Given the following:

", The plant is operating at 100% power -

"* The No. 1 EDG is OOS for maintenance on its governor

Core Spray Booster pumps NZ03-A and D are OOS for routine PMs Electrical Maintenance has requested permission to remove the "B" CRD pump from service to repair an oil leak and change the oil.

As the Unit Supervisor you would:

a. Allow the maintenance because the LCO allows continued operation for up to 7 days with one CRD pump inoperable.

b. Allow the maintenance because CRD pumps are not considered safety related.

c. Not allow the maintenance because LCO 3.0.B applies with the Core Spray Booster Pumps also being inoperable.

d. Not allow the maintenance because the "A" CRD pump's emergency power is not available at this time.

90

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

90 Choice Basis or Justification Correct: D TS 3.4.0 and TS 3.7.C. With one EDG OOS the other train must have all components operable.

Distractors: A Plausible, This is LCO for one pump inoperable, but "A" is inop due to the EDG 1 being inop.

B Plausible, CRD pumps are addressed by TS C Plausible, applicant must know Booster pumps are on OOS diesel.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 4 X - 43.1 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): TS 3.4.D and TS 3.7.C [2621.828.111 Learning Objective: 00006, 03304 Terminal Objective: 2010101011 Knowledge/Ability: G2.2.24 Importance: 2.6/3.8 Equipment Control. Ability to analyze the affect of maintenance activities on LCO status.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

91. The maintenance department has prepared a Temporary Modification (TM)

Package and submitted it to Engineering. The Temporary Modification requires installation of blank flanges to isolate-a CRD pump for 4 days for maintenance.

As the Shift Manager conducting a review of the TM, in addition to the Maintenance Risk Assessment and a 50.59 Screening Review, what is the highest additional review required by Station Procedure 108.8, Temporary Modification Control.

a. Second independent 50.59 screening review.

b. Nuclear Safety Review Board (NSRB) review.

c. Plant Operations Review Committee (PORC) review

d. Nuclear Regulatory Commission (NRC) review I~ 91

Oyster Creek 2002 Question Data Sheet NRC NRC Initial Initial Licensing Licensing Exam Exam Oyster Creek 2002 Question Data Sheet Answer Key

91 Choice Basis or Justification Correct: A Per Station Procedure 108.8, Temporary Modification Control Distractors: B Plausible, NSRB would normally be involved irf ATS change not a 50.59 review.

C Plausible, would be required if a 50.59 evaluation was required.

D Plausible, if more than marginal decrease in safety is determined during evaluation.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3.5 4 X - 43.3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Administrative procedures Learning Objective:

Terminal Objective:

Knowledge/Ability: G2.2.10 Importance: 1.9/3.3 Equipment Control. Knowledge of the process for determining ifthe margin of safety; as defined in the basis of any Technical Specification is reduced by a proposed change/test or experiment.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 Oystr Ceek 002NRC Initial Licensing Exam

92. The core was completely off loaded. Which one of the following is required to establish SRM operability for reloading per Procedure 205.0, Reactor Refueling?

a. Load the first 4 bundles around the SRM detector.

b. Place Neutron sources in the core.

c. Adjust the SRM bias to raise the SRM sensitivity.

d. Maintain a dipping cell next to the fuel assemblies being moved.

92 I9

Oyster Creek 2002 Answer Key

92 Choice Basis or Justification Correct: B Placing Neutron sources in the core as fuel is reloaded provides adequate counts to ensure continuing operation of the SRMs by keeping a visible count rate.

Distractors: A Plausible, loading fuel cell adjacent to SRMs in-the control cell is performed first to help ensure count rate remains above I CPS. The four bundles around the SRM would be in four different cells.

C Plausible, this would not be effective in increasing the sensitivity of the detector.

D Plausible, can be done but not at OC Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 2 43.6/7 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Station Procedure 205.0, Reactor Refueling [2621.812.03]

Learning Objective: 01132 Terminal Objective: 3410302029 Knowledge/Ability: G2.2.34 Importance: 2.8/3.2 Equipment Control. Knowledge of the process for determining the internal and external effects on core reactivity.

Prepared by: Larry Briggs J Question Data Sheet

Oyster Creek 2002 Oyster Creek 2002 .n~l Initiml ,-I I irynqrl In r.

93. Given the following:

A reactor startup is in progress -

Rod withdrawal is in progress

A control rod has been withdrawn to notch 48 The US has directed you to perform a coupling check of the control rod per Procedure 302.2, Control Rod Drive Manual Control System.

Which one of the following is correct if the control rod is correctly coupled?

Hold ROD CONTROL switch in ROD OUT NOTCH:

a. And place the NOTCH OVERRIDE switch to NOTCH OVERRIDE; position indication will indicate "48" with a red backlight.

b. And place the NOTCH OVERRIDE switch to NOTCH OVERRIDE.

Position indication will go dark.

c. And position indication will indicate "48" with a red backlight.

d. And position indication will go dark then settle at position "48," verify the settle light is out.

93

Oyster Creek 2002 Question Data Sheet Answer Key

93 Choice Basis or Justification Correct: A Per Station Procedure 302.2, Control Rod Drive Manual Control System Distractors: B Plausible, this would happen if uncoupled C Plausible, must go to NOTCH OVERRIDE to perform coupling check D Plausible, same as "C"above, dark indication indicates uncoupled Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 2.5 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Station Procedure 302.2, Control Rod Drive Manual Control System [2621.828.361 Learning Objective: 00076, 00726 Terminal Objective: 2170101006 Knowledge/Ability: G2.2.2 Importance: 4.0/3.5 Equipment Control. Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

Prepared by: Larry Briggs Question Data Sheet JI

'K

Oyster Creek 2002 NRC R Initial Licensing Exam IiilLcnigEa OytrCek20

94. Which one of the following is an appropriate use of a Special Condition Tag (SCT), per Procedure 108P, Clearance and Tagging?

a. The SCT is being applied with an information tag to change and correct the stated position on the information tag.

b. A second SCT is being applied to the same component and is being tagged in the same position.

c. The SCT is being applied to the same component as a red tag and the component is tagged in the same position.

d. An SCT is being applied to a breaker to maintain it in the energized condition.

I 94

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

94 Choice Basis or Justification Correct: D Per Station Procedure 108P, Clearance and Tagging, Section 5.2 and 5.3 Distractors: A Plausible, can be applied with information tag ifpositions do not conflict.

B Plausible, two SCTs cannot be applied to one component.

C Plausible, SCT cannot be applied to a red tagged component.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3 2 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Other Exam Bank Mod. Lim EX. Q #18 OC Exam Bank NRC Exam Bank Reference(s): Station Procedure 108P, Clearance and Tagging, Section 5.2 and 5.3 Learning Objective: Administrative procedures Terminal Objective:

Knowledge/Ability: G2.2.13 Importance: 3.6/3.8 Equipment Control. Knowledge of tagging and clearance procedures.

Revised 2 distractors including correct answer.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Oyster Creek 2002 NRC Initial Licensing Exam Exam

95. Given the following:

A male, fully qualified radiation worker at Oyster Creek has just returned from 2 weeks of outage support at Peach Bottom.

Total Effective Dose Equivalent (TEDE) received at Peach Bottom was 200 mrem

After a fall at home the worker received an ankle X-Ray estimated at 20 mrem exposure to the ankle

Theworkers TEDE for Oyster Creek for 2002 is 125 mrem Which one of the following is correct lAW Oyster Creek Procedure, ADM 4000.01, Administrative Dose Limits?

For the year 2002, the individual would need the permission of the:

a. Radiation Protection Manager to exceed 3655 mRem.

b. Radiation Protection Manager and Oyster Creek Vice President to exceed 4655 mRem.

c. Radiation Protection Manager to exceed 4675 mRem.

d. Radiation Protection Manager and the Oyster Creek Vice President to exceed 3675 mRem.

95

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

95 Choice Basis or Justification Correct: D Oyster Creek Procedure, ADM-4000.01, Administrative Dose Limits. Limit is 4000 mrem. 20 mrem is not counted as occupational exposure..

Distractors: A Plausible, if 20 mrem to ankle is considered TEDE B Plausible, if applicant uses NRC limits with 20 mrem to ankle considered TEDE C Plausible, if NRC limits are used. Still need VP approval also.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 5 X - 43.4 Source Documentation Source: New Exam Item X (MOD 2001 PB NRC*) Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Oyster Creek Procedure, ADM-4000.01, Administrative Dose Limit; Fundamentals, Radiation Protection!

Learning Objective:

Terminal Objective:

Knowledge/Ability: G2.3.4 Importance: 2.5/3.1 Radiation Control. Knowledge of radiation exposure limits and/or contamination control, including permissible levels in excess of those authorized.

Modified Stem and all distractors to include approval for excess of normal authorized level. Also made limits site specific.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

96. Given the following:

Oyster Creek is at 5% power -

A Drywell entry is being made to repair a leak identified during the 1000 psi inspection following the outage.

The leak is on a pipe flange and the gasket needs to be isolated and replaced.

As the Unit Supervisor (US) use the As Low As Reasonably Achievable (ALARA) guidelines to determine which one of the following methods should be used to complete the repair. Consider only the radiation exposure aspects of the repair.

a. Two individuals:

Install temporary shielding for 30 minutes in a 200 mr/hr area.

Take 60 minutes to complete the repair in a 20 mr/hr area.

Remove the shielding in 20 minutes in a 200 mr/hr area.

b. Two individuals:

Take 60 minutes to complete the repair with no temporary shielding in a 200 mr/hr area.

c. Two individuals:

Install temporary shielding for 20 minutes in a 200 mr/hr area.

Take 60 minutes to complete the repair in a 40 mr/hr area.

Remove the shielding in 15 minutes in a 200 mr/hr area

d. One individual:

Install temporary shielding for 60 minutes in a 200 mr/hr area.

Two individuals:

Take 60 minutes to complete the repair in a 40 mr/hr area.

One individual:

Removes the shielding in 30 minutes in a 200 mr/hr area.

96 ,96

Oyster Creek 2002 Question Data Sheet NRC Initial Licensina Exam Answer Key

96 Choice Basis or Justification Correct: C 314 mrem exposure Distractors: A Plausible,374 mrem exposure B Plausible, 400 mrem exposure D Plausible,380 mrem exposure Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2.5 5 X-43.4 Source Documentation Source: New Exam Item X (2001 PB NRC EX*) Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Station Procedure ADM-4110.04, Radiological Work Process, Exhibit 8; ; Fundamentals, Radiation Protection Learning Objective:

Terminal Objective:

Knowledge/Ability: G2.3.2 Importance: 2.5/2.9 Radiation Control. Knowledge of ALARA program.

Stem only slightly modified Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

97. Given the following:

"* The plant is at 75% power and being shutdown in preparation for a refueling outage

"* A drywell purge with air is in progress

"* Stack activity has increased to 500 CPS.

The control room operator reports that Torus pressure has increased during the purging process and is approaching Drywell pressure.

In accordance with Station Procedure 312.9, Primary Containment Control:

a. Close the Torus and Drywell vent valves to stop the radioactive release.

b. Close the Drywell vent valves to stop the radioactive release.

c. Close Drywell vent Valves then open the Torus vent valves to reduce Torus pressure.

d. Open the Torus vent valves then close the Drywell vent valves to reduce the Torus pressure.

97

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

97 Choice Basis or Justification Correct: C Per Station Procedure 312.9, Primary Containment Control, Section 7.

Distractors: A Plausible, not required till counts have reached 1000 CPS B Plausible, not required till counts have reached 1000 CPS D Plausible, This would violate primary containment when the Torus valves were opened.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO F 3.5 3 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Station Procedure 312.9, Primary Containment Control, Section 7 [2621.828.32]

Learning Objective: 00418, 00424, 00446 Terminal Objective: 2230101006 Knowledge/Ability: G2.3.9 Importance: 2.5/3.4 Radiation Control. Knowledge of the process for performing a containment purge.

Prepared by: Larry Briggs Queston ShetDta .

.1 Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

98. Given the following:

"* The plant experienced a reactor scram due-to a loss of condenser vacuum

"* Isolation Condensers did not automatically initiate

"* RPV level reached 120 inches TAF and is recovering

"* Reactor Pressures is 1055 psig

"* DC control power for Recirculation Pump breakers has been lost The US has directed the reactor operator to use the "A" Isolation Condenser to help reduce pressure.

lAW Support Procedure 11, Alternate Pressure Control Systems, Isolation Condensers, which one of the following is correct?

Dispatch an operator:

a. To the 1A 4160 VAC bus to manually trip the "E" recirculation pump breaker to clear the high flow trip.

b. To the Recirculation Pump MG set room to manually trip the "E" recirculation pump breaker to prevent the high flow trip.

c. To the 1A 4160 VAC bus to manually trip the "A" recirculation pump breaker to prevent the high flow trip.

d. To the Recirculation Pump MG set room to manually trip the "A" recirculation pump breaker to clear high flow trip.

98

Oyster Creek 2002 Question Data Sheet NRC Initial Licensingq Exam Answer Key

98 Choice Basis or Justification Correct: C Per Support Procedure 11, Alternate Pressure Control Systems, Isolation Condensers.

Distractors: A Plausible, however the "E"recirculation pump bffects the "B"isolation condenser B Plausible, "E"recirc pump affects the "B"ICand the field breaker in the MG set room is not used to trip the Recirc Pump D Plausible, "A"recirc pump affects the "A'IC however the field breaker in the MG eset room is not used to trip the Recirc Pump Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 3 Source Documentation Source" New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): Support Procedure 11, Alternate Pressure Control Systems, Isolation Condensers

[2621.845.041 Learning Objective: 03096, 09521 Terminal Objective: 2000501412 Knowledge/Ability: G2.4.35 Importance: 3.3/3.5 Emergency Plan. Knowledge of local auxiliary operator tasks during emergency operations including system geography and system implications.

Prepared by: Larry Briggs Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam

99. Given the following:

"* Reactor has scrammed due to a LOCA -

"* Two (2) control rods are at notch 48

"* RPV level is unknown

"* Torus level is 180 inches

"* Reactor Engineering has not been notified yet Which one of the following accident mitigation strategies is correct?

a. Emergency Depressurization - With ATWS, EMG-3200.04B, to reduce pressure, with a minimum of injection, till placed on shutdown cooling.

b. RPV Flooding -With ATWS, EMG-3200.08B, to reduce pressure and slowly inject water until the Main Steam lines are flooded to ensure adequate core cooling.

c. RPV Flooding - No ATWS, EMG-3200.08A, to reduce pressure and rapidly inject water until the Main Steam lines are flooded to ensure adequate core cooling.

d. RPV Control - No ATWS, EMG-3200.01 B, to control water level and pressure control to ensure adequate core cooling and cool down the reactor to cold shutdown conditions.

99 99

Oyster Creek 2002 Question Data Sheet NRC Initial NRC Initial Licensing Exam Licensing Exam Oyster Creek 2002 Question Data Sheet Answer Key

99 Choice Basis or Justification Correct: B Per entry conditions, RPV level is unknown.

Distractors: A Plausible, similar, but level would be know in this case.

C Plausible, applicant must note that Reactor Engineering has not been notified to determine if core will remain shutdown. It most likely would but has not been determined.

D Plausible, but level is unknown and 2 rods are not inserted.

Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 2.5 4 43.5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): RPV Flooding [2621.845.181 Learning Objective: 08025 Terminal Objective: 2000501410, 2005010418 Knowledge/Ability: G2.4.7 Importance: 3.1/3.8 Emergency Procedures/Plan. Knowledge of event based EOP mitigation strategies.

Prepared by: Larry Briggs I,/

Question Data Sheet

Oyster Creek 2002 NRC Initial Licensing Exam 100. Given the following:

"* The plant has experienced a 3 gpm reactor-coolant leak

"* The EOPs are being implemented

"* RPV level is 75 inches TAF and has been steady for the last 10 minutes

"* RPV pressure is at 700 psig

"* Drywell pressure is 5 psig and steady lAW with EPIPs the Shift Manager must:

a. Declare an Unusual Event, and activate the Initial Response Emergency Organization and the TSC.

b. Declare an Unusual Event and notify the proper NJ authorities within 15 minutes and the NRC within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

c. Declare an Alert, and activate the Initial Response Emergency Organization and the TSC.

d. Declare an Alert and notified the proper NJ authorities within 15 minutes and the NRC within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

100

Oyster Creek 2002 Question Data Sheet NRC Initial Licensing Exam Answer Key

100 Choice Basis or Justification Correct: B Per EPIP-OC-.01, Classification of Emergency Events, EPIP-OC-.02, Direction of Emergency Response/Emergency Control Center (ECC), and EPIP-OC-.03, Emergency Notification. Will need EPIP-OC-.01, attachment 1; Emergency Classification Table to answer.

Distractors: A Plausible, IREO and TSC is not required to be activated on UE C Plausible, but not an Alert D Plausible, but not an Alert Metrics Level of Knowledge Difficulty Time Allowance (minutes) SRO H 3 5 Source Documentation Source: New Exam Item X Old NRC Exam Modified Bank Item Other Exam Bank OC Exam Bank NRC Exam Bank Reference(s): EPIP-OC-.01, Classification of Emergency Events, EPIP-OC-.02, Direction of Emergency Response/Emergency Control Center (ECC), and EPIP-OC-.03, Emergency Notification.

Learning Objective: 2685.780.07, A,AA Terminal Objective: 2000502401 Knowledge/Ability' G2.4.29 Importance: 2.6/4.0 Emergency Procedures/Plan. Knowledge of the Emergency Plan.

Prepared by: Larry Briggs Question Data Sheet

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ML021610274

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