ML083330126

PV-2008-11-Final-Written Exam

ML083330126
Person / Time
Site:	Palo Verde
Issue date:	11/14/2008
From:	Mckernon T Operations Branch IV
To:
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Download: ML083330126 (172)

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ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 1 of 120 11/18/08 1

This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

42008AK2.03 Importance Rating:

2.50 Unit 1 is stable at 100% power with the following conditions:

Pzr level is 51.5 %

Pressurizer is in Boron Equalization Pressurizer pressure is 2235 psia PZR pressure controller, RCN-PIC-100, output is 40% and stable PZR level controller, RCN-LIC-110, output is 40% and stable A subsequent event occurs with these conditions:

Letdown controller output 45% and INCREASING Pressurizer pressure controller output 25% and LOWERING Which one of the following events occured?

A.

Secondary steam leak B.

Pressurizer steam space leak C.

A full strength CEA has dropped D.

A purification IX with new resin has been placed in service Answer:

B Associated KA:

L10452 Given PZR Safety Valve tailpipe temperatures and the steam tables analyze the data to determine the status of the PZR safety valve Reference Id:

Q10492 Difficulty:

4.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

GFES, PPCS lesson plan K&A: Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following: Controllers and Positioners Justification:

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 2 of 120 11/18/08 A is Wrong - steam leak equals cooldown level output would lower pressure output would lower B is Correct - vapor space leak causes Pzr level increase which causes letdown controller output to increase. Pzr pressure will drop causing pressure controller output to lower to prop heaters full on at 0 output C is Wrong - dropped CEA means colder water = level drop= letdown controller lowering and pressure controller lowering D is Wrong - this is a dilution causing an RCS heatup so letdown controller will increase and if anything a pressure increase which would cause controller output to increase

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 3 of 120 11/18/08 2

This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

41009ek2.03 Importance Rating:

3.00 Given the following plant conditions:

Unit 1 was manually tripped due to decreasing Pzr level with letdown isolated SG pressures are being maintained 1170 psia by the Steam Bypass Control System.

Containment pressure and humidity are slowly increasing RCS pressure is currently 1860 psia and stable.

Subcooled margin is 48°F and stable.

PZR level is 30% and stable.

SIAS/CIAS were manually initiated.

Which one of the following describes the primary heat removal method that will be used during the cooldown? (assume the leak size remains constant and CSAS does not actuate)

A.

Reflux boiling B.

SGs with forced circulation C.

SGs with subcooled natural circulation D.

Once thru cooling using HPSI injection Answer:

B Associated KA:

L10450 Given a Loss of Coolant condition determine the major mitigating strategies contained in 40EP-9EO03 Reference Id:

Q22427 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

LOCA tech guideline, 40DP-9AP08 K&A: Knowledge of the interrelations between the small break LOCA and the following:

S/Gs Justification:

A is Wrong - this is a SB LOCA subcooling will be maintained B is Correct - CD will be performed using SBCS and SGs, SBLOCA

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 4 of 120 11/18/08 C is Wrong - RCPs will remain in operation for the CD, no problem with subcooling or RCS pressure D is Wrong - There will be some injection during CD but crew will throttle HPSI as appropriate

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 5 of 120 11/18/08 3

This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

41011EK1.01 Importance Rating:

4.20 Unit 1 has tripped from 100% power with the following conditions:

RCPs were manually tripped 25 minutes ago due to a CSAS actuation RCS T-cold is 325 ºF and lowering RCS T-hot is 400 ºF and lowering Max quadrant CET temperature is 450 ºF RCS pressure is 345 psia and lowering Which one of the following is correct?

Natural Circulation flow...

A.

has been established. Ensure SG levels are 45 - 60% NR B.

has been established. Place the RCS on Shutdown Cooling C.

has not been established. Ensure SG levels are 45 - 60% NR D.

has not been established. Place the RCS on Shutdown Cooling Answer:

C Associated KA:

L62490 Given a LOCA Event, Tailboard the guidance included in the LOCA Emergency Procedure Technical Guideline.

Reference Id:

Q10493 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: Steam Tables Technical

Reference:

40EP-9EO03, LOCA / 40DP-9AP08, LOCA Tech Guideline K&A: Knowledge of the operational implications of the following concepts as they apply to the Large Break LOCA: Natural circulation and cooling, including reflux boiling.

Justification:

A & B are Wrong - Natl Circ can not be verified delta T is to great, Delta between Thot and CET is to great and subcooling is not met for Thot but not the required CET temperatures C is correct Natl circ can not be verified and ensuring SG levels 45 - 60% NR is directed by LOCA D is Wrong - SDC is not permitted with inadequate subcooling

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 6 of 120 11/18/08 4

This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

2.4.16 Importance Rating:

3.50 Given the following conditions:

Unit 1 is at rated power RCP 1A has indications of Seal Failure CRS has implemented 40AO-9ZZ04, RCP Emergencies The CRS determines that RCP 1A has exceeded Trip Setpoints The CRS holds a brief, discussing tripping the 1A RCP Which one of the following is the correct process to be followed?

A.

Trip the 1A RCP, concurrently perform the SPTAs and RCP Emergencies AOP B.

Trip the 1A RCP, address reactivity safety function, concurrently perform the remaining SPTAs and RCP Emergencies AOP C.

Trip the Reactor, trip 1A RCP, address reactivity safety function, concurrently perform the remaining SPTAs and RCP Emergencies AOP D.

Trip the Reactor, address reactivity safety function, trip the 1A RCP, concurrently perform the remaining SPTAs and RCP Emergencies AOP Answer:

D Associated KA:

L10335 Given that an ORP, FRP or LMFR is in use describe what actions are required if a step in the left (instruction) or right (contingency) column can not be performed Reference Id:

Q10398 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Memory Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

EOP Users Guide, 40DP-9AP16; AOP Users Guide, 40DP-9AP18; 40AO-9ZZ04, RCP Emergencies.

K&A: Emergency Procedures / Plan Knowledge of EOP implementation hierarchy and coordination with other support procedures.

Justification:

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 7 of 120 11/18/08 D is the correct answer. 40AO-9ZZ04, RCP Emergencies, step 7 requires the reactor to be tripped prior to securing the RCP. This makes distracters A and B incorrect.

AOP Users Guide, 40DP-9AP18, section 17 states that the Reactivity Control Safety Function SHALL be addressed immediately after a reactor trip. This makes distracter C incorrect.

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 8 of 120 11/18/08 5

This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

42025ak3.03 Importance Rating:

3.90 Given the following conditions:

Unit 1 is in Mode 5 RCS level is 103 feet 6 inches RCS temperature is 140ºF LPSI pump B is providing Shutdown Cooling flow at 4500 gpm NOW RCS level has slowly dropped to 102 feet 8 inches LPSI pump B amps are oscillating Shutdown Cooling flow is oscillating Which one of the following actions is directed by the Lower Mode Functional Recovery Procedure?

A.

Run LPSI and CS pumps in parallel to lower RCS temperature B.

Reduce LPSI pump B flow to minimize vortexing at the pump suction C.

Shift SDC to CS pump B due to its lower suction pressure requirements D.

Place LPSI pump A in service and vent the B SDC train to remove entrapped gases Answer:

B Associated KA:

56506 Given the LMFRP is being performed and HR is in progress outline the major steps used to control Core and RCS heat removal in HR (LMFRP)

Reference Id:

Q22463 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (5) 55.41 (5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9AP19, LMFRP tech guideline K&A: Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System: Immediate actions contained in EOP for Loss of RHRS

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 9 of 120 11/18/08 Justification:

A is Wrong - This may help lower temperature eventually but would further lower LPSI pump suction pressure B is Correct - Reducing flow would increase LPSI pump suction pressure and reduce vortexing and is directed by HR-2 C is Wrong - CS pump B has pressure and temperature requirements when placed on SDC. Examinee may confuse this with lower suction pressure requirements D is Wrong - This may be done eventually but with lowering level it is not directed to swap trains until the reason for the lowering level is determined

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 10 of 120 11/18/08 6

This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

42027AA2.12 Importance Rating:

3.70 Given the following conditions:

Pressurizer pressure is 2250 psia Pressurizer level is 52%

Pressurizer low level heater cutout switch (RCN-HS-100-3) is selected to Channel X Pressurizer level control channel selector (RCN-HS-110) is selected to Channel X Which one of the following conditions is true regarding the Pressurizer Pressure Control System?

A.

Backup heaters will energize if RCS pressure drops to 2225 psia B.

All heaters will be energized if PZR level transmitter RCN-LT-110X fails high C.

All heaters will de-energize if PZR level transmitter RCN-LT-110Y fails low D.

Proportional heaters will trip and must be reset if pressurizer pressure reaches 2275 psia Answer:

B Associated KA:

L75234 Describe the function of Pressurizer Level Instruments (RCN-LT-110X and RCN-LT-110Y) inputs to the Pressurizer Pressure Control System.

Reference Id:

Q10494 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

PPCS Lesson Plan K&A: Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: PZR level Justification:

A is Wrong - backup heaters energize 2200 de-energize at 2225 psia B is Correct - proportional heaters are always energized and backup heaters energize on a

+3% level deviation C is Wrong - channel Y has no effect if not in Y or both D is Wrong - Prop heaters have 0 output but do not trip or require reset at 2275 psia

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 11 of 120 11/18/08 7

This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

2.2.3 Importance Rating:

3.80 If all PVNGS units are in a normal electric plant alignment then the minimum allowed switchyard voltage for Unit 1 is _______ than Unit 2. In addition the Water Reclamation Facility supply breakers will trip open on a simultaneous low switchyard voltage and _______ signal.

A.

lower, LOP B.

lower, SIAS C.

higher, LOP D.

higher, SIAS Answer:

D Associated KA:

30264 Unit differences Reference Id:

Q10495 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

41AL-1RK1B, window 6B K&A: Equipment Control (multi-unit) Knowledge of the design, procedural, and operational differences between units.

Justification:

A & B are Wrong - Unit 1 has a higher minimum voltage requirement but examinee may think that U1 requirement is lower because it will shed loads on a SIAS C is Wrong - SIAS and voltage permissive is required D is Correct - see above

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 12 of 120 11/18/08 8

This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

41038ek3.08 Importance Rating:

4.10 Given the following conditions:

Unit 1 was manually tripped due to a SG tube rupture RCS pressure 1400 psia RCS Tcold is 531 ºF RCS Thot is 536 ºF SIAS setpoints were lowered during the controlled RCS de-pressurization MSIS setpoints were lowered during the controlled RCS cooldown The SGTR procedure, 40EP-9EO04, directs...

A.

tripping all RCPs due to the loss of subcooling B.

that all RCPs remain running since SIAS has not actuated C.

tripping both RCPs in one loop to reduce the potential for RCS inventory loss D.

tripping one RCP in each loop to maintain maximum flexibility for plant control Answer:

D Associated KA:

L11239 Given the SGTR EOP is being performed and a cooldown to less than 550°F is required describe how and at what rate the cooldown will be performed Reference Id:

Q10496 Difficulty:

4.00 Time to complete:

3 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: Steam Tables Technical

Reference:

40EP-9EO04, LOCA K&A: Knowledge of the reasons for the following responses as the apply to the SGTR:

Criteria for securing RCP Justification:

A is wrong - Subcooling is greater than 24 degrees, examinee may see lower pressure and think subcooling is lost B is Wrong - may confuse SIAS setpoint and SIAS actuation for tripping 2 RCPs believing it is permissible to leave RCPs running

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 13 of 120 11/18/08 C is Wrong - T2L2 is for opposite loops but inventory loss is one of the 2 given reasons in the tech guide D is Correct - T2L2 is correct for opposite loops and max flexibility

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 14 of 120 11/18/08 9

This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

42040AK2.02 Importance Rating:

2.60 Given the following plant conditions:

The reactor has tripped.

PZR level is 25% and lowering.

RCS pressure is 1700 psia and dropping.

Containment pressure and temperature is rising.

RCS subcooling is 75°F and increasing.

SG 1 level is 45% WR and lowering Loop 1 Tcold is 520°F and lowering SG 2 level is 65% WR and lowering Loop 2 Tcold is 555°F and lowering Which one of the following is the most likely response of the SG 1 steam flow transmitters SGN-FT-1011 (Line 1) and SGN-FT-1012 (Line 2)?

A.

SGN-FT-1011 flow > SGN-FT-1012 flow. SGN-FT-1012 decreases to 0 (zero) flow when MSIS actuates.

B.

SGN-FT-1011 flow equals SGN-FT-1012 flow. SGN-FT-1012 decreases to 0 (zero) flow when MSIS actuates.

C.

SGN-FT-1011 flow > SGN-FT-1012 flow. SGN-FT-1011 and SGN-FT-1012 each decrease to 0 (zero) flow when MSIS actuates.

D.

SGN-FT-1011 flow equals SGN-FT-1012 flow. SGN-FT-1011 and SGN-FT-1012 each decrease to 0 (zero) flow when MSIS actuates.

Answer:

A Associated KA:

L11203 Given plant conditions analyze SG parameters to determine the presence and relative severity of an ESD Reference Id:

Q10497 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

mechanical prints, 01-SGP-0002

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 15 of 120 11/18/08 K&A: Knowledge of the interrelations between the Steam Line Rupture and the following:

Sensors and detectors Justification: SG 1 steam line break in Containment, Examinee must deduce break location and on steam line 1 A is Correct - 1 > 2 is correct and 1011 will go to 0 as dryout approaches and 1012 goes to 0 on MSIS. Flow detectors are on SG nozzle outlets B is Wrong - 1 = 2 is wrong and MSIS will not cause flow to go to zero C is Wrong - 1 > 2 is correct but since the leak is in containment flow will degrade not go to 0 on MSIS D is Wrong - 1 = 2 is wrong but examinee may assume redundant indications as they are used in COLSS. Flow will trend to 0 as dryout conditions are reached

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 16 of 120 11/18/08 10 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

41055EA1.01 Importance Rating:

3.70 Given the following plant conditions:

Unit 1 has been in a blackout condition for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

QSPDS indicates 32 degrees superheat and has been stable for the last 15 minutes.

CET temperatures and RCS pressure have also been stable for the last 15 minutes.

What is the condition of RCS and core heat removal?

A.

Two phase natural circulation is maintaining heat removal.

B.

Single phase natural circulation is maintaining heat removal.

C.

All natural circulation has been lost, core uncovery has occurred.

D.

All natural circulation has been lost, but the core still remains covered.

Answer:

A Associated KA:

L56411 Given conditions of a Blackout state the action necessary to maintain subcooling margin L75186 Maintain RCS temp L61432 State the action necessary to maintain subcooling margin during a blackout.

100866 Active Question Bank 2004 Reference Id:

Q8927 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Comprehension / Anal Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40EP-9EO08, BLACKOUT / 40DP-9AP13. BO Tech Guideline K&A: Ability to operate and monitor the following as they apply to a Station Blackout: In-core thermocouple temperatures Justification:

A is Correct - single phase nal circ has been lost. Provided that REP CET is maintained less than 50 degrees superheated than the core is covered and 2 phase natl circ flow is effective 11

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 17 of 120 11/18/08 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

42056AK1.04 Importance Rating:

3.10 Given the following conditions:

Main Spray valves 100E & 100F failed open SIAS/CIAS/MSIS automatically initiated Offsite power was lost when the reactor tripped Offsite power has been restored PZR level is 7% and slowly increasing RCS Tcold temperature is 510ºF RCS Thot temperature is 520ºF REP CET temerature is 550ºF RCS pressure is 1044 psia The RCS is currently....

A.

24ºF subcooled. HPSI flow may be throttled at the current RCS conditions.

B.

at saturation conditions. HPSI flow may be throttled if RCS pressure is raised to 1350 psia.

C.

24ºF subcooled. RCP restart is permitted per Standard Appendix 1 at the current RCS conditions.

D.

at saturation conditions. RCP restart is permitted per Standard Appendix 1 if RCS pressure is raised to 1350 psia.

Answer:

D Associated KA:

30267 RCP restart Reference Id:

Q10498 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: Steam Tables /

Standard App. 2 (RCP curves)

Technical

Reference:

Standard Appendice 2 (RCP curves only), 40EP-9EO07, LOOP K&A: Knowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power: Definition of saturation conditions, implication for the systems Justification:

11 Question Deleted

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 18 of 120 11/18/08 A & C are Wrong - RCS is 24 degrees subcooled by Thot but must use CET temp when in Natl Circ B is Wrong - RCS is at saturation but HPSI can not be throttled with < 10% PZR level D is Correct - RCS is at saturation and minimum RCS pressure for 550 degrees is 1320 psia per provided reference

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 19 of 120 11/18/08 12 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

2.2.2 Importance Rating:

4.60 Given the following conditions:

Unit 1 is operating at rated power An instrument air (IA) line breaks in the Auxiliary building IAN-V055 has been closed isolating IA to the Auxiliary and Containment buildings Which one of the following is true regarding Chemical and Volume Control System (CVCS) under these conditions?

A.

The Fuel Pool is the only available borated water source to the RCS B.

CHN-UV-501 fails closed causing CHN-UV-514 to open, borating the RCS C.

Charging flow will be isolated to the RCS due to CHE-HV-239 and CHE-PDV-240 failing closed D.

The RWT can be aligned to the charging pump suction thru CHE-HV-532 and by opening CHA-HV-536 Answer:

D Associated KA:

L56751 Determine the major effects on plant operation as instrument air pressure degrades.

Reference Id:

Q22461 Difficulty:

2.00 Time to complete:

3 10CFR Category:

CFR 55.41 (6) 55.41 (6) Design, components, and functions of reactivity control mechanisms and instrumentation.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ06, Loss of Instrument Air K&A: Equipment Control Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

Justification:

A is Wrong - RWT is still available CH-532 fails open B is Wrong - CH-501 is motor operated and won't react but if CH-501 were to close CH-514 is interlocked to come open C is Wrong - CH-239/240 do fail closed but the spring loaded check valve CH-435 will maintain flow D is Correct - CH-532 fails open and CH-536 is motor operated and available for CR operation

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 20 of 120 11/18/08

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 21 of 120 11/18/08 13 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

42058aa2.03 Importance Rating:

3.50 Given the following conditions:

Unit 1 is operating at rated power Numerous alarms are annunciated on Board 6 An RO reports that all of the Emergency Oil pumps have lost power This was caused by a loss of. In addition.....

A.

NKN-M45, Control power for NAN-S05 must be transferred to its alternate source.

B.

NKN-M45, NAN-S05 has lost control power until this control center can be restored.

C.

NKN-M46, Control power for NAN-S06 must be transferred to its alternate source.

D.

NKN-M46, NAN-S06 has lost control power until this control center can be restored.

Answer:

C Associated KA:

L68175 Describe the major Loads associated with the Non-Class 125 VDC Power System.

Reference Id:

Q22430 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40ao-9zz14, Loss of non class instrument or control power K&A: Ability to determine and interpret the following as they apply to the Loss of DC Power: DC loads lost; impact on ability to operate and monitor plant systems Justification:

A & B are Wrong - NKN-M45 is the other major DC bus C is Correct - control power for NAN-S06 is available from NKN-M45 D is Wrong - same as above

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 22 of 120 11/18/08 14 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

42062AK3.03 Importance Rating:

4.00 Given the following conditions:

Unit 1 has tripped from rated power due to a Loss of Offsite Power event.

All systems have responded as designed The crew has cross connected Essential Cooling Water (EW) system "A" to Nuclear Cooling Water per Standard Appendix 63.

The procedure now directs that EWA-HCV-53, SDCHX A Outlet Isolation, be throttled closed to a minimum EW system flow of 8500 gpm to...

A.

maintain Operability of the EW "A" system.

B.

provide the NCW priority loads with adequate flow.

C.

prevent EW pump damage due to operating in a runout condition.

D.

ensure adequate flow to the Fuel Pool Heat Exchangers if aligned.

Answer:

B Associated KA:

30268 X-tie EW to NC Reference Id:

Q10499 Difficulty:

2.00 Time to complete:

3 10CFR Category:

CFR 55.41 (8) 55.41 (8) Components, capacity, and functions of emergency systems.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

SA-63 and Tech Guide/ 40DP-9AP12, LOOP Tech Guide /

K&A: Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: Guidance actions contained in EOP for Loss of nuclear service water Justification:

A is Wrong - EW is INOP when cross tied B is Correct - this is to ensure adequate flow to NCW priority loads C is Wrong - not for runout but examinee could believe this to be true when taking systems out of normal alignment

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 23 of 120 11/18/08 D is Wrong - One train of EW not sized to provide both NCW and Fuel Pool cooling, this would require aligning the other train

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 24 of 120 11/18/08 15 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

42057aa1.02 Importance Rating:

3.80 Given the following conditions:

Unit 1 is operating at rated power Diesel Generator A is running and loaded for a surveillance test Heater Control Selector handswitch (RCN-HS-100-3) is selected to "BOTH" Level Control Channel Selector handswitch (RCN-HS-110) is selected to "X" Which one of the following describes the response to a loss of Class Instrument Bus PNA-D25?

A.

The Rod Drop Contacts (RDC) for the A, B and C quadrants will be lit on the board 4 core mimic B.

DG A controls, starting circuit and electrical protection control power is lost causing the DG to trip.

C.

AFN-P01 has lost its normal control power, alternate power is available from the A train battery charger.

D.

RCA-LT-110X fails low causing all PZR heater breakers to open and letdown flow goes to minimum Answer:

D Associated KA:

L75123 Describe the response of the Pressurizer Level Control System to a failure of a power supply.

Reference Id:

Q22441 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ13, Loss of Class Instrument or Control Power K&A: Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual control of PZR level Justification:

A is Wrong - Loss of PNC-D27 B is Wrong - Loss of PKA-D21

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 25 of 120 11/18/08 C is Wrong - Loss of PKA-D21 D is Correct -

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 26 of 120 11/18/08 16 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

42077AA1.03 Importance Rating:

3.80 Unit 1 is operating at 100% power when the following occurs:

Alarm window 6B08D, EXCTN SYS TRBL is alarming Reference the provided Generrex control mimic, LED 14 is extinguished and LED 15 (V/Hz) is flashing This indicates that the Generrex system has.....

A.

raised Main Generator output voltage. AC regulator control can be restored by raising the AC regulator setpoint.

B.

limited Main Generator output voltage. AC regulator control can be restored by lowering the AC regulator setpoint.

C.

activated the V/Hz trip timing circuit. Immediately adjust the AC regulator or a V/Hz trip will occur after the variable timer has timed out.

D.

overridden the AC regulator to increase excitation to an acceptable level. AC regulator control can be restored by increasing the AC regulator setpoint.

Answer:

B Associated KA:

L75018 Explain the operation of the Volts/Hertz Regulator and Trip circuits under normal operating conditions.

Reference Id:

Q10500 Difficulty:

4.00 Time to complete:

3 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Memory Question Source:

Modified PV Bank Comment:

modified from Q21330 Proposed reference to be provided to applicant during examination: Generrex mimic Technical

Reference:

40OP-9MB01, Main Generation and Excitation / 40AL-9RK6B (6B08D), ARP / LOIT lesson plan K&A: Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: Voltage Regulator Controls Justification:

A is Wrong - increase and raise are wrong

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 27 of 120 11/18/08 B is Correct - V/HZ is designed to limit generator voltage prior to a V/HZ trip and AC regulation is restored by lowering the AC reg setpoint C is Wrong - This describe the V/Hz trip timing circuit which is not activated per the cue D is Wrong - This is describing the URAL circuit which works to maintain excitation raising the AC regulator is how URAL is restored.

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 28 of 120 11/18/08 17 This Exam Level RO Apears on:

RO EXAM 2008 K/A #

44E02EA2.2 Importance Rating:

3.00 Given the following plant conditions:

Unit 1 has manually tripped from 20% power for a scheduled refueling outage SPTAs were entered at 0000 Reactor Trip ORP entered at 0015 The Boron Dilution Alarm System (BDAS) must be placed in service and channel check completed when Rx power is less than.....

A.

2x10-4% power but no later than 0100 B.

2x10-4% power but no later than 0115 C.

2x10-6% power but no later than 0100 D.

2x10-6% power but no later than 0115 Answer:

C Associated KA:

L10354 Given conditions of a reactor trip describe the time limitation (including its bases) placed on aligning the BDAS L74318 Given the plant has been placed in Mode 3 apply the requirements for Boron Dilution Alarm System (BDAS) 100866 Active Question Bank 2004 Reference Id:

Q9699 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Memory Question Source:

Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Rx trip, 40EP-9EO02 / Rx Trip tech guide 40DP-9AP07 / LCO 3.3.12 K&A: Ability to determine and interpret the following as they apply to the (Reactor Trip Recovery) Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Justification:

A and B are wrong BDAS is not placed in service until 10 -6%, 10 -4 is verification of subcritical conditions following a rx trip and is used in CPCs log 1 & 2 bistables

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 29 of 120 11/18/08 C is Correct 6 and one hour from Rx trip (SPTAs) is the standard D is Wrong - waiting 15 minutes for start of EOP is not conservative

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 30 of 120 11/18/08 18 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 1 K/A #

44E06ek1.2 Importance Rating:

3.20 Given the following plant conditions:

A reactor trip from 100% power occurs due to an inadvertent MSIS "A".

PBA-S03 is de-energized due to a bus lockout.

AFB-P01 is out of service to repair a pump bearing and is disassembled.

AFA-P01 tripped on overspeed.

The CRS has entered the appropriate EOP.

Which ONE of the following Operator actions should be performed first?

A.

Stop all RCPs.

B.

Start AFN locally at the breaker.

C.

Ensure AFAS-1 and AFAS-2 are actuated.

D.

Depressurize one S/G to less than condensate pump discharge pressure.

Answer:

A Associated KA:

100866 Active Question Bank 2004 L76768 Given a loss of all feedwater event perform required actions L90312 As an operating crew mitigate a loss of all feedwater using the condensate pumps L61371 Describe the major mitigating strategies used during a LOAF.

L61386 Describe how the RCPs are operated (including the bases for this action) during a LOAF.

L10494 Given a Loss of all Feed determine the major mitigating strategies contained in 40EP-9EO06 Reference Id:

Q0878 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Comprehension / Anal Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40EP-99EO06, LOAF K&A: Knowledge of the operational implications of the following concepts as they apply to the (Loss of Feedwater) Normal, abnormal and emergency operating procedures associated with (Loss of Feedwater). facility's license and amendments.

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 31 of 120 11/18/08 Justification:

A is Correct - step 4 of LOAF B is Wrong - PBA-S03 is dead C is Wrong - no indication that AFAS is currently required and no AF pumps are available D is Wrong - Condensate pumps are performed in the FRP

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 32 of 120 11/18/08 19 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 2 K/A #

42024ak1.02 Importance Rating:

3.60 Given the following conditions:

Reactor was initially at 100% power (225 EFPD)

CRS has directed an Emergency Boration due to a loss of Shutdown Margin 1000 gallons of boron have been sent to the Charging Pump suction at 40 gpm Turbine load has been adjusted to maintain RCS temperature on program From memory, using the STA reactivity worksheet approximate values, which one of the following is the most likely current condition?

A.

Reactor Power is ~ 90%, Tave has risen and Tcold has risen B.

Reactor Power is ~ 80%, Tave has lowered and Tcold has risen C.

Reactor Power is ~ 90%, Tave has risen and Tcold has lowered D.

Reactor Power is ~ 80%, Tave has lowered and Tcold has lowered Answer:

B Associated KA:

L58915 Given as set of plant conditions identify entry and exit of Emergency Boration Reference Id:

Q22435 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.41 (5) 55.41 (5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

Basic Operator knowledge K&A: Knowledge of the operational implications of the following concepts as they apply to Emergency Boration: Relationship between boron addition and reactor power Justification:

STA quick reference numbers or Core Data Book state 50 gal of Boration per 1%

power Tave is 585ºF (100%) to 564ºF (0%)

T cold is 558ºF (100%) to 564ºF (0%)

addition rate of 40 gpm means xenon has had little effect at this time

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 33 of 120 11/18/08 A is Wrong -

B is Correct - Based on the above information C is Wrong -

D is Wrong -

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 34 of 120 11/18/08 20 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 2 K/A #

42032ak3.01 Importance Rating:

3.20 Given the following plant conditions:

A reactor startup is in progress.

The shutdown groups are being withdrawn.

Startup Channel #1 fails downscale.

Which one of the following is required?

A.

No action, since one channel of BDAS is still operable.

B.

No action, since you are presently in a mode that doesn't require BDAS.

C.

The startup can continue as long as RCS boron concentration is determined within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

D.

Immediately terminate the startup, Rx startup procedure requires both trains of SU channels to be Operable Answer:

D Associated KA:

L60641 Describe the actions required if a Startup Channel fails during a Reactor Startup.

Reference Id:

Q8394 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Comprehension / Anal Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Tech Specs, 40OP-9ZZ03/ Rx startup, LOIT lesson plan K&A: Knowledge of the reasons for the following responses as they apply to the Loss of Source Range Nuclear Instrumentation: Startup termination on source-range loss Justification:

A is wrong - prereq does not allow B is wrong - BDAS required in modes 3, 4 and 5 C is wrong - boron must be verified immediately D is CORRECT - prereq 5.9 requires two operable BDAS/SU channels

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 35 of 120 11/18/08 21 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 2 K/A #

42036ak1.01 Importance Rating:

3.50 Given the following conditions:

Unit 1 is in Mode 6 Core off-load is in progress LSRO informs the CRS that a Fuel Assembly has been dropped in the Refueling Pool Reactor Operator reports RU 37 & 38, Power Access Purge monitors, are slowly trending up In addition to CPIAS, 40AO-9ZZ22 will direct the crew to initiate or verify initiated...

A.

CRVIAS only B.

CREFAS only C.

CREFAS and FBEVAS D.

CRVIAS and FBEVAS Answer:

B Associated KA:

L96631 Determine whether or not the Irradiated Fuel Damage AOP should be executed.

Reference Id:

Q22425 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ22 (Fuel Damage)

K&A: Knowledge of the operational implications of the following concepts as they apply to Fuel Handling Incidents: Radiation exposure hazards Justification: the procedure requires both CPIAS and CREFAS for a containment fuel handling accident A is Wrong - may choose this to isolate the CR believing that a gas release is occurring B is Correct - procedurally required for a fuel handling accident of any kind C is Wrong - FBEVAS is only required for a FB incident D is Wrong - FBEVAS is only required for a FB incident

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 36 of 120 11/18/08

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 37 of 120 11/18/08 22 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 2 K/A #

42060aa1.01 Importance Rating:

2.80 Given the following conditions:

Unit 1 is operating at rated power RU-8, Auxiliary Building Ventilation Exhaust Filter Inlet, is in alert RU-9, Auxiliary Building Lower Level Exhaust, is in alert RU-143, Plant Vent, readings are increasing Which one of the following events is most likely occurring?

A.

Charging system leak B.

Steam Generator Tube leak C.

Waste Gas Decay tank leak D.

RCS to Nuclear Cooling Water leak in the Letdown heat exchanger Answer:

A Associated KA:

67127 Explain the operation of the Area Radiation Monitors under normal operating conditions.

Reference Id:

Q22437 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

74RM-9EF41, Rad Monitoring ARP K&A: Ability to operate and / or monitor the following as they apply to the Accidental Gaseous Radwaste: Area radiation monitors Justification:

A is Correct - RCS leak to Aux Bldg atmos would show up on ARM and plant vent B is Wrong - SGTL would be RU-4/5, RU-139/140 C is Wrong - WGDT is located in the RW building RU-12/14/15 and 143 would alarm D is Wrong - would show up in RU-6 NCW

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 38 of 120 11/18/08

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 39 of 120 11/18/08 23 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 2 K/A #

42001ak2.01 Importance Rating:

2.90 Given the following conditions:

Reactor power is at 80%

Group 5 CEAs at 120 inches withdrawn All others CEAs at UEL Selected CEA is # 14 Selected CEA Group is # 5 A malfunction occurs causing CEA 15 to move 12 steps out before standby is selected and motion stops Based on this event the pulse counter selected Group position reads...

A.

120 inches B.

122.25 inches C.

124.5 inches D.

129 inches Answer:

B Associated KA:

L58554 Describe the required actions addressing a continuous rod motion accident.

Reference Id:

Q22442 Difficulty:

2.00 Time to complete:

4 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

LOIT lesson plan K&A: Knowledge of the interrelations between the Continuous Rod Withdrawal and the following: Rod bank step counters Justification: 12 steps times 3/4 inch equals 129 inches withdrawn A is Wrong - examinee may believe that that the pulse counter uses lowest CEA position (CPCs)

B is Correct - group position is the average position C is Wrong - examinee may believe that the pulse counter uses average of high/low

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 40 of 120 11/18/08 D is Wrong - examinee may believe that pulse counter uses highest cea position (CPCs)

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 41 of 120 11/18/08 24 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 2 K/A #

44016ak3.3 Importance Rating:

3.30 Unit 1 is operating at rated power when the following conditions are observed:

Pressurizer level is slowly lowering RCS temperature is stable The in-service letdown control valve CHN-110P is slowly closing The CRS implements the appropriate AOP All available charging pumps are running Pressurizer level continues to lower The AOP now directs...

A.

isolating letdown to quantify leakage for E-plan classification B.

an immediate reactor trip to minimize dose rates at the site boundary C.

an immediate reactor trip due to leakage is excess of Tech Spec limits D.

isolating letdown to determine if leakage exceeds CVCS makeup capacity Answer:

D Associated KA:

L10169 Given indications of RCS or a Steam Generator Tube Leak, describe the basic procedure methodology, including Reactor Trip is thresholds, Reference Id:

Q22453 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ02, Excessive RCS Leakrate K&A: Knowledge of the reasons for the following responses as they apply to the (Excess RCS Leakage) Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.

Justification:

A is Wrong - E-plan numbers are determined by performing appendix A/B B is Wrong - next step is to isolate letdown then trip if Pzr level continues to lower C is Wrong - next step is to isolate letdown then trip if Pzr level continues to lower

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 42 of 120 11/18/08 D is Correct - isolate letdown and determine if CVCS makeup capability is exceeded if so then trip reactor

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 43 of 120 11/18/08 25 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 2 K/A #

42069ak2.03 Importance Rating:

2.80 Unit 1 is in Mode 1 with the following Containment conditions:

Pressure is a negative (-) 0.1 psig Average air temperature is 105ºF Both doors in the 140 ft Air Lock are Inoperable but closed 2 Hydrogen recombiners are Operable but located in Unit 2 1 Hydrogen Purge Cleanup system is functional but Inoperable The CRS must implement the actions of....

A.

LCO 3.6.2, Containment Air locks.

B.

LCO 3.6.4, Containment Pressure.

C.

LCO 3.6.5, Containment Temperature.

D.

TLCO 3.6.100, Hydrogen Purge Cleanup system.

Answer:

A Associated KA:

L89788 Given a set of plant conditions apply the one hour or less actions statements of T.S. 3.6 Reference Id:

Q22426 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

Tech Specs K&A: Knowledge of the interrelations between the Loss of Containment Integrity and the following: Personnel access hatch and emergency access hatch Justification:

A is Correct - 2 doors inop in one airlock doors open or closed requires immediate verification of cntmt leakage per condition C B is Wrong - pressure limit is -.3 to +2.5 psig C is Wrong - limit is <117 D is Wrong - only applies with less than two recombiners operable

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 44 of 120 11/18/08 26 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 2 K/A #

2.4.47 Importance Rating:

4.20 Given the following conditions:

Unit 1 is operating at rated power Effluent Technician reports increasing trends on Primary Coolant monitors RU-150/151 This would be indicative of...

A.

Fuel Cladding leakage into the RCS B.

RCS leakage into the Steam Generators C.

RCS Boundary leakage into containment D.

RCS leakage into the Letdown Heat Exchanger Answer:

A Associated KA:

66723 Given a Radiation Monitor number and name describe the purposes and sample points of the Radiation Monitors at PVNGS Reference Id:

Q10460 Difficulty:

2.00 Time to complete:

3 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Memory Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

74RM-9EF41, Rad Monitoring System Alarm Response K&A: Emergency Procedures / Plan Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Justification: all of the listed parameters are monitored by the RMS system and are related to an RCS boundary leak of some sort A is Correct - RU-6 would be alarming B is Wrong - RU-1 and RU-16 would be alarming C is Correct - RU-150/151 are in place to monitor for fuel cladding leakage D is Wrong - RU-4,5, 141,142 and so on would be alarming

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 45 of 120 11/18/08 27 This Exam Level RO Apears on:

RO EXAM 2008 Tier 1 Group 2 K/A #

44a11aa2.2 Importance Rating:

3.00 The following conditions are noted in Unit 1 following an Excessive Steam Demand event:

The crew has initiated a 20°F/hr cooldown to shutdown cooling entry conditions RCS pressure is 1200 psia RCS temperature is 360°F Which of the following actions is appropriate?

A.

Heat up and repressurize the RCS.

B.

Heat up and depressurize the RCS.

C.

Maintain temperature constant and repressurize the RCS.

D.

Maintain temperature constant and depressurize the RCS.

Answer:

D Associated KA:

100866 Active Question Bank 2004 L11210 Given that the EOPs are being performed and specific plant conditions are given determine whether or not the plant is over subcooled, and if it is what actions must be taken L61360 Analyze plant conditions to determine whether or not the plant is over subcooled, and if it is what actions must be taken.

L89131 Given that the EOPs are being performed and specific plant conditions are given determine whether or not the plant is over subcooled, and if it is what actions must be taken Reference Id:

Q28565 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

ESD, 40EP-9EO06 / Tech guide and standard appendices / LOIT lesson plan K&A: Ability to determine and interpret the following as they apply to the (RCS Overcooling) Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Justification:

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 46 of 120 11/18/08 A is Wrong - might believe that over subcooling is corrected by a heatup B is Wrong - this would drive the conditions right of the curve but not the expected actions C is Wrong - this would drive conditions below and right of curve but is not procedurally directed or desired D is Correct - directed by the ESD procedure step 21

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 47 of 120 11/18/08 28 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

34003KK5.02 Importance Rating:

2.80 Each RCP motor has a fly wheel which:

A.

Provides RCP speed signal to the Core Protection Calculators B.

Increases RCP coastdown time to maximize decay heat removal.

C.

Prevents an idle pump from turning due to flow from other running RCP's.

D.

Provides shaft balancing to prevent excessive vibration on pump start and stops.

Answer:

B Associated KA:

L67246 Explain the operation of the Reactor Coolant Pumps under normal operating conditions.

100866 Active Question Bank 2004 Reference Id:

Q3571 Difficulty:

1.00 Time to complete:

2 10CFR Category:

CFR 55.41 (3) 55.41 (3) Mechanical components and design features of the reactor primary system.

Cognitive Level:

Memory Question Source:

Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

LOIT lesson plan K&A: Knowledge of the operational implications of the following concepts as they apply to the RCPs: Effects of RCP coastdown on RCS parameters Justification:

A is Wrong - CPC speed sensors are mounted on the RCP shaft B is Correct - provides longer coastdown time and sets up natural circulation flow as part of design C is Wrong - anti-rotation device does this D is Wrong - this is a reasonable distracter balancing is performed on the shaft

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 48 of 120 11/18/08 29 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

34003A4.02 Importance Rating:

2.90 Which one of the following parameters, occuring independently, would require an immediate RCP trip/shutdown?

A.

Running at 550 amps B.

Controlled Bleedoff Flow of 8 gpm C.

Complete loss of Seal Injection flow D.

Nuclear Cooling Water temperature of 130ºF Answer:

A Associated KA:

L67247 Describe the Control Room controls associated with the Reactor Coolant Pumps including indications.

Reference Id:

Q10503 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

10CFR Category:

CFR 55.41 (10)CFR 55.41 (7) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AO-9ZZ04, RCP motor emergencies / standard appendix 16 K&A: Ability to manually operate and/or monitor in the control room: RCP motor parameters Justification:

A is Correct - limit is 520 amps B is Wrong - BO flow limit is.5 to 9.5 gpm C is Wrong - SI loss is 10 minutes D is Wrong - there is no trip requirement associated with NCW

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 49 of 120 11/18/08 30 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

31004a1.12 Importance Rating:

2.80 Given the following conditions:

Unit 1 is in a end of cycle power "coastdown" as the Refueling outage approaches Turbine load is being lowered to maintain Tcold Current power level is 80%

The de-borating ion exchanger is in service Charging Pump Mode Selector is in 1-2-3 Charging pump "A" is operating Charging pump "B" is in PTL Charging pump "E" is in PTL Letdown flow is 36 gpm Pzr level controller, RCN-LIC-110, is in Manual control with 30% output Pressurizer level is being maintained at 40%

Which one of the following actions/events, occurring independently, will cause an increasing (greater) rate of Boron reduction?

A.

CHN-LT-227 fails low B.

Taking Charging pump "B" out of PTL C.

Raising Letdown Setpoint Controller RCN-LIC-110 output to 35%

D.

Returning Letdown Setpoint Controller RCN-LIC-110 to automatic control with auto setpoint Answer:

C Associated KA:

L67635 Explain the operation of the Letdown Ion Exchanger under normal operating conditions.

Reference Id:

Q22432 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (5) 55.41 (5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40AL-9RK3A / pages 33 and 50 of simplified drawings

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 50 of 120 11/18/08 K&A: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: Rate of boron concentration reduction in RCS as a function of letdown flow while deborating demineralizer in service Justification:

A is Wrong - this causes a shift, CH-501 closes and CH-514 opens means boration B is Wrong - Pump will start but will not effect LD flow with controller in manual C is Correct - Raising output means more LD flow = more deborating D is Wrong - auto/auto operation means PLCS tries to raise Pzr level to approx. 48%

= less letdown flow

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 51 of 120 11/18/08 31 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

3.4005K2.03 Importance Rating:

2.70 What are the power supplies to the Shutdown Cooling Isolation valves, SIA-HV-651 (A) and SIC-HV-653 (B)?

A.

(A) 480 VAC Class LC, PG (B) 480 VAC Class LC, PG B.

(A) 480 VAC Class LC, PG (B) 125 VDC Class MCC, PK C.

(A) 480 VAC Class MCC, PH (B) 480 VAC Class MCC, PH D.

(A) 480 VAC Class MCC, PH (B) 125 VDC Class MCC, PK Answer:

D Associated KA:

65136 Identify the power supplies to SI related equipment.

Reference Id:

Q10504 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Electrical prints, 01-E-SIB-013 & 014 K&A: Knowledge of bus power supplies to the following: RCS pressure boundary motor-operated valves Justification:

A is wrong -

B is wrong -

C is wrong -

D is CORRECT - SI-651 is supplied by a class MCC (PH) and SI-654 is supplied by class DC (PK) thru an inverter N43

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 52 of 120 11/18/08 32 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

34005A4.03 Importance Rating:

2.80 Given the following conditions:

RCS level is at midloop LPSI pump "B" is providing shutdown cooling (SDC) flow at 4000 gpm as read on SIB-FI-307 Refueling Water Level Indicating System (RWLIS) is in service RWLIS flow compensator is selected to "B" Area 3 reports that SIB-HV-690 is 10% open Which one of the following describes the effects on the SDC system indications?

A.

RCS level is lower than indicated and RCS flow is less than indicated flow B.

RCS level is higher than indicated and RCS flow is less than indicated flow C.

RCS level is lower than indicated and RCS flow is greater than indicated flow D.

RCS level is higher than indicated and RCS flow is greater than indicated flow Answer:

A Associated KA:

65120 Describe the Control Room indications associated with the SDC system.

Reference Id:

Q22479 Difficulty:

4.00 Time to complete:

5 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40OP-9SI01, SDC Initiation / 40OP-9ZZ16, RCS Drain Operations K&A: Ability to manually operate and/or monitor in the control room: RHR temperature, PZR heaters and flow, and nitrogen Justification:

A is Correct - Bypass flow means that actual RCS flow is less than indicated and bypass flow effects RWLIS indicating higher than actual B is Wrong - higher is wrong but would be caused if miniflow was open. Flow is lower than indicated C is Wrong - RCS level is lower than indicated and flow is lower D is Wrong - RCS level is lower not higher and flow is lower

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 53 of 120 11/18/08 33 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

32006K6.13 Importance Rating:

2.80 Given the following plant conditions:

A LOCA has occurred on Unit 1.

RCS pressure is 750 psia and lowering.

One minute after the Train B Essential Chiller started, a fault locks out PBB-S04.

As RCS pressure is lowered from 750 to 500 psia the expected Emergency Core Cooling System injection flow will be increasing...

A.

HPSI flow into all reactor coolant loops.

B.

LPSI and HPSI flow into all reactor coolant loops.

C.

HPSI flow into reactor coolant loops 1A and 1B only.

D.

LPSI and HPSI flow into reactor coolant loops 1A and 1B only.

Answer:

A Associated KA:

100866 Active Question Bank 2004 65106 Describe the design characteristics of the HPSI pumps.

Reference Id:

Q8305 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Standard Appendix 2 K&A: Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: Pumps Justification:

A is Correct - pressure is to high for LPSI pumps to inject and HPSI will inject into all 4 cold legs and increase flow rate as pressure continues to drop B is Wrong - examinee may not know LPSI shutoff head C is Wrong - examinee may not realize that HPSI inject to all cold legs

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 54 of 120 11/18/08 D is Wrong - LPSI flow is loop specific and pressure is above shutoff head. HPSI flows to all cold legs

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 55 of 120 11/18/08 34 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

35007k5.02 Importance Rating:

3.10 Given the following conditions:

Unit 1 is in Mode 5 preparing to form a Steam bubble in the pressurizer As saturation conditions are established in the Pressurizer the most likely response of the Reactor Drain Tank (RDT) would be a...

A.

slower rate of pressure increases with larger level increases.

B.

greater rate of pressure increases with larger level increases.

C.

slower rate of pressure increases with smaller level increases.

D.

greater rate of pressure increases with smaller level increases.

Answer:

A Associated KA:

L97166 Describe how a steam bubble is drawn in the pressurizer.

Reference Id:

Q22433 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (5) 55.41 (5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40OP-9ZZ01, CSD to HSTBY mode 5 to 3 K&A: Knowledge of the operational implications of the following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR Justification:

A is Wrong -

B is Correct - As more of the non condensible gases are vented and the percentage of steam increases the pressure increases will be lower while the level increases will be larger C is Wrong -

D is Wrong -

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 56 of 120 11/18/08 35 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

38008A2.04 Importance Rating:

3.30 Given the following conditions:

A failure of both Nuclear Cooling Water pumps has occurred.

The Operating Crew has cross connected "A" EW to NC from the control room.

A small leak into one of the Reactor Coolant pump high pressure seal coolers occurs after the systems are cross-connected.

Based on these conditions, how will RMS respond?

A.

RU-155D (Letdown) alarm only. Take actions per 40AO-9ZZ05, Loss of Letdown AOP.

B.

RU-2 (ECW "A") and RU-6 (NCW) alarm. Take actions per 40AO-9ZZ03, Loss of Cooling Water AOP.

C.

RU-6 (NCW) and RU-155D (Letdown) alarm. Take actions per 40AO-9ZZ02, Excessive RCS Leakrate AOP.

D.

RU-2 (ECW "A") alarm only. Take actions per 74RM-9EF41, Radiation Monitoring System Alarm Response.

Answer:

D Associated KA:

100866 Active Question Bank 2004 65002 Explain the operation of the NC Radiation Monitoring under normal operating conditions.

Reference Id:

Q27523 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (5) 55.41 (5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

Cognitive Level:

Comprehension / Anal Question Source:

Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

74RM-9EF41, Radiation Monitoring System Alarm Response / 01-M-NCP-0001, mech print K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PRMS alarm

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 57 of 120 11/18/08 Justification:

A is Wrong - When NC and EW are X-connected only RU-2 is in the system Letdown is isolated when NCV-99 is closed B is Wrong - RU-6 is a non vital load and is isolated when NCV-99 is closed C is Wrong - see above D is Correct - RU-2 still monitors EW and is in service during the cross connect

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 58 of 120 11/18/08 36 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

33010K6.03 Importance Rating:

3.20 Unit 1 is at 100% power with the following conditions:

Pressurizer Pressure Control System (PPCS) is in "Automatic" with a setpoint of 2252 psia.

RCS pressure is 2252 psia and stable.

Subsequently the following is noted:

Main spray valve RC-100E, red and green position indicator lights are lit.

Main spray valve RC-100F, only the green position indicator light is lit.

Spray Valve Selection handswitch RCN-HS-100-10 is selected to BOTH RCS pressure is 2220 psia and lowering Pressurizer Pressure Master controller output is currently in the percent range and the pressurizer backup heaters are.

A.

0 - 32, energized B.

33 - 50, energized C.

0 - 32, de-energized D.

33 - 50, de-energized Answer:

C Associated KA:

100866 Active Question Bank 2004 L75344 Describe the response of the Pressurizer Pressure Control System to a failure of an input transmitter.

L88170 Describe the Control Room controls associated with the Pressurizer Pressure Master Controller including it's indications.

L75245 Describe the Control Room controls associated with the Pressurizer Spray Valve Controller including it's indications.

Reference Id:

Q62087 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 59 of 120 11/18/08 Technical

Reference:

LOIT lesson plan K&A: Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: PZR sprays and heaters Justification:

A is Wrong - BU heaters do not energize till 2200 psia decreasing and turn off at 2225 increasing B is Wrong - BU heaters do not energize till 2200 psia decreasing and turn off at 2225 increasing C is Correct - Spray valves operate in the 33 - 55% master controller range, prop heaters 0

- 33%. These indications are for a failed open spray valve in both they are either both open or closed and the low pressure confirms a malfunction. the Controller would be calling for increasing output of the prop heaters therefore the range would be 0 - 33% output D is Wrong - 33-55% is the full range of spray valve 2250 - 2275 psia

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 60 of 120 11/18/08 37 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

2.4.9 Importance Rating:

3.80 Given the following conditions:

Unit-1 is in Mode 5 Shutdown cooling is in service using LPSI "A" SDC flow was being maintained at 3780 gpm An event now occurs RCS level is lowering An Operator in containment reports that the "A" train LTOP is partially open Based on these conditions the mitigating strategy would be to...

A.

isolate the LTOP then place CS pump A in service.

B.

isolate the LTOP then place B train SDC in service.

C.

close LPSI pump A suction valve, (SIA-HV-683) then place CS pump A in service.

D.

close LPSI pump A suction valve, (SIA-HV-683) then place B train SDC in service.

Answer:

B Associated KA:

L56421 Given plant conditions determine whether or not entry into or exit from the LMFRP is appropriate Reference Id:

Q22466 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40EP-9EO11, Lower Mode FRP K&A: Emergency Procedures / Plan Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

Justification:

A is Wrong - isolating the LTOP takes both LPSI and CS out of service B is Correct - isolate the LTOP then run the un-affected loop

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 61 of 120 11/18/08 C is Wrong - examinee may not be aware of LTOP location and assume that LPSI suction will isolate the LTOP D is Wrong - examinee may not be aware of LTOP location and assume that LPSI suction will isolate the LTOP

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 62 of 120 11/18/08 38 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

37012k1.06 Importance Rating:

3.10 Unit 1 is operating at 100% power when the following events occur:

RCP 1A trips All 4 RPS channels of CPCs DNBR & LPD pre-trips and trips have initiated All 4 RPS channels SG-1 Lo Flow trips have initiated DNBR LO is in fast flash on the Reactor Trip 1st Out Annunciator board All attempts to trip the Reactor from the Control Room have failed Phase current lights are still illuminated An AO has been sent to open the Reactor Trip Switchgear breakers locally Under these conditions the Main Turbine...

A.

tripped when the Reactor trip signal was generated.

B.

will trip when the Reactor trip undervoltage relays are actuated.

C.

will trip following the Reactor trip when the Overspeed signal is generated.

D.

will trip following the Reactor trip when the Reverse Power signal is generated.

Answer:

B Associated KA:

L77391 Describe the conditions that will result in a trip of the Main Turbine Reference Id:

Q10506 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

01-E-MAB-0008 K&A: Knowledge of the physical connections and/or cause effect relationships between the RPS and the following systems: T/G Justification:

A is Wrong - Turbine trip is generated by the UVRX relays which function with the reactor trip B is Correct - Turbine trip is generated by the UVRX relays which come from the RTSG breakers

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 63 of 120 11/18/08 C is Wrong - trips before the overspeed signal is generated D is Wrong - This would be (describes) on a Sequential trip

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 64 of 120 11/18/08 39 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

32013K4.06 Importance Rating:

4.00 Given the following conditions:

Inadvertant "A" train Recirculation Actuation Signal (RAS) has initiated The initiating signal has been cleared Resetting the RAS signal requires which of the following actions? The Operator must....

A.

depress either AUX relay cabinet reset pushbutton only B.

depress both AUX relay cabinet reset pushbuttons simultaneously C.

reset the board 5 RAS initiation light then depress either AUX relay cabinet reset pushbutton D.

reset the board 5 RAS initiation light then depress both AUX relay cabinet reset pushbuttons simultaneously Answer:

A Associated KA:

L77239 Describe how an ESFAS subsystem can be manually actuated and manually reset from the Aux Relay Cabinets.

100866 Active Question Bank 2004 Reference Id:

Q8248 Difficulty:

2.00 Time to complete:

1 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

LOIT lesson plans K&A: Knowledge of ESFAS design feature(s) and/or interlocks(s) which provide for the following Recirculation actuation system reset Justification:

A is Correct - de-pressing either button will immediately power up the actuation relays energizing the lockout relay and repositions contact to rest the signal B is wrong - both reset will reset the signal but does not meet the only if criteria

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 65 of 120 11/18/08 C is wrong - this will reset the signal but does not meet the only if criteria the board light is only indication D is wrong - this will clear the RAS signal but the second pushbutton and board 5 reset are not required 40 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

35022k1.04 Importance Rating:

2.90 The Containment Normal ACUs are cooled by (a) and will be isolated by a (b).

A.

(a) Normal Chilled Water (b) CIAS B.

(a) Normal Chilled Water (b) CSAS C.

(a) Nuclear Cooling Water (b) CIAS D.

(a) Nuclear Cooling Water (b) CSAS Answer:

A Associated KA:

74427 Describe how the Containment Building HVAC System is supported by the following systems:

• Nuclear Cooling Water (NC)

• Normal Chilled Water (WC)

• Engineered Safety Features Actuation System (ESFAS)

• Balance of Plant-Engineered Safety Features Actuation System (BOP-ESFAS)

Reference Id:

Q10509 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.41 (4) 55.41 (4) Secondary coolant and auxiliary systems that affect the facility.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

LOIT lesson plan, 40OP-9HC01 (contmt HVAC), 01-M-WCP-0001 K&A: Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems: Chilled water Justification:

A is Correct - WC supplies Cntmt normal HVAC and isolates on a CIAS B is Wrong - right supply but normal chilled water isolates on CIAS not CSAS C is Wrong - wrong supply but correct isolation signal / NCW supplies the CEDM coolers D is Wrong - wrong supply wrong signal

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 66 of 120 11/18/08 41 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

2.2.41 Importance Rating:

3.50 Using the provided electrical print (01-E-HCB-004) determine which one of the following statements is correct regarding the operation/status of Containment Normal ACUs.

HCN-A01A(s)...

A.

motor space heater power is supplied by NHN-D20 B.

requires a SIAS signal and CS-1 taken to stop to energize the OR relay C.

shutdowns or trips are limited to (3) CS-1 to Stop/PTL, Load Shed or SIAS signal D.

will start 20 seconds after CTMT Normal ACU Fan B diff press LO signal is sensed Answer:

B Associated KA:

15946 Check of print logic Reference Id:

Q22440 Difficulty:

4.00 Time to complete:

5 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: 01-E-HCB-004 Technical

Reference:

01-E-HCB-004 K&A: Ability to obtain and interpret station electrical and mechanical drawings.

Justification:

A is Wrong - D20 is the supply for the D unit [in brackets]

B is Correct - SIAS stop after start is in the J13 path C is Wrong - left out the 86 lockout D is Wrong - 60 seconds after the start the TDE can be set 20 - 200 seconds

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 67 of 120 11/18/08 42 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

35026k3.01 Importance Rating:

3.90 Given the following conditions:

Unit 1 operating at 100% power A "B" train inadvertant CSAS has actuated Which one of the following conditions will result?

A.

Letdown flow has isolated B.

CEDM coolers are running but without cooling water C.

"B & D" RTSG breakers have opened with no reactor trip D.

CS pump "B" can only be stopped by going to start getting the OR light then going to stop Answer:

B Associated KA:

L56750 Determine the plant impact of an inadvertent CSAS actuation and the actions needed to restore plant stability Reference Id:

Q22436 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ17, Inadvertant PPS-ESFAS actuation K&A: Knowledge of the effect that a loss or malfunction of the CSS will have on the following: CCS Justification:

A is Wrong - Letdown isolates on SIAS/CIAS or high regen HX temperature B is Correct - CSAS isolates Nuclear Cooling water flow to containment C is Wrong - this will not make up the PPS matrix to open any RTSG breakers, although a full train actuation could be confused with RTSG breakers opening D is Wrong - must be stopped by anti-pumping the breaker, this describes how to stop the pump on an inadvertant SIAS

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 68 of 120 11/18/08

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 69 of 120 11/18/08 43 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

34039a4.07 Importance Rating:

2.80 Proper operation of an ADV from the control room requires that the operator initially check the thumbwheel set at zero for the controller, and enable (a) then (b).

A.

(a) both of the permissives (b) set the controller for the desired demand, the valve should open immediately.

B.

(a) either of the permissives (b) set the controller for the desired demand, the valve should open within 1 minute.

C.

(a) either of the permissives (b) set the demand to 30%, the valve should open immediately, then adjust controller demand as desired.

D.

(a) both of the permissives (b) set the demand to 30%, the valve should open within 1 minute, then adjust controller demand as desired.

Answer:

D Associated KA:

L75014 Explain the operation of the Atmospheric Dump Valves under normal operating conditions.

Reference Id:

Q3770 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40OP-9SG01, Main Steam K&A: Ability to manually operate and/or monitor in the control room: Steam dump valves.

Justification:

A is Wrong - requires both permissives and initial opening requires the demand be set at 30% also requires a minute to open B is Wrong - initial opening requires the demand be set at 30% (PV event)

C is Wrong - requires both permissives requires a minute to open D is Correct - this is correct operation per PVNGS note in the procedure mentions valve opens within a minute after to apply force required to overcome bonnet pressure. This reflect back to the PVNGS event of the 80s when the CR operators were unable to operate ADVs from the CR due to setting demand to low (10%)

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 70 of 120 11/18/08

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 71 of 120 11/18/08 44 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

34059k4.16 Importance Rating:

3.10 Four conditions that will cause an automatic Feedwater Pump Trip are Lo Vacuum,...

A.

Hi vibrations, Hi discharge pressure and Thrust Bearing Wear B.

Lo bearing oil pressure, Loss of speed signal and Hi vibrations C.

Thrust Bearing Wear, Lo suction pressure and Hi discharge pressure D.

Lo suction pressure, Lo bearing oil pressure and Loss of speed signal Answer:

C Associated KA:

100866 Active Question Bank 2004 L74627 Describe the conditions required to generate the following annunciators.

• FWPT Trip

• FWPT Trip Ckt Energized

• FWPT Lube Oil Press Low

• FWPT High Vibration

• FWP Discharge Press High

• FWPT Suction Pressure Low L82496 Explain the operation of the MFWP Turbine Trip subsystem under normal operating conditions.

Reference Id:

Q3418 Difficulty:

3.00 Time to complete:

5 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AL-9RK6A windows 3B, 5A, 2A & 3C K&A: Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following: Automatic trips for MFW pumps Justification:

A is Wrong - Hi vibrations is alarm not trip B is Wrong - Loss of speed signal and Hi vibrations are is alarms not trip C is Correct - all trips not alarms D is Wrong - Loss of speed signal is alarm not trip

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 72 of 120 11/18/08

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 73 of 120 11/18/08 45 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

34061a2.05 Importance Rating:

3.10 Given the following plant conditions:

Unit 1 tripped from 100% full power.

SPTA's in progress SIAS, CIAS, MSIS, and AFAS-1 have initiated.

The RCS is in forced circulation.

Steam Generator #1 pressure is 745 psia and dropping rapidly.

Steam Generator #1 level is 8% WR and dropping rapidly Steam Generator #2 pressure is 940 psia and slowly lowering.

Steam Generator #2 level is 37% WR and slowly lowering.

Auxiliary feedwater flow is > 2000 gpm to steam generator #1.

Auxiliary feedwater flow is 0 gpm to steam generator #2.

Which ONE of the following actions correctly address the existing symptoms in accordance with the Excess Steam Demand procedure?

A.

AFAS-2 has failed. Throttle and balance flow to each steam generator.

B.

SG 2 > SG 1 lockout has failed. Stop feeding SG #1 and allow SG #2 to feed in RTO.

C.

AFAS-2 has failed. Initiate maximum flow to SG #2, allow maximum flow to SG

1. 1 until level is greater than 10%.

D.

SG 2 > SG 1 lockout has failed. Stop feeding SG #1 and ensure auxiliary feedwater flow is restoring level in SG #2.

Answer:

D Associated KA:

L11202 Given conditions of an ESD describe the mitigating strategy outlined in the ESD EOP Reference Id:

Q10244 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.41 (5) 55.41 (5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

Cognitive Level:

Comprehension / Anal Question Source:

Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AL-9RK5B windows 5B08C/9C, ESD procedure

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 74 of 120 11/18/08 K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Automatic control malfunction Justification:

A is Wrong - SG 2 is > AFAS setpoint and flow and SG 1 flow needs to be stopped B is Wrong - delta-P lockout has failed but RCS is to cold to feed SG 2, 940# = 537 degrees which is prevents RTO flow C is Wrong - AFAS-2 is fine. SG 2 doesn't not need max flow and SG 1 feed should be stopped D is Correct - DP lockout has failed setpoint is 185 psid, stop feeding SG 1

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 75 of 120 11/18/08 46 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

34061k4.12 Importance Rating:

3.50 Which one of the following are design features or interlocks of the Auxiliary Feedwater system that will promote natural circulation flow?

The backup water source is the....

A.

Recycle Monitor Tanks and AFAS maintains SG water level no less than 25%

WR B.

Recycle Monitor Tanks and AFAS maintains SG water level no less than 45%

WR C.

Reactor Makeup Water Tank and AFAS maintains SG water level no less than 25% WR D.

Reactor Makeup Water Tank and AFAS maintains SG water level no less than 45% WR Answer:

C Associated KA:

78325 Discuss the purpose and conditions under which the Auxiliary Feedwater System is designed to function.

Reference Id:

Q22439 Difficulty:

2.00 Time to complete:

1 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

Tech Specs 3.3.1 & 3.3.5 / LOIT lesson plan K&A: Knowledge of AFW design feature(s) and/or interlock(s) which provide for the following: Natural circulation flow Justification:

A is Wrong - Backup is RMWT but 25% is AFAS setpoint B is Wrong - Backup is RMWT and 45% is RX trip setpoint C is Correct - Backup is RMWT and AFAS setpoint is 25%

D is Wrong - Backup is RMWT and 45% is RX trip setpoint

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 76 of 120 11/18/08 47 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

36062a2.05 Importance Rating:

2.90 Given the following conditions:

Unit 1 was manually tripped due to excessive RCS leakage Offsite power was lost on the trip DG "B" tripped due to "Generator Differential" signal SIAS/CIAS initiated due low Pressurizer pressure Containment pressure is 1.0 psig and slowly increasing HPSI "A" tripped on overcurrent and an 86 lockout The CRS has entered the Functional Recovery procedure due to a loss of Safety Function(s)

Which one of the following actions will restore the Jeopardized Safety Function(s)?

A.

Reset the 86 lockout and start HPSI pump A to restore Inventory Control B.

Depressurize the RCS to allow LPSI injection flow to restore Inventory Control C.

Override and start DG "B", the sequencer will start HPSI pump B to restore MVAC and Inventory Control D.

Energize PBB-S04 from the "A" DG, HPSI pump B must be manually started to restore MVAC and Inventory Control Answer:

D Associated KA:

L54947 Given conditions of a loss of offsite power with one vital 4.16 kV AC bus deenergized and restoration is desired cross-tie a DG to the opposite class bus Reference Id:

Q22454 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40EP-9EO09, MVAC-2 (appendix 59) / Relay Resetting, 40DP-0OP02 K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Methods for energizing a dead bus Justification:

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 77 of 120 11/18/08 A is Wrong - Both MVAC and IC are jeopardized, it is permitted to reset an 86 from the Control Room on a bus supplied by a DG but the pump will trip again with the 86 fault still present B is Wrong - restoring LPSI flow may address IC but not Bus Plus criteria C is Wrong - Override will not work Gen. Differential is an Emergency Run trip D is Correct - A DG is available and will restore Bus Plus and IC issues. The HPSI pump must be manually started due to 86 loads per the Standard Appendix

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 78 of 120 11/18/08 48 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

36063k2.01 Importance Rating:

2.90 Unit 1 had been operating at 100% power when an event occurred with the following results:

Reactor has tripped Main Turbine tripped Fast Bus Transfer did not actuate The Main Generator breakers MAN-915/918 had to be manually tripped The Main Generator tripped only after excitation was lost Steam Bypass Control system is unavailable The plant computer (PC) was lost after the main turbine tripped These conditions could have been the result of a loss of which of the following?

A.

NNN-D11 B.

NNN-D12 C.

NKN-M45 D.

NKN-M46 Answer:

C Associated KA:

L68063 Describe the circuit paths to include these major components:

• Control Centers M45 and M46

• Batteries

• Battery Chargers

• Distribution Panels Reference Id:

Q22467 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AO-0ZZ14, Loss of Non-class Instrument or Control Power K&A: Knowledge of bus power supplies to the following: Major dc loads Justification:

A is Wrong - this would also make SBCS fail B is Wrong - This would also make SBCS fail

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 79 of 120 11/18/08 C is Correct - M45 causes these effects and is the normal power supply for the plant computer D is Wrong - this is the other major 130 vdc bus, examinee may confuse buses 49 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

36064k1.03 Importance Rating:

3.60 Per LCO 3.8.3, Diesel Generator Fuel OIl Storage Tank level must be maintained greater than (a) level in order to provide storage for (b) days of continuous 100% rated output operation of the Diesel Generator.

A.

(a) 71% (b) 7 B.

(a) 80% (b) 7 C.

(a) 71% (b) 10 D.

(a) 80% (b) 10 Answer:

B Associated KA:

L75054 Explain the operation of the Diesel Fuel Oil sub-system under normal operating conditions.

Reference Id:

Q10512 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.41 (8) 55.41 (8) Components, capacity, and functions of emergency systems.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Tech Specs and Bases K&A: Knowledge of the physical connections and/or cause-effect relationships between the ED/G system and the following systems: Diesel fuel oil supply system Justification:

A is Wrong - 71% is mentioned in TS and is the level below which 3.0.3 would apply. 7 days is correct B is Correct - 80% and 7 days per LCO 3.8.3 C is Wrong - 10 days is the LCO limit per 3.8.1 D is Wrong - 10 days is the LCO limit per 3.8.1

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 80 of 120 11/18/08

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 81 of 120 11/18/08 50 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

37073a1.01 Importance Rating:

3.20 Given the following Unit 1 conditions:

The plant is in a normal full power alignment Dry Cask storage and transfer operations are in progress "A" train of Control Room Essential Filtration System (CREFAS) is in bypass An event occurs causing Hi Radiation levels in the Fuel Building Provided Information RU-19 is the New fuel storage area monitor RU-31 is the Spent Fuel Pool Area monitor RU-145 is the Fuel building ventilation monitor RU-146 is the Fuel building ventilation monitor Which one of the following should occur if radiation levels continue to increase?

A.

RU-145 will shutdown, RU-146 comes on line B.

RU-31 will shutdown, RU-146 will come on line C.

RU -19 will initiate a full FBEVAS and CREFAS actuation D.

RU-145 will initiate a full FBEVAS actuation, only B train CREFAS actuates Answer:

A Associated KA:

66731 Describe the interlocks associated with the Radiation Monitors at PVNGS Reference Id:

Q10513 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

LOIT lesson plan / 40OP-9SA01, BOP ESFAS operations / System Training Manuals K&A: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including: Radiation levels

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 82 of 120 11/18/08 Justification:

A is Correct - RU-145 (low range) will shutdown after FBEVAS due to the monitor becoming over saturated, RU-146 high range comes on line B is Wrong - RU-31does not shutdown C is Wrong - RU-19 does not actuate either FBEVAS signal, RU-31/145 D is Wrong - Ru-145 will initiate a full FBEVAS signal and both trains of CREFAS sill initiate. X-trips are downstream of bypass

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 83 of 120 11/18/08 51 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

34076a1.02 Importance Rating:

2.60 Given the following conditions:

Unit 1 is operating at rated power Plant Cooling Water pump PWN-P01A is in service Ignoring the Air Removal Seal Coolers, A loss of PWN-P01A....

A.

cause an auto start of PWN-P01B and only the Turbine Cooling water system will heat up if PCW flow is not restored B.

require a manual start of PWN-P01B and only the Nuclear Cooling water system will heat up if PCW flow is not restored C.

cause an auto start of PWN-P01B and the Turbine and Nuclear Cooling water systems will heat up if PCW flow is not restored D.

require a manual start of PWN-P01B and both the Turbine and Nuclear Cooling water systems will heat up if PCW flow is not restored Answer:

C Associated KA:

L62235 Given the Loss of Cooling Water AOP is being performed determine the appropriate mitigating strategies for a loss of plant cooling water L74242 Describe the Control Room controls associated with the PW Pumps, including their indications.

Reference Id:

Q22465 Difficulty:

2.00 Time to complete:

3 10CFR Category:

CFR 55.41 (4) 55.41 (4) Secondary coolant and auxiliary systems that affect the facility.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40A0-9ZZ03, Loss of Cooling Water AOP K&A: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures.

Justification:

A is Wrong - auto start is correct but PCW cools both NC and TC B is Wrong - manual start is not required auto start will work and cools both systems

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 84 of 120 11/18/08 C is Correct - auto start and cools both NC and TC systems D is Wrong - manual start is not required auto start will work and cools both systems

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 85 of 120 11/18/08 52 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

36062k3.02 Importance Rating:

4.10 Given the following conditions:

All 3 units are operating at 100% power All 3 units are in a normal electric plant alignment Startup transformer 3 faults and is de-energized Which one of the following describes the status of the Diesel Generators?

A.

Unit 1: DG A is supplying PBA-S03 Unit 2: DG A is supplying PBA-S03 B.

Unit 1: DG A is supplying PBA-S03 Unit 2: DG B is supplying PBB-S04 C.

Unit 3: DG A is supplying PBA-S03 Unit 3: DG B is supplying PBB-S04 D.

Unit 1: DG B is supplying PBB-S04 Unit 2: DG A is supplying PBA-S03 Answer:

B Associated KA:

30264 Unit differences Reference Id:

Q22483 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

electrical prints and simplified drawings K&A: Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: ED/G Justification: Startup transformer X03 is the normal supply for Unit 1 S05 and Unit 2 S06 therefore the unit 1 "A" and unit 2 "B" DGs will start and load on their respective buses, XO3 is the alternate for unit 3 buses A is Wrong -

B is Correct -

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 86 of 120 11/18/08 C is Wrong -

D is Wrong -

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 87 of 120 11/18/08 53 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

38078a3.01 Importance Rating:

3.10 Given the following conditions:

Unit 1 is operating in a normal full power alignment Only the "lead" air compressor is running The normal Instrument Air pressure is (a) psig and the Nitrogen backup valve opens at (b) psig.

A.

(a) 115 (b) 95 B.

(a) 115 (b) 85 C.

(a) 105 (b) 95 D.

(a) 105 (b) 85 Answer:

B Associated KA:

L76595 Describe the Control Room indications associated with the Instrument Air system.

Reference Id:

Q10515 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40OP-9IA01, IA system / 40AL-9RK7B, 7B01B ARP K&A: Ability to monitor automatic operation of the IAS, including: Air pressure Justification:

A is Wrong - 115 is correct but 95 is the low pressure alarm B is Correct - 115 is correct and the N2 backup opens at 85 psig C is Wrong - 105 is when the 3rd compressor should start and 95 is the low pressure alarm D is Wrong - 105 is when the 3rd compressor should start but 85 is when the backup opens

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 88 of 120 11/18/08 54 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

35103a3.01 Importance Rating:

3.90 Given the following plant conditions:

Containment pressure Channel A is 3.4 psig Containment pressure Channel B is 2.7 psig Containment pressure Channel C is 3.1 psig Containment pressure Channel D is 2.6 psig Pressurizer pressure Channel A is 1845 psia Pressurizer pressure Channel B is 1830 psia Pressurizer pressure Channel C is 1832 psia Pressurizer pressure Channel D is 1840 psia SG 1 pressure Channel A is 980 psia SG 1 pressure Channel B is 950 psia SG 1 pressure Channel C is 970 psia SG 1 pressure Channel D is 970 psia Any required ESFAS actuations have properly initiated

• Assuming NO Operator actions, the SG sample valves are....

A.

closed due to SIAS and CIAS actuations B.

closed due to a SIAS and MSIS actuations C.

open, Hi containment trip setpoint (CIAS) has not been reached D.

open, Lo SG pressure trip setpoint (MSIS) has not been reached Answer:

B Associated KA:

L77167 Describe what automatically initiates the Containment Isolation Actuation System (CIAS) and its function.

Reference Id:

Q10516 Difficulty:

4.00 Time to complete:

4 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

41AL-9RK5B windows 5C, 6C and 7C / prints

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 89 of 120 11/18/08 K&A: Ability to monitor automatic operation of the containment system, including:

Containment isolation Justification: 3.0 psig in cntmt will initiate CIAS, SIAS and MSIS signals A is Wrong - Valves will be closed, but CIAS does not close these valves B is Correct - Valves will be closed due MSIS (cntmt press) and SIAS (Pzr press). CIAS although the same setpoint does not close these valves C is Wrong - open is wrong and CIAS initiates at 3 psig D is Wrong - open is wrong but it is true that Lo pressure MSIS has not initiate

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 90 of 120 11/18/08 55 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 1 K/A #

35103k3.03 Importance Rating:

3.70 Given the following conditions:

Unit 1 is in Mode 6 Refueling Purge is in operation Core alterations are in progress RU-38, Power Access Purge "B" monitor failed high and has been placed in Bypass Effluents Tech reports that RU-37, Power Access Purge "A" Monitor has failed a channel check and recommends that the monitor be declared Inoperable Which one of the following actions is required?

A.

Containment must be evacuated B.

Core alterations must be stopped C.

RU-34, Containment Building Refueling Purge Monitor must be placed in service D.

Both trains of Control Room Essential Filtration Actuation System (CREFAS) must be placed in service Answer:

B Associated KA:

75094 Describe LCO 3.9.3 and its basis.

Reference Id:

Q10517 Difficulty:

4.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

LCO 3.9.3 K&A: Knowledge of the effect that a loss or malfunction of the containment system will have on the following: Loss of containment integrity under refueling operations.

Justification:

A is Wrong - there is no accident in progress just a monitor/setpoint failure B is Correct - LCO 3.9.3 requires that during core alterations contmt penetrations must be operable this would include CPIAS closure of refueling purge valves C is Wrong - RU-34 is required for refueling purge operations

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 91 of 120 11/18/08 D is Wrong - CPIAS cross trips CREFAS but this action is not required 56 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 2 K/A #

31001k2.01 Importance Rating:

3.50 With both Control Element Drive Mechanism (CEDM) motor generators is service, a loss of (a) will de-energize the #2 CEDM motor generator and (b) phase current lights are extinguished.

A.

(a) NHN-M10 (b) no B.

(a) NGN-L10 (b) no C.

(a) NHN-M10 (b) the 2-4 leg D.

(a) NGN-L10 (b) the 2-4 leg Answer:

B Associated KA:

L80233 Explain the operation of the Motor Generator Set.

Reference Id:

Q22452 Difficulty:

2.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

LOIT lesson plan & electrical prints K&A: Knowledge of bus power supplies to the following: One-line diagram of power supply to M/G sets.

Justification:

A is Wrong - M10 is wrong but all phase current light remain lit B is Correct - L10 will trip the #2 MG set and all light remain lit due to the parallel path of the RTSG breakers C is Wrong - M10 is wrong but examinee may believe the power runs in series D is Wrong - L10 is correct but the parallel path will deep all light illuminated

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 92 of 120 11/18/08 57 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 2 K/A #

32002k6.07 Importance Rating:

2.50 Given the following conditions:

Unit 1 is operating at 100% power RCP 1A experiences a failure causing it to slow down at 1% per minute Assuming that all other input parameters remained the same, the CPC calculated value of DNBR will...

A.

not change until RCP speed reaches 95% of rated speed, then a DNBR trip will occur.

B.

not change until RCP speed reaches 95% of rated speed, then an Auxiliary trip will occur.

C.

gradually decrease until RCP speed reaches 95% of rated speed, then a DNBR trip will occur.

D.

gradually decrease until RCP speed reaches 95% of rated speed, then an Auxiliary trip will occur.

Answer:

C Associated KA:

100866 Active Question Bank 2004 L78285 Explain how RCS Mass Flow rate is calculated in the Core Protection Calculators.

L98190 Describe the function of the Reactor Coolant Pump Speed inputs to the Core Protection Calculators.

L77427 Describe the function of the Reactor Coolant Pump Speed inputs to the Core Protection Calculators.

L98190 Describe the function of the Reactor Coolant Pump Speed inputs to the Core Protection Calculators.

Reference Id:

Q3180 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Comprehension / Anal Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

LOIT lesson plan

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 93 of 120 11/18/08 K&A: Knowledge of the effect or a loss or malfunction on the following RCS components:

Pumps Justification:

A is Wrong - DNBR will reduce as speed drops then generate a DNBR/LPD trip B is Wrong - DNBR will reduce as speed drops then generate a DNBR/LPD trip aux trip is less than 2 RCPs running C is Correct - DNBR will reduce as speed drops then generate a DNBR/LPD trip D is Wrong - DNBR will reduce as speed drops then generate a DNBR/LPD trip, aux trip is less than 2 RCPs running

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 94 of 120 11/18/08 58 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 2 K/A #

31014a4.02 Importance Rating:

3.40 Given the following Unit 1 conditions:

Reactor power is currently 55% following a Large Load Reject event All systems have responded as designed The CRS has implemented 40AO-9ZZ08, Load Rejection CEDMCS has been placed in standby Reg. Group 3 CEAs are at 135 inches withdrawn Reg. Group 4 CEAs are fully inserted Proper CEA group overlap will be restored by...

A.

withdrawing Reg group 4 CEAs in manual group mode.

B.

withdrawing Reg group 4 CEAs in manual sequential mode.

C.

withdrawing Reg. group 4 CEAs in manual individual mode while maintaining CEAs within 6.6 inches.

D.

lowering the load limit pot until the "Load Limiting" light illuminates then allow the Reg group 4 CEAs to withdraw in auto sequential mode.

Answer:

A Associated KA:

L78790 Describe the CEDMCS Remote Operator Module located in the Control Room to include all switches and the meaning of each switch position.

Reference Id:

Q22484 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Large Load reject, 40AO-9ZZ08 / 40OP-9SF01, CEDMCS operations K&A: Ability to manually operate and/or monitor in the control room: Control rod mode-select switch Justification:

A is Correct - procedure directs withdraw in manual group

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 95 of 120 11/18/08 B is Wrong - MS would cause group 3 to withdraw to UGS while moving group 4 C is Wrong - this would work but not directed by procedure, 6.6 inches is na CWP/CEDMCS/Alarm limit D is Wrong - Lowering the pot is proceduraly directed but to clear the RPCB signal not to wd CEAs

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 96 of 120 11/18/08 59 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 2 K/A #

38034a1.02 Importance Rating:

2.90 Given the following conditions:

Unit 1 is in Mode 6 Core re-load is in progress LSRO reports that Refueling Pool level is slowly raising Spent Fuel Machine operator reports that the Spent Fuel pool level has lowered Which one of the following events or evolutions could explain this?

A.

FBEVAS has initiated B.

Refueling Purge supply fan has tripped C.

Improperly performed Fuel Pool Cleanup alignment D.

These level changes are expected as fuel bundles are transferred to the reactor vessel Answer:

B Associated KA:

L97324 State the requirements for RV water level during refueling.

Reference Id:

Q22460 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (5) 55.41 (5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40OP-9ZZ23, Outage GOP K&A: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Fuel Handling System operating the controls including: Water level in the refueling canal Justification:

A is Wrong: FBEVAS draws a vacuum on fuel building this would cause a lowering level if anything.

B is Correct - a change in containment pressure would be caused by a supply fan tripping as cntmt becomes more negative refueling pool level will increase

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 97 of 120 11/18/08 C is Wrong - PC-118 is open a mis-alignment would be felt on both spent fuel and refueling pools. PVNGS has numerous cleanup mis-alignment events D is Wrong - PC-118 is open net loss or gain is not seen

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 98 of 120 11/18/08 60 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 2 K/A #

34035k4.01 Importance Rating:

3.60 Given the following conditions:

Unit 1 is operating at 100% power SG 1 level transmitter LT-1111 is within the normal band SG 1 level transmitter LT-1112 is within the normal band Which one of the following describes the level transmitter signal(s) used by SG 1 DFWCS?

A.

The lower output of LT-1111 and LT1112 B.

The higher output of LT-1111 and LT-1112 C.

The average output of LT-1111 and LT-1112 D.

The output of LT-1111, unless it is out of range then LT-1112 will be selected Answer:

B Associated KA:

100866 Active Question Bank 2004 30008 Given the new DFWCS simplified print describe the processing of inputs of the DFWCS and what happens on input failures L82151 Describe the NR steam generator level inputs to DFWCS and their function.

L60980 Given a simpliifed drawing of the Feedwater Control System list the control function inputs.

L60987 Given abnormal feedwater control system indications determine which digital feedwater control system indications are abnormal.

L65871 Given a failure of a Level transmitter input to DFWCS, perform required alarm response actions L60974 Given classroom instruction and reference material demonstrate the mastery of knowledge necessary to operate the feedwater control system.

Reference Id:

Q10087 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

LOIT lesson plan

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 99 of 120 11/18/08 K&A: Knowledge of S/GS design feature(s) and/or interlock(s) which provide for the following: S/G level control Justification:

A is Wrong - DFWCS uses the higher output B is Correct - DFWCS uses the higher output C is Wrong - DFWCS uses the higher output D is Wrong - only true if LT-1111 is placed in maintenance

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 100 of 120 11/18/08 61 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 2 K/A #

34045k5.23 Importance Rating:

2.70 Given the following conditions:

Reactor power is currently at 40%

Rod control (CEDMCS) is in Auto Sequential Group 5 CEAs were at 120 inches withdrawn A power ascension to 60% is being initiated A 2 gpm boration has just been started The Control Operator has made a large clockwise adjustment on the load potentiometer The following conditions are now observed:

RK window 4A08B, T-avg / T-ref HI-LO is alarming CEA Auto Control Status has high a demand light illuminated The CEAs are....

A.

inserting at 3 inches per minute B.

inserting at 30 inches per minute C.

withdrawing at 3 inches per minute D.

withdrawing at 30 inches per minute Answer:

C Associated KA:

30269 Rod Control & Boron concentration relationship L78793 Describe the normal operation and any automatic functions / interlocks associated with CEDMCS.

Reference Id:

Q10518 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (5) 55.41 (5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AL-9RK4A, window 4A08B / LOIT lesson plan / STM

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 101 of 120 11/18/08 K&A: Knowledge of the operational implications of the following concepts as the apply to the MT/B System: Relationship between rod control and RCS boron concentration during T/G load increases Justification:

A is Wrong - this should generate a withdrawl signal B is Wrong - this should generate a withdrawl signal C is Correct -there is a high demand but auto sequential is limited to 1/10 max speed so CEAs are withdrawing at 3 inches per minute D is Wrong - 30/min is limited to manual operation or inward motion in AS

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 102 of 120 11/18/08 62 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 2 K/A #

34056k1.03 Importance Rating:

2.60 Given the following conditions:

Unit 1 is operating at rated power The Secondary is in a normal full power alignment Feedwater Pumps A & B low suction pressure alarms (white alarm lights) have annunciated Which one of the following conditions could have occured?

A.

Lo-Lo level in the A Low Pressure heater strings B.

Instrument Air isolated to B condensate pump miniflow valve C.

Condensate Demin Bypass valve CDN-PDV-195 output is 0%

D.

Either of the B condensate suction valves CDN-HV-1 or 2 has closed Answer:

B Associated KA:

L67439 Discuss the purpose and conditions under which the Condensate System is designed to function.

Reference Id:

Q10519 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.41 (5) 55.41 (5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

LOIT lesson plan / 40AL-9RK6A, window 6A05D K&A: Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and the following systems: MFW.

Justification:

A is Wrong - Hi-HI level will cause a LP string to isolate B is Correct - miniflow fails open on loss of IA C is Wrong - CDN-HV-195 is reverse acting 0% output means the valve is open = more pressure to suction D is Wrong - Both CDN_HV-1 & 2 have to close to cause the B condensate pump to trip

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 103 of 120 11/18/08 63 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 2 K/A #

2.1.4 Importance Rating:

3.30 Per Conduct of Shift Operations, 40DP-9OP02, the minimum requirements to maintain an active Reactor Operator license are...

A.

40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of licensed watchstanding duties in the previous month B.

60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of licensed watchstanding duties in the previous month C.

40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of licensed watchstanding duties in the previous calendar quarter D.

60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of licensed watchstanding duties in the previous calendar quarter Answer:

D Associated KA:

L12030 State the minimum requirements for shift crew manning.

Reference Id:

Q10520 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40DP-9OP02 K&A: Conduct of Operations: Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

Justification:

D is Correct - 60 HOURS PER QUARTER IS THE ONLY CORRECT ANSWER

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 104 of 120 11/18/08 64 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 2 K/A #

38075a2.03 Importance Rating:

2.50 Given the following conditions:

Unit 1 is operating at 55% power Condenser vacuum has degraded to 8 inches HgA As a result the Circulating Water System makeup flow demand will be (a) and the degraded vacuum results in a (b)

A.

(a) unchanged (b) condenser interlock actuation, Implement the Loss of Vacuum AOP B.

(a) lower (b) a main turbine trip with a condenser interlock requiring a reactor trip and performance of SPTAs C.

(a) unchanged (b) main turbine trip and associated Reactor Power Cutback implement the Load Rejection AOP D.

(a) lower (b) main feedpump trip and associated Reactor Power Cutback implement the Loss of Feedpump AOP Answer:

B Associated KA:

L65647 Describe the main condenser vacuum interlock associated with the SBCS System including how it is reset.

Reference Id:

Q22456 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.41 (5) 55.41 (5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ07, Loss of Condenser Vacuum / 40OP-9SF04, Operation of RPCB system K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Safety features and relationship between condenser vacuum, turbine trip, and steam dump Justification: Circ Water makeup flow and temperature will lower due to a reactor trip on loss of vacuum

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 105 of 120 11/18/08 A is Wrong - lower, and a reactor trip is required B is Correct - main turbine auto trips at 7.5 inches but without vacuum 5,5 inches a reactor trip is required C is Wrong - main turbine trips but RPCB is OOS at 55% power (removed below 70%)

D is Wrong - MFPs trip at 13.5 inches and RPCB is OOS

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 106 of 120 11/18/08 65 This Exam Level RO Apears on:

RO EXAM 2008 Tier 2 Group 2 K/A #

34055a3.03 Importance Rating:

2.50 Which one of the following statements describe the automatic actions that will occur upon a HIGH alarm on RU-141, Condenser Vacuum Pump/Gland Seal Exhaust monitor?

The Post Filter...

A.

bypass valve, Inlet valve and Outlet valve all close.

B.

bypass valve opens and the Post Filter Blower starts.

C.

blower will stop and the Post Filter Inlet and Outlet valves will open.

D.

bypass valve will close, Inlet valve opens and the Post Filter Blower starts.

Answer:

D Associated KA:

100866 Active Question Bank 2004 L62447 Explain the operation of the Post Filter Unit under normal operating conditions.

Reference Id:

Q7338 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

LOIT lesson plan / Mech print 01-M-ARP-001 K&A: Ability to monitor automatic operation of the CARS, including: Automatic diversion of CARS exhaust Justification: If the examinee doesn't understand the system any of these combinations may seen plausible A is Wrong - may believe that a high alarm causes all flow to stop preventing a release B is Wrong - my believe that we go into a high flow exhaust mode such as the hogging mode on condenser vacuum startup C is Wrong - flow reduces to allow absorption time D is Correct - RU-141 HIGH causes the unit to go into the thru filter mode 19A bypass closes and 19B inlet opens along with the blower starting

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 107 of 120 11/18/08

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 108 of 120 11/18/08 66 This Exam Level RO Apears on:

RO EXAM 2008 Tier 3 K/A #

2.1.27 Importance Rating:

3.90 Why do the the Fuel Building Essential AFUs automatically align to the Auxiliary Building during a SIAS?

A.

The essential AFUs augment the normal AFUs, ensuring a negative pressure is maintained.

B.

Due to the number of additional heat loads, such as motors and piping, additional air movement is necessary.

C.

The essential AFUs are responsible for treating the air below the 100' elevation, which may contain contamination from a SI pump seal failure.

D.

Since the normal AHUs and AFUs trip on a SIAS, the Fuel Building Essential AFUs will ensure a negative pressure is kept on the building.

Answer:

C Associated KA:

67350 Discuss the purpose and conditions under which the Fuel Building HVAC System is designed to function.

N77019 Describe the normal operation of the Normal Exhaust AFUs.

L62455 Given that a SIAS has actuated Identify why the Fuel Building essentials AFU take a suctions on the AUX building below the 100' 100866 Active Question Bank 2004 Reference Id:

Q8310 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Tech Spec Bases 3.7.13 K&A: Conduct of Operations: Knowledge of system purpose and or function.

Justification:

A is Wrong - negative pressure is maintained by an equal number of exhaust and supply units running B is Wrong - essential room coolers start when pumps start on an ESFAS actuation C is Correct - per the TS bases, filtration is required for an assumed seal failure

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 109 of 120 11/18/08 D is Wrong - The normal AFRO and AHOy do not trip on a SIAS 67 This Exam Level RO Apears on:

RO EXAM 2008 Tier 3 K/A #

2.1.34 Importance Rating:

2.70 Which one of the below listed conditions would require an immediate Reactor trip?

A.

RCP 1A seal failure and Bleedoff flow is 7 gpm B.

RCS leak with letdown is service, 3 charging pumps operating and lowering pressurizer level C.

Main Generator sync'd to the grid with 1400 MW output and Condenser Vacuum is 5 inches HgA D.

Steam Generator Chemistry, Chlorides are > 1 ppm with a corresponding rise in Cation Conductivity Answer:

D Associated KA:

L10043 Determine if a reactor trip is necessary and if so, what actions are required after the trip Reference Id:

Q22405 Difficulty:

4.00 Time to complete:

3 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AO-9ZZ04, RCP emergencies / 40AO-9ZZ07, Loss of Vacuum /

40AO-9ZZ10 Condenser Tube Rupture K&A: Conduct of Operations: Knowledge of primary and secondary plant chemistry limits Justification:

A is Wrong - BO must be greater than 9.5 gpm B is Wrong - Letdown must be out of service C is Wrong - this would be true for low turbine load ie < 410 MW D is Correct - per 40AO-9ZZ10 high clorides with increasing conductivity = trip

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 110 of 120 11/18/08 68 This Exam Level RO Apears on:

RO EXAM 2008 Tier 3 K/A #

2.2.21 Importance Rating:

2.90 Unit 1 is operating at rated power with the following conditions:

Essential Cooling Water pump A failed its Inservice Test, 73ST-9EW01 Differential Pressure (psid) did not meet acceptance criteria EWA-P01 was declared Inoperable All EWA-P01 maintenance activities have been completed All EWA-P01 TDs and alignments have been completed 73ST-9EW01 has been completed satisfactorily 73ST-9EW01 acceptance review has not been completed 73ST-9EW01 CRS approval has not been completed The EWA-P01 pump status....

A.

is Operable when the TDs and alignments were completed B.

is currently available but not Operable until the CRS review is complete C.

is currently available but not Operable until the acceptance review is complete D.

is currently available but can only be declared Operable when the auto start function is verified Answer:

C Associated KA:

L79568 Given a copy of TS and the TRM Determine if a specific piece of equipment is required to be operable.

Reference Id:

Q22469 Difficulty:

4.00 Time to complete:

3 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

73DP-9ZZ14, Surveillance Testing K&A: Equipment Control Knowledge of pre-and post-maintenance operability requirements.

Justification:

A is Wrong - operability depends on st closure, this makes the pump available B is Wrong - CRS review is not required for 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 111 of 120 11/18/08 C is Correct - acceptance reviewer responsibilities D is Wrong - this function did not fail in the ST and rebuild would not effect auto start feature

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 112 of 120 11/18/08 69 This Exam Level RO Apears on:

RO EXAM 2008 Tier 3 K/A #

2.1.7 Importance Rating:

4.40 Given the following conditions:

Unit 1 is operating at rated power You observe channels "A and C" Steam Generator 1 level at 92% NR You should...

A.

immediately trip the reactor B.

request permission from the CRS then trip the reactor C.

verify that a High Level Override has actuated on both SGs D.

verify SG 1 level on the remaining channels then take any appropriate actions Answer:

A Associated KA:

L82271 Describe the response of the DFWCS to excessively high SG levels.

Reference Id:

Q22462 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (5) 55.41 (5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

Tech Specs / Conduct of Shift Operations, 40DP-9OP02 / LOIT lesson plan K&A: Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Justification:

A is Correct - PVNGS setpoint for SG high level trip is 91% NR. RO responsibility to trip RX if setpoint is exceeded B is Wrong - See above C is Wrong - HLO override occurs at 88%but us SG specific the cross level signal is only used a SG has a > 15% level deviation on its own level transmitters

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 113 of 120 11/18/08 D is Wrong - two channels above setpoint means RX should be tripped, no matter what the other channels read 70 This Exam Level RO Apears on:

RO EXAM 2008 Tier 3 K/A #

2.2.42 Importance Rating:

3.90 Given the following conditions:

Unit 1 is operating at rated power Which one of the following conditions require entry in to a Tech Spec LCO action?

A.

610 psig in SIT 1A B.

57% Pressurizer level C.

86 lockout/trip of the "A" Fuel Pool Cooling pump D.

86 lockout/trip of a single DG "A" starting air compressor Answer:

B Associated KA:

L89775 Given a set of plant conditions determine whether or not the LCOs of 3.4 are satisfied Reference Id:

Q22407 Difficulty:

4.00 Time to complete:

3 10CFR Category:

CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Tech specs K&A: Equipment Control: Ability to recognize system parameters that are entry level conditions for Tech Specs Justification:

A is Wrong - 610 psig is the low alarm, TS is 600 psig B is Correct - LCO 3.4.9 27 band is 27 to 56% pzr level C is Wrong - "A" fuel pool cooling is a class powered pump but not TS, temp is the LCO D is Wrong - DG air pressure is TS not the compressors

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 114 of 120 11/18/08 71 This Exam Level RO Apears on:

RO EXAM 2008 Tier 3 K/A #

2.3.4 Importance Rating:

3.20 Which of the following is the 10 CFR20 annual exposure limit for Whole Body (TEDE) and Lens of the eyes (LDE)?

A.

1500 mrem TEDE, 15 Rem LDE B.

1500 mrem TEDE, 50 Rem LDE C.

5 Rem TEDE, 15 Rem LDE D.

5 Rem TEDE, 50 Rem LDE Answer:

C Associated KA:

30226 exposure limits Reference Id:

Q22408 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.41 (12) 55.41 (12) Radiological safety principles and procedures.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

General Employee Training / EPIP-99, appendix K K&A: Radiation Control: Knowledge of radiation exposure limits under normal or emergency conditions.

Justification:

A is Wrong - 1500mrem is the quarterly limit, 15 LDE is correct B is Wrong - 1500mrem is the quarterly limit, 50 is the extremities limit C is Correct - 5 Rem is the yearly TEDE limit and 15 is correct D is Wrong - 5 Rem is the yearly TEDE limit, 50 is the extremities limit

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 115 of 120 11/18/08 72 This Exam Level RO Apears on:

RO EXAM 2008 Tier 3 K/A #

2.3.13 Importance Rating:

3.40 Given the following conditions:

Unit 1 is operating at rated power ERFDADS leakrate has increased from.3 to 11 gpm RU-139, Main Steam Line monitor is in HIGH alarm RU-140, Main Steam Line monitor has an increasing trend RU-141, Condenser Vacuum/Gland Seal Exhaust shows an increasing trend RU-142, (all channels) Main Steam Line N-16 monitor show an increasing trend Unit 3 is supplying the Aux Steam Cross-Tie Header Which one of the following mitigating actions should be taken for this event?

A.

Align SG blowdown to the condenser B.

Select OFF on SGN-HS-1007 & 1008, Mode select switches C.

Close the Unit 3 Aux Steam isolation valve to the x-tie header D.

Verify closed CDN-HV-275, Demin Water Feed to the Condensate Service Header Answer:

B Associated KA:

L10174 Given indications of a Steam Generator Tube Leak, describe the possible adverse effects of SBCS and Aux. Stream operation, and the operator action to minimize these consequences.

Reference Id:

Q22409 Difficulty:

4.00 Time to complete:

4 10CFR Category:

CFR 55.41 (12) 55.41 (12) Radiological safety principles and procedures.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AO-9ZZ02, Excessive RCS Leakrate / 74RM-9EF41, Rad Monitor system ARP K&A: Radiation Control: Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Justification:

A is Wrong - SG blowdown is secured for a high alarm on RU-139.140. These steps may be performed later to drain a SG that is filling due to a SGTR

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 116 of 120 11/18/08 B is Correct - limits the release of contamination by disabling the SBCVs that go to atmosphere C is Wrong - this is a supply not a load, if Unit 1 was providing steam to the x-tie header than isolation would be correct D is Wrong - AOP ZZ02 directs action to provide the condensate service header with Demin water

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 117 of 120 11/18/08 73 This Exam Level RO Apears on:

RO EXAM 2008 Tier 3 K/A #

2.4.5 Importance Rating:

3.70 A plant perturbation is in progress that if not properly addressed could result in a manual or automatic Unit trip.

Which set of procedures would most likely be used to mitigate this event?

A.

Normal Operating procedures B.

General Operating procedures C.

Abnormal Operating procedures D.

Emergency Operating procedures Answer:

C Associated KA:

L10343 Given that an ORP is being implemented describe the use of an AO or OP when the reactor trips or when performing an EOP Reference Id:

Q22410 Difficulty:

2.00 Time to complete:

1 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

AOP/EOP Users Guides K&A: Emergency Procedures / Plan Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

Justification:

A is Wrong - Intended normal conditions not transients B is Wrong - For general operations, not transients C is Correct - AOPs restore normal conditions following a transient D is Wrong - Place the plant in a safe condition after a Reactor trip event

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 118 of 120 11/18/08 74 This Exam Level RO Apears on:

RO EXAM 2008 Tier 3 K/A #

2.4.26 Importance Rating:

3.10 The Palo Verde Fire Response Team includes a Fire Team Advisor (FTA) who at a minimum must be a qualified...

A.

Reactor Operator, one is required for the site.

B.

Reactor Operator, one is required for each unit.

C.

Senior Reactor Operator, one is required for the site.

D.

Senior Reactor Operator, one is required for each unit.

Answer:

A Associated KA:

L57493 Describe the responsibilities of the Fire Team Advisor in regards to Emergency Notification And Response.

Reference Id:

Q22415 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Conduct of Shift Operations K&A: Emergency Procedures / Plan Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.

Justification:

A is Correct - per the conduct of shift OPS procedure the FTA must be at a minimum an RO one for the site B is Wrong - exceeds the minimum C is Wrong - exceeds the minimum D is Wrong - exceeds the minimum

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 119 of 120 11/18/08 75 This Exam Level RO Apears on:

RO EXAM 2008 Tier 3 K/A #

2.4.32 Importance Rating:

3.60 Unit 1 is operating at 100% power when the following events occur:

A major loss of annunciators Plant Computer (PC) has failed Which one of the following actions would be appropriate?

A.

Initiate a plant shutdown B.

Immediately trip the reactor C.

Terminate any plant evolutions that are not needed D.

No special actions are required, provided that the Core Monitoring computer is available Answer:

C Associated KA:

L56949 Determine if the Loss of Annunciators AOP should be implemented.

Reference Id:

Q22464 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AO-9ZZ15, Loss of Annunciators K&A: Emergency Procedures / Plan Knowledge of operator response to loss of all annunciators.

Justification:

A is Wrong - not required by the procedure and would complicate the event but there are numerous other events that require a plant shutdown B is Wrong - see above C is Correct - stabilize the plant is the directed action D is Wrong - PC and CMC work together for COLSS and plant monitoring, examinee may believe that as long as one is good requirements are met

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Reactor Operator Exam OPTRNG_EXAM Page: 120 of 120 11/18/08 Cognitive Level Summary Number of questions linked:

75 Percentage Memory 35 35 Comprehension 0

0 Analysis 0

0 Question Source Summary Number of questions linked to source:

75 Percentage New New 52 52 Modified INPO Bank Modified 0

PV Bank Modified 10 Total Modified 10 10 Bank INPO Bank Not Modified 0

PV Bank Not Modified 13 PV NRC Exam Question Not Modified 0

Total BANK 13 13

RO ANSWER KEY

1. B

2. B

3. C

4. D

5. B

6. B

7. D

8. D

9. A

10. A

11. D DELETED

12. D

13. C

14. B

15. D

16. B

17. C

18. A

19. B

20. D

21. B

22. A

23. B

24. D

25. A

26. A

27. D

28. B

29. A

30. C

31. D

32. A

33. A

34. A

35. D

36. C

37. B

38. B

39. A

40. A

41. B

42. B

43. D

44. C

45. D

46. C

47. D

48. C

49. B

50. A

51. C

52. B

53. B

54. B

55. B

56. B

57. C

58. A

59. B

60. B

61. C

62. B

63. D

64. B

65. D

66. C

67. D

68. C

69. A

70. B

71. C

72. B

73. C

74. A

75. C

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 1 of 49 11/18/08 1

This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 1 Group 1 K/A #

2.4.44 Importance Rating:

4.40 Given the following conditions:

Unit 1 was manually tripped 10 minutes ago due to lowering Pzr pressure and level SIAS/CIAS/MSIS have properly initiated ADVs are maintaining T-cold at 551ºF RCS pressure is stable at 1500 psia HPSI flow is adequate RU-148 is reading 7.1E +06 mrem/hr RU-149 is reading 7.2E +06 mrem/hr Wind is from 210º What (if any) Protective Action Recommendations (PARs) should be made for these conditions?

A.

No PARs are required B.

Shelter within a 2-mile radius C.

Evacuation for a 2-mile radius and 5 miles in sectors A-B-C D.

Evacuation for a 2-mile radius and 5 miles in sectors B-C-D Answer:

C Associated KA:

L92708 Given the appropriate portions of EPIP-01 and either plant conditions or an EAL identify the prescribed Protective Action Recommendations.

Reference Id:

Q10469 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: EPIP-99, appendices A (table 1) & B Technical

Reference:

EPIP-99, appendices A & B K&A: Knowledge of emergency plan protective action recommendations.

Justification:

A is wrong - event is an GE requiring PARs B is wrong - event is GE.

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 2 of 49 11/18/08 C is correct

1.

loss of Fuel Clad [1-4]

2.

loss of RCS [1-16]

3.

potential loss of containment [1-11]

is a GE and the wind direction of 210 degrees is sectors A-B-C D is wrong - GE but B-C-D is wrong

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 3 of 49 11/18/08 2

This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 1 Group 1 K/A #

2.4.20 Importance Rating:

4.30 Following a reactor trip Unit 1 has the following conditions:

Pressurizer pressure is 1600 psia and stable.

PZR level is 28% and increasing.

Containment pressure is 3.5 psig and increasing.

SG #1 pressure is 1090 psia and stable.

SG #2 pressure is1100 psia and stable.

SG #1 level is 70% WR and raising.

SG #2 level is 70% WR and stable.

RCS T-cold is 560°F and slowly lowering.

Containment temperature is 112°F and increasing.

Containment humidity is 42% and increasing.

HPSI flow is 150 gpm to each loop.

SIAS/CIAS/MSIS have initiated.

The CRS has come to the step in the Emergency Operating Procedure regarding throttling HPSI flow and finds the following:

CAUTION Throttling HPSI injection valves will cause erosion to downstream piping The correct mitigating EOP for these conditions is (A) and throttling HPSI injection valves to lower HPSI flow (B)

A.

(A) ESD (B) is permitted but should be avoided B.

(A) LOCA (B) is permitted but should be avoided C.

(A) ESD (B) is only permitted by fully closing the Injection valve D.

(A) LOCA (B) is only permitted by fully closing the Injection valve Answer:

B Associated KA:

16350 Describe the use of cautions and notes in the EOPs.

Reference Id:

Q10483 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 4 of 49 11/18/08 situations.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40DP-9AP16, EOP Users Guide 40DP-9AP15 EOP writers guide K&A: Knowledge of the operational implications of EOP warnings, cautions, and notes.

Justification:

A is Wrong - ESD is wrong B is Correct - LOCA is correct and the caution would prefer full valve stroke but it is not required C is Wrong - ESD is Wrong D is Wrong - LOCA is correct but caution only warn of potential hazard not give direction

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 5 of 49 11/18/08 3

This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 1 Group 1 K/A #

2.1.25 Importance Rating:

4.20 Given the following conditions:

Unit-1 has been shutdown for five days and is currently in Mode 5 The RCS is being maintained at 102 ft 6 inches in preparation for installing Steam Generator Nozzle Dams The Steam Generator primary manways are off RCS temperature is 135 ºF Per the tables found in the Unit-1 Safety Analyses Operational Data (SAOD) during a sustained Loss of Shutdown Cooling the RCS...

A.

time to boil is 18.9 minutes B.

time to boil is 23.3 minutes C.

makeup flowrate to compensate for boil off is 76.9 gpm D.

makeup flowrate to compensate for boil off is 98.5 gpm Answer:

D Associated KA:

L56598 Given the LMFRP HR-2 is being performed, and provided with Time to Boil curves determine time to core boiling using the TTB curves in the back of the core data book and describe what this value is used for 100866 Active Question Bank 2004 Reference Id:

Q1187 Difficulty:

4.00 Time to complete:

5 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Comprehension / Anal Question Source:

Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: Unit-1 Safety Analysis Operational Data (SAOD)

Technical

Reference:

Unit-1 Safety Analysis Operational Data (SAOD)

K&A: Ability to interpret reference materials, such as graphs, curves, tables, etc.

Justification:

A is Wrong, time to boil at midloop is 14.7 minutes (18.9 comes from flange level after core reload)

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 6 of 49 11/18/08 B is Wrong, time to boil at midloop is 14.7 minutes (23.3 comes from flange level prior to core reload)

C is Wrong, 76.9 gpm is the makeup requirement for midloop after core reload D is Correct, this is the makeup rate for midloop prior to core offload

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 7 of 49 11/18/08 4

This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 1 Group 1 K/A #

42056AA209 Importance Rating:

2.90 Given the following plant conditions:

The plant is operating at 100% power NAN-S02 Fast Bus Transfer is blocked due to SWYD maintenance The "A" and "C" Containment Normal ACUs are running The "B" and "D" Containment Normal ACUs are in standby.

The "A" and "B" Normal Chillers are running NAN-S01 bus faults and de-energizes All equipment actuates as expected The CRS should implement...

A.

40EP-9EO02 (Reactor Trip) due to a loss of 2 RCPs. Normal containment ACU status is unchanged.

B.

40EP-9EO07 (LOOP) due to a loss of 4 RCPs. Normal containment cooling can be restored by energizing NAN-S02 from Offsite power.

C.

40EP-9EO07 (LOOP) due to a loss of 4 RCPs. Normal containment cooling will be restored by the auto start of the "B" and "D" ACU units.

D.

40EP-9EO02 (Reactor Trip) due to the loss of 2 RCPs. Normal containment cooling will be restored when PBA-S03 power is restored by the "A" DG.

Answer:

B Associated KA:

74452 Describe the automatic functions associated with the Containment Building Normal ACU Fans (HCN-A01-A, B, C, & D).

Reference Id:

Q10470 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40EP-0EO07(LOOP)

K&A: Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Operational status of reactor building cooling unit

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 8 of 49 11/18/08 Justification:

A is Wrong - all 4 RCPs trip due the loss of NAN-S01 tripping 2 RCPs causing a Rx trip/Turbine trip and a subsequent loss of NAN-S02due fast bus xfer blocked on the 2 side B is Correct - LOOP/LOFC due to the loss of 4 RCPs and both NAN-S01/S02 de-energized even though the switchyard is still energized. The operators have the ability to manually energize S02 following the event to restore normal containment cooling C is Wrong - LOOP is correct but the B/D units have no power for the auto start and the "A" (PBA-S03) normal chiller will have to be manually started in addition NC pumps have no power till S02 is energized D is Wrong - 4 RCPs trip and although the A normal chiller is restored by PBA-S03, NCW is still down

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 9 of 49 11/18/08 5

This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 1 Group 1 K/A #

44E02EA22 Importance Rating:

4.00 Given the following conditions:

Unit 1 was manually tripped from 100% power RU-142 (N-16 Main steam Line Monitor) channel 1 was reading 92 cpm at the time of the trip RU-142 (N-16 Main steam Line Monitor) channel 2 was reading 96 cpm at the time of the trip RCS pressure 2150 psia and slowly lowering Pressurizer level 31% and recovering SG 1 level is 65% WR and lowering SG 2 level is 60% WR and lowering NAN-S01 is de-energized PBA-S03 is de-energized NNN-D11 is de-energized RCS Thot is 565°F and slowly lowering RCS Tcold is 562°F and slowly lowering Main Feedwater flow is 0 gpm to each SG The CRS should enter...

A.

Reactor Trip (40EP-9EO02) and stabilize Tcold 560 to 570 ºF B.

Loss of All Feedwater (40EP-9EO06) and restore SG levels to 45 to 60% NR C.

Steam Generator Tube Rupture (40EP-9EO04) and lower Thot to less than 540ºF D.

Loss of Offsite Power/Loss of Forced Circulation (40EP-9EO07) and initiate MSIS Answer:

A Associated KA:

L10350 Given conditions of a reactor trip analyze whether or not entry into the Reactor Trip EOP is appropriate Reference Id:

Q10471 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None B

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 10 of 49 11/18/08 Technical

Reference:

Reactor Trip (40EP-9EO02), 40AO-9ZZ14 (Loss of non class instrument power)

K&A: Ability to determine and interpret the following as they apply to the (Reactor Trip Recovery) Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Justification:

A is Correct, all indications are consistent with RT and RT directs the use of ADVs to stabilize RCS temerature with a loss of SBCS (NNN-D11)

B is Wrong, SG feed rate is 0 gpm due to low RCS temp < 564 which is the cut off for Reactor Trip Override (RTO). Additionally AF "A" and AF "B" are available C is Wrong, low RCS temperature and pressure could be indicative of SGTR but the SG RU readings are in the normal range D is wrong, NAN-S02 is still energized

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 11 of 49 11/18/08 6

This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 1 Group 1 K/A #

44E06EA22 Importance Rating:

4.20 Given the following conditions:

Unit 1 was manually tripped due to a steam line break in the Turbine building MSIS was manually initiated SG 1 pressure is currently 1140 psia and stable SG 2 pressure is currently 1150 psia and stable Offsite power was lost on the turbine trip 4160 bus PBA-S03 has faulted and is de-energized Both SG levels are 20% WR and slowly lowering AFA-P01 has tripped on overspeed AFB-P01 has tripped due to an 86 lock-out Feed rate to both SGs is 0 gpm.

All appropriate ESFAS actuations have initiated Which one of the following would be the appropriate procedurally directed action to restore the RCS Heat Removal Safety Function?

A.

Reset AFA-P01 overspeed trip and establish feed after 40EP-9EO06 (LOAF) is entered B.

Depressurize a SG and establish feedflow with a Condensate pump after 40EP-9EO09 (FRP) is entered C.

Stop the RCPs and establish feed using a Main Feedwater pump after 40EP-9EO07 (LOOP) is entered D.

Override the Downcomer isolation valves and establish feed using AFN-P01 prior to exiting the Standard Post Trip Actions Answer:

A Associated KA:

L61371 Describe the major mitigating strategies used during a LOAF.

Reference Id:

Q10472 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Comprehension / Anal Question Source:

Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: NONE

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 12 of 49 11/18/08 Technical

Reference:

EOP Operations Expectations, 40EP-9EO01 (SPTAs). 40EP-9EO06 (LOAF)

K&A: Ability to determine and interpret the following as they apply to the (Loss of Feedwater) Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Modified from Q10472 Justification:

A is Correct - LOAF allows the resetting of AFA per appendix 38 B is Wrong - Condensate pumps are not available due the LOOP C is Wrong - LOOP will not restore feedwater and MFPs are not available due to MSIS and LOOP causing a loss of vacuum D is Wrong - AFN-P01 has lost power, PBA-S03

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 13 of 49 11/18/08 7

This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 1 Group 2 K/A #

2.3.14 Importance Rating:

3.80 Given the following conditions:

Unit 1 was manually tripped due to a tube rupture in SG 1 Offsite power was lost on the trip SG 1 has been isolated per 40EP-9EO04 (SGTR)

SG 1 pressure is 1100 psia SG 1 narrow range level is 65% and rising RCS pressure is 1400 psia RCS cooldown rate is currently 12°F/hr Which of the following are the preferred methods to maintain SG level and control the spread of contamination?

A.

Drain SG 1 to the condenser or lower RCS pressure below SG 1 pressure B.

Lower RCS pressure below SG 1 pressure or increase the RCS cooldown rate to 100°F C.

Open the affected MSIVs and steam SG 1 to the condenser or drain SG 1 to the condenser D.

Increase the RCS cooldown rate to 100°F or open the affected MSIVs and steam SG 1 to the condenser Answer:

A Associated KA:

L11232 Given the SGTR EOP is being performed outline the strategy by which water management is established and releases to the environment are minimized Reference Id:

Q22476 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.43 (4) 55.43 (4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40EP-9EO04 (SGTR), 40DP-9AP09 (SGTR Tech Guide)

K&A: Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (Loss of Condenser Vacuum)

Justification:

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 14 of 49 11/18/08 A is Correct - step 32 of SGTR directs either one of these actions B is Wrong - with a loss of offsite power CD rate is limited to 30°F per SGTR. But increasing the CD rate would get to SDC quicker limiting secondary contamination C is Wrong - Steaming to condenser is correct but not thru the MSIVs. MSIV bypasses should be used to limit secondary waterhammer D is Wrong - both of these are wrong as stated above

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 15 of 49 11/18/08 8

This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 1 Group 2 K/A #

42069AA201 Importance Rating:

4.30 Given the following:

Unit 1 is in Mode 3 NCB-UV-401 failed it's stroke time Surveillance Test and has been declared INOPERABLE Larger reference attached Containment Isolation (LCO 3.6.3)...

A.

does not apply in Mode 3 B.

can be complied with by closing and tagging NCB-UV-401 C.

does not apply, NCB-UV-401 closes on a Containment Spray signal D.

can be complied with provided that flow is maintained thru check valve NCA-V118 Answer:

B Associated KA:

L89788 Given a set of plant conditions apply the one hour or less actions statements of T.S. 3.6 Reference Id:

Q10474 Difficulty:

4.00 Time to complete:

3 10CFR Category:

CFR 55.43 (1) 55.43 (1) Conditions and limitations in the facility license.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Tech Specs 3.6.3

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 16 of 49 11/18/08 K&A: Ability to determine and interpret the following as they apply to the Loss of Containment Integrity:

Justification: this is a condition "A" type valve per table 7.0 of the TRM A is wrong - 3.6.3 applies modes 1 - 4 B is correct - LCO 3.6.3 condition A requires closed and de-activated automatic valve C is wrong - the valve does close on CSAS but CIAS does apply D is wrong - check valve can only be given credit with flow secured

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 17 of 49 11/18/08 9

This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 1 Group 2 K/A #

44A16AA22 Importance Rating:

3.30 Given the following conditions:

Letdown flow has lowered to maintain Pzr level constant.

RCS temperature is stable.

ERFDADS indicates a stable 12 gpm RCS leakrate Equipment Drain Tank (EDT) level is increasing.

RU-1 (Containment Atmosphere) is reading 7.5 E - 7 µCi/cc RU-6 (Nuclear Cooling Water) is reading 1.14 E - 06 µCi/cc RU-141, ch 1 (Condenser Vacuum/Gland Steam Exhaust) is reading 4.61 E - 07 µCi/cc Based on these conditions and referencing LCO 3.4.14 the operating crew is required to implement the Excessive RCS Leakrate AOP...

A.

section 5.0 due to SG Tube leakage. Take actions per condition B of LCO 3.4.14.

B.

section 3.0 due to RCS identified leakage. Take actions per condition A of LCO 3.4.14.

C.

section 3.0 due to RCS unidentified leakage. Take actions per condition A of LCO 3.4.14.

D.

section 4.0 due to RCS to Nuclear Cooling Water leakage. Take actions per condition B of LCO 3.4.14.

Answer:

B Associated KA:

L10169 Given indications of RCS or a Steam Generator Tube Leak, describe the basic procedure methodology, including Reactor Trip is thresholds, Reference Id:

Q10475 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.43 (1) 55.43 (1) Conditions and limitations in the facility license.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: Tech Spec LCO 3.4.14 Technical

Reference:

LCO 3.4.14, 40AO-9ZZ03 (Excessive RCS Leakage)

K&A: Adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments.

Justification:

A is Wrong. this is not a SGTL, RU 141 reading are normal

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 18 of 49 11/18/08 B is Correct. candidate has sufficient info to determine identified leakage exceeds limits (10 gpm) of LCO 3.4.14. EDT level increasing and normal RU-1 readings indicate identified leakage.

C is Wrong. this is not unidentified leakage it is going to the EDT D is wrong. this is not a leak in to NCW, RU-6 readings are normal

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 19 of 49 11/18/08 10 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 3 K/A #

236 Importance Rating:

3.10 Given the following plant conditions:

A large break LOCA has occurred.

Due to emergency conditions a gaseous radioactive release from Containment must be performed to relieve pressure in the containment and bring the plant to a safer condition.

Who may authorize this release without a release permit?

A.

Shift Manager.

B.

Effluents Supervisor.

C.

Chemistry Supervisor.

D.

Radiation Protection Supervisor.

Answer:

A Associated KA:

L57256 Given that abnormal conditions require exceeding ODCM requirements describe whose authority is needed to exceed requirements and what reporting is necessary 100866 Active Question Bank 2004 Reference Id:

Q6695 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.43 (4) 55.43 (4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.

Cognitive Level:

Memory Question Source:

PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

LOIT lesson plan / 74RM-9EF20, GR release permits and offsite dose assessments K&A: Knowledge of the requirements for reviewing and approving release permits.

Justification:

A is Correct - Only the Shift Manager or CRS allowed to approve emergency release's to stabilize the plant during EOP performance B is Wrong -

C is Wrong -

D is Wrong -

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 20 of 49 11/18/08

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 21 of 49 11/18/08 11 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 2 Group 1 K/A #

37012A203 Importance Rating:

3.70 Given the following plant conditions:

Time 1 Channel A "LO SG-1 PRESS" bistable trips due to a transmitter failure.

The appropriate parameter has been placed in bypass Time 2 PNB-D26 de-energizes due to a ground fault The CRS directs recovery actions per the Loss of Class Instrument or Control Power AOP The RO removes channel A "LO SG-1 PRESS" bistable from bypass prior to placing the B channel parameters in bypass This results in a(n) and requires the CRS to implement the...

A.

reactor trip, 40EP-9EO02, Reactor Trip procedure.

B.

reactor trip, 40EP-9EO06, Loss Of All Feedwater procedure.

C.

MSIS actuation, 40AO-9ZZ17, Inadvertant PPS-ESFAS Actuations procedure.

D.

half leg MSIS actuation, 40AL-9RK5B, panel B05B alarm response procedure Answer:

A Associated KA:

L77088 Describe the RPS Trip Channel bypass interlock.

Reference Id:

Q10476 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Comprehension / Anal Question Source:

Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

training material Modified from Q2596 K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Incorrect channel bypassing Justification:

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 22 of 49 11/18/08 Pushing the B train Lo SG 2 pressure pushbutton will cause the B train to come out of Bypass initiating an MSIS and Rx trip A is Correct - Rx trip will be implemented due to 2/4 Lo SG-1 pressure trip, AFW can be used to feed the SGs B is Wrong - LOAF will not be needed even though MFW will be locked out and require Override of FWIV to restore C is Wrong - examinee may not realize Rx trip (A & B channels) and opt for large load reject due to MSIVs closing D is Wrong - examinee may think the A & B channels or only SG 1 will initiate a half leg trip

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 23 of 49 11/18/08 12 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 2 Group 1 K/A #

2.4.38 Importance Rating:

4.40 You are the On-shift Emergency Coordinator with the following conditions:

Unit 1 tripped 20 minutes ago from 100% power Offsite power was lost on the trip Pressurizer level is 0%

Pressurizer pressure is 950 psia and dropping RCS T-hot is 564 ºF QSPDS indicates 0º subcooling PBB-S04 has faulted and is de-energized AFA-P01 will not come up to speed HPSI pump "A" is under clearance RCS activity is 330 µCi/gm Dose Equivalent I-131 Containment pressure is 9.1 psig and increasing RVLMS indicates 0% in the outlet plenum All other equipment has functioned as required Which one of the following events would require you to change the current Emergency Action Level?

A.

CS pump A trips B.

AFN-P01 trips on an 86 lockout C.

RVLMS indicated plenum level increases to 47%

D.

RU-148, CNTMT Rad Monitor readings increase to 4.1 E +05 mrem/hr Answer:

A Associated KA:

L58622 Given an Emergency Plan condition, use the EAL tables and basis document to determine the emergency plan classification Reference Id:

Q10477 Difficulty:

2.00 Time to complete:

4 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: Table 1 of EPIP-99 Technical

Reference:

Table 1 of EPIP-99 K&A: Ability to take actions called for in the facility emergency plan, including l

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 24 of 49 11/18/08 supporting or acting as emergency coordinator if required.

Justification:

A is Correct - loss of CS pump A [1-10] will upgrade classification to a GE, 2 lost barriers and an additional potential lost barrier of cntmt. B CS pump was lost due to PBB-S04 loss B is Wrong - a loss of AFN is a LOAF but this a potential [1-8] and will not cause upgrade already have [1-6] lost in the RCS Barrier C is Wrong - RVLMS increasing will not lower classification [1-2] is or has been below 21%

additionally RCS activity is a loss of Fuel Clad [1-3]

D is Wrong - RU-148 readings are another loss of Fuel Clad no upgrade [1-4] additionally readings do not meet the potential loss of cntmt requirements [1-11]

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 25 of 49 11/18/08 13 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 1 Group 1 K/A #

34059A212 Importance Rating:

3.40 Given the following conditions:

Unit 1 is operating at 100% power SG 2 Economizer Feed Regulating Valve SGN-HV-1122 has failed open Area 2 reports that SGN-HV-1122 is mechanically seized SG 2 level is 65% NR and RISING RCS T-cold is 552ºF and LOWERING The Crew initiates a manual Reactor Trip Assuming no other Operation actions, SG 2 level will continue to increase until a(n) (a) signal is generated and the CRS should implement the (b) procedure upon completing SPTAs.

A.

(a) MSIS (b) Reactor Trip B.

(a) MSIS (b) Excessive Steam Demand C.

(a) High Level Override (b) Reactor Trip D.

(a) High Level Override (b) Excessive Steam Demand Answer:

B Associated KA:

L11200 Given conditions of an ESD analyze whether or not entry into the ESD EOP is appropriate Reference Id:

Q10484 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Reactor Trip and ESD procedures / Board 6 alarm response and 40AO-9ZZ17 inadvertant PPS-ESFAS actuations K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of feedwater regulating valves Justification:

A is Wrong - T-cold below 560 excludes Rx Trip procedure

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 26 of 49 11/18/08 B is Correct - MSIS shuts Isolation valves to stop FW flow, ESD entry conditions include rise in FW flow until stopped by MSIS C is Wrong - HLO only shuts reg valves not Isolation valves, Rx Trip is wrong D is Wrong - HLO only shuts reg valves not Isolation valves

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 27 of 49 11/18/08 14 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 2 Group 1 K/A #

2.4.45 Importance Rating:

4.30 Given the following conditions:

Unit 1 has tripped from rated power Offsite power was lost following the reactor trip DG "B" is under clearance and OOS DG "A" is supplying power to PBA-S03 AFA-P01 is feeding each SG at 300 gpm SPTAs have been completed CRS has implemented the Loss of Offsite Power/ Loss of Forced Circulation MSIS has been manually actuated The following now occurs Window 1A04A (125 1E CC M41 CHGR A/AC PNL D21 TRBL) is alarming Point ID - PKYS3 125 VDC CC PKA-M41 Bus Undv/Ground/Breaker Trip is in alarm The Reactor Operator reports that the PK "A" bus shows 0 volts The CRS should...

A.

remain in LOOP/LOFC and initiate feedwater flow with AFN-P01 by overriding and opening downcomer isolation valves B.

transition to the Loss of All Feed procedure and initiate AFW flow per Standard Appendix 40, Local Operation of AFA-P01 C.

transition to the Blackout procedure and restore power and feedwater flow by paralleling Blackout Turbine Generators to PBA-S03 D.

transition to the Functional Recovery procedure and implement the appropriate MVDC appendix to restore power and feedwater flow.

Answer:

D Associated KA:

L74204 Describe how the 125 VDC Class IE Power System supports the operation of the following systems:

• Class IE 4.16 kV Switchgear and 480 Vac Load Centers (PB & PG)

• Class IE Standby Generation System (PE)

• Auxiliary Feed System (AF)

• Safety Injection (SI)

• Class IE 120 Vac Instrumentation Power (PN)

• Steam Generators (SG)

Reference Id:

Q10485 Difficulty:

4.00

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 28 of 49 11/18/08 Time to complete:

4 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AO-9ZZ13, Loss of Class Instrument or Control Power K&A: Emergency Procedures / Plan Ability to prioritize and interpret the significance of each annunciator or alarm.

Justification:

A is Wrong - the loss of PKA-M41 causes a DG trip = no AFN-P01, dual event requires entry into FRP B is Wrong - Dual event requires entry into FRP, LOAF will not address the loss of power although manual operation of AFA would restore AFW flow C is Wrong - dual event requires entry into the FRP. although Blackout would restore power and ultimately restore flow the Blackout assumes that AFA and ADVs are available D is Correct - Loss of PKA-M41 trips the A DG and loses Control Power to AFA-P01 it to shutdown. This is now a dual event Blackout and LOAF, FRP is mandated

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 29 of 49 11/18/08 15 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 2 Group 1 K/A #

38078A2.01 Importance Rating:

2.90 Given the following conditions Unit 1 is operating at 100% power Instrument Air System (IA) is aligned for normal operation IA system pressure is at normal operating pressure Instrument Air Dryer IAN-M01D has failed and will not supply the IA system Which one of the following is correct?

A.

The nitrogen backup valve will open and maintain normal IA header pressure B.

IA dryers are normally aligned for parallel operation. IAN-M01C will maintain normal IA header pressure C.

IAN-C02 Service Breathing Air compressor can be aligned to maintain IA pressure ~ 110 psia per 40OP-9IA02, Service/Breathing Air System.

D.

The IA header pressure will decrease until the nitrogen backup valve opens.

Implement 40AO-9ZZ06, Loss of Instrument Air, to valve in another air dryer Answer:

D Associated KA:

L76601 Describe the flowpath of Service/Breathing Air, including the following:

• Air Compressor

• Air Receivers

• Air Dryers Reference Id:

Q10479 Difficulty:

2.00 Time to complete:

3 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40OP-9IA01 (Instrument Air System), 40OP-9IA02 (Service/Breathing Air), 40AO-9ZZ06 (Loss of Instrument Air)

K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunction

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 30 of 49 11/18/08 Justification:

A is Wrong - LP nitrogen will open but maintain ~ 85 psia B is Wrong - IA dryers are not normally aligned for parallel operation but it is an available option per section 4.6 of IA01 C is Wrong - Service Air and IA can not be x-tied, although in the past it was possible D is Correct - Nitrogen maintains system pressure and ZZ06 should be implemented to mitigate effects

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 31 of 49 11/18/08 16 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 2 Group 2 K/A #

37015a2.01 Importance Rating:

3.90 Given the following conditions:

Unit 1 is operating at 100% power Various B05 alarms associated with channel "D" have annunciated Channel "D" Log power indicator (SEB-JI-1D) and recorder (SEB-JI-3D) are exhibiting erratic behavior The CRS should declare the "D" train...

A.

Log Power Inoperable. Place PPS parameter HI Log Power in bypass within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per LCO 3.3.1 (RPS Instrumentation Operating).

B.

CPCs, Log Power and Linear Power Inoperable. Place PPS parameters VOPT, HI Log Power, Lo DNBR and Hi LPD in bypass within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per LCO 3.3.1 (RPS Instrumentation Operating).

C.

Log Power Inoperable. Place PPS parameter HI Log Power in bypass within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per LCO 3.3.1 (RPS Instrumentation Operating). In addition enter the actions of LCOs 3.3.10 (Post Accident Monitoring Instrumentation) and 3.3.11 (Remote Shutdown System)

D.

CPCs, Log Power and Linear Power Inoperable. Place PPS parameters VOPT, HI Log Power, Lo DNBR and Hi LPD in bypass within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per LCO 3.3.1 (RPS Instrumentation Operating). In addition enter the actions of LCOs 3.3.10 (Post Accident Monitoring Instrumentation) and 3.3.11 (Remote Shutdown System)

Answer:

B Associated KA:

L75664 Explain the operation of the Safety Channels under normal operating conditions.

Reference Id:

Q22481 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.43 (2) 55.43 (2)Facility operating limitations in the technical specifications and their bases.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Tech Specs and TS bases K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Power supply loss or erratic operation

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 32 of 49 11/18/08 Justification:

A is Wrong - Log power is the middle detector of the Linear channel. Linear power and CPCs are also affected B is Correct - As stated above Log, Linear & CPCs are affected and should be declared Inoperable. LOG power being placed in bypass is obvious but TS bases directs that with a failed Linear channel that VOPT, DNBR and LPD also be placed in bypass C & D are Wrong - Examinee should know that "D" channel does not apply to PAM or Remote Shutdown LCOs, only channels A and B are affected

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 33 of 49 11/18/08 17 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 2 Group 2 K/A #

2.1.20 Importance Rating:

4.60 Given the following conditions:

Unit 1 was manually tripped SG 1 has an estimated 155 gpm tube rupture SG 1 has been isolated per 40EP-9EO04, SGTR An event now occurs:

The crew has determined that a 1000 gpm SGTR is in progress on SG 2 The CRS should...

A.

enter 40EP-9EO09, FRP and isolate both SGs.

B.

remain in 40EP-9EO04, SGTR and fill both SGs to 45 - 60% NR C.

enter 40EP-9EO09, FRP and continue the RCS cooldown using SG 2 D.

remain in 40EP-9EO04, SGTR, restore feeding and steaming to SG 1 and isolate SG 2.

Answer:

D Associated KA:

L11218 Given that the SGTR EOP is being implemented describe the SGTR EOP mitigation strategy Reference Id:

Q22472 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

40EP-9EO04, SGTR K&A: Ability to interpret and execute procedure steps (Steam Generator)

Justification:

A is Wrong - SGTR directs that only the most affected SG be isolated B is Wrong - raising SG level to > 45% NR is directed when steaming a faulted SG to atmosphere (ESD/SGTR)

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 34 of 49 11/18/08 C is Wrong - need to isolate the most affected SG per the SGTR procedure D is Correct - SGTR has actions to unisolate the least affected SG then isolate the most affected SG

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 35 of 49 11/18/08 18 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 2 Group 2 K/A #

34041a2.02 Importance Rating:

3.90 Given the following conditions:

Unit 1 was operating at 100% power SBCV #6 failed 100% open A reactor trip and MSIS have both automatically initiated T-avg dropped to 570°F on the reactor trip T-cold dropped to 556°F before the MSIS was initiated Which one of the following is correct?

A.

SBCS "Quick Open" was blocked on the trip, direct the crew to maintain T-cold at 556°F and implement 40EP-9EO05 (ESD)

B.

SBCS "Quick Open" was blocked on the trip, direct the crew to restore T-cold to 560-570°F and implement 40EP-9EO02 (Rx Trip)

C.

SBCS "Quick Open" functioned normally on the trip, direct the crew to maintain T-cold at 556°F and implement 40EP-9EO05 (ESD)

D.

SBCS "Quick Open" functioned normally on the trip, direct the crew to restore T-cold to 560-570°F and implement 40EP-9EO02 (Rx Trip)

Answer:

A Associated KA:

L65642 Describe the function of the inputs from the following to the SBCS:

• Main Steam

• Feedwater Control System

• Reactor Regulating System

• Reactor Power Cutback System

• Instrument Air System

• Reactor Coolant System

• Condensate System Reference Id:

Q22473 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Sicklied drawings, LOIT lesson plan

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 36 of 49 11/18/08 K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the SDS; and (b) based on those predictions or mitigate the consequences of those malfunctions or operations: Steam valve stuck open Justification:

A is Correct - QO is blocked on Rx trip with T-avg < 573.5°F, OPS expectations requires that ESD be entered if T-cold goes below 560°F due to an ESD event B is Wrong - Examinee may pick any of these others based on lack of system understanding C is Wrong - QO does not function normally D is Wrong - QO does not function normally

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 37 of 49 11/18/08 19 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 3 K/A #

2.1.7 Importance Rating:

4.70 Given the following Unit 1 conditions:

The Main Turbine tripped 60 minutes ago Rx power was stabilized at 55%

Tave was stabilized at 576 ºF NOW Pzr level is on program Letdown flow is 72 gpm and lowering Rx power is slowly dropping Tave is slowly dropping CEDMCS has a withdraw demand Which one of the following is the most likely event in progress?

A.

A small RCS leak, implement 40AO-9ZZ02, Excessive RCS Leakage.

B.

A small steam leak. Trip the Reactor and implement 40EP-9EO06, Excess Steam Demand.

C.

Thot instrument RCN-TT-111X is failing low, implement 40AO-9ZZ16, RRS Malfunctions.

D.

Normal xenon response following a Large Load Reject. Direct a dilution per 40OP-9CH01.

Answer:

D Associated KA:

L569445 Given a TLI instrument failing low describe the impact this would have on various control systems that rely on this indication Reference Id:

Q10481 Difficulty:

3.00 Time to complete:

3 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AO-9ZZ16, RRS Malfunctions

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 38 of 49 11/18/08 K&A: Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Justification:

A is Wrong - RCS leakage will not cause changes in anything other than Letdown flow decreasing B is Wrong - Steam leak will cause power increase and temperature decrease C is Wrong - Thot failing low causes Letdown flow to increase but not all the other changes D is Correct - Xenon will build in after trip causing power drop, temperature drop, WD demand and Letdown decrease trying to maintain Pzr level with decreasing RCS temp

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 39 of 49 11/18/08 20 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 3 K/A #

2.1.37 Importance Rating:

4.60 A plant upset requires that you as the CRS give a "concise" reactivity brief prior to initiating a downpower to mitigate the event. Per direction found in Operations Department Practices (ODP-1) all of the following information should be included except...

A.

the expected rate of power reduction B.

which parameters are to be monitored during the power reduction C.

the expected power level that must be reached to mitigate the event D.

the power level at which the Reactor Power Cutback system will be disabled Answer:

D Associated KA:

30265 ODP-1 Reactivity Management Reference Id:

Q22470 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.43 (6) 55.43 (6) Procedures and limitations involved in initial core loading, alterations in core configuration, control rod programming, and determination of various internal and external effects on core reactivity.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: NONE Technical

Reference:

ODP-1 K&A: Conduct of Operations: Knowledge of procedures, guidelines or limitations associated with Reactivity Management Justification:

A is Wrong - required per ODP-1 B is Wrong - required per ODP-1 C is Wrong - required per ODP-1 D is Correct - the power level to remove RPCB would be covered in mitigation brief not a reactivity brief

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 40 of 49 11/18/08 21 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 3 K/A #

2.2.37 Importance Rating:

4.60 Given the following conditions:

Unit 1 is operating at rated power DG "A" is under clearance and OOS for planned maintenance A low level alarm is received on the "B" Essential Chill water surge tank Area 3 reports a leak on the HPSI pump room "B" Essential ACU, HAB-Z01 Chill Water (EC) is isolated to HAB-Z01 Which one of the following correctly reflects the current HPSI pump status?

A.

HPSI pumps A/B are both Inoperable but available B.

HPSI pumps A/B are both Inoperable and not available C.

HPSI pump A is Operable and available provided offsite power is available to PBA-S03 D.

HPSI pump B is Operable and available provided room temperature is maintained < 104 ºF Answer:

A Associated KA:

L89782 Given a set of plant conditions apply the one hour or less actions statements of T.S. 3.5 Reference Id:

Q10482 Difficulty:

5.00 Time to complete:

6 10CFR Category:

CFR 55.43 (2) 55.43 (2)Facility operating limitations in the technical specifications and their bases.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Tech Specs K&A: Ability to determine operability and/or availability of safety related equipment.

Justification:

A is Correct - Both HPSI are Inop per definition but both are also functional to use if needed B is Wrong - see above C is Wrong - Operable means emergency source of power is available D is Wrong - Operable requires attendant equipment available including room coolers or C

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 41 of 49 11/18/08

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 42 of 49 11/18/08 22 This Exam Level SRO Apears on:

SRO EXAM 2008 K/A #

2.2.23 Importance Rating:

4.60 Given the following conditions:

Unit 1 is operating at 100% power LPSI pump "A" was declared Inoperable at 0000 on 4/1/2008 due to scheduled maintenance At 0600 on 4/1/2008 area 3 reports that an oil bubbler on HPSI pump "B" has broken off and there is a large amount of oil on the floor Referring to LCO 3.5.3 which one of the following is correct?

A.

Be in Mode 3 by 1300 on 4/1/2008 per LCO 3.0.3 B.

Be in Mode 3 by 1200 on 4/1/2008 per Condition C C.

Be in Mode 3 by 1200 on 4/4/2008 per Condition C D.

Be in Mode 3 by 1200 on 4/8/2008 per Condition C Answer:

C Associated KA:

L89783 Given plant conditions and Technical Specification action statements that are greater than one hour apply the action statements that are greater than one hour for T.S. 3.5 Reference Id:

Q22482 Difficulty:

3.00 Time to complete:

4 10CFR Category:

CFR 55.43 (2) 55.43 (2)Facility operating limitations in the technical specifications and their bases.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: Tech Specs 3.5.3 Technical

Reference:

Tech Specs 3.5.3 & LCO 3.0.3 K&A: Ability to track Technical Specification limiting conditions for operations.

Justification:

A is Wrong - 3.0.3 does not apply, although not listed this LCO does have allowance for inoperable HPSI pumps as part of ECCS B is Wrong - If examinee mis-applies 3.5.3 condition B and goes directly to condition C this would appear correct C is Correct - The "AND" statement of condition B has allowance for 1 each HPSI and LPSI provided one equivalent train of ECCS flow is available no matter train designation D is Wrong - If examinee mis-applies 3.5.3 or does not recognize HPSI then condition A would appear correct

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 43 of 49 11/18/08

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 44 of 49 11/18/08 23 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 3 K/A #

2.3.4 Importance Rating:

3.70 Given the following conditions:

A General Emergency has been declared Satellite Technical Support Center (STSC) has been activated Operations Support Center (OSC) has been activated It has been determined that in order to stabilize the plant repair activities are required to be performed in a high dose area Who can authorize a "Protecting Valuable Property" exposure and what is the Dose limit?

A.

Emergency Coordinator ONLY, 10 Rem TEDE B.

Emergency Coordinator ONLY, 25 Rem TEDE C.

Emergency Coordinator or Radiation Protection Monitor, 10 Rem TEDE D.

Emergency Coordinator or Radiation Protection Monitor, 25 Rem TEDE Answer:

A Associated KA:

30226 exposure limits Reference Id:

Q10491 Difficulty:

2.00 Time to complete:

3 10CFR Category:

CFR 55.43 (4) 55.43 (4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

EPIP-99 Appendix K K&A: Knowledge of radiation exposure limits under normal or emergency conditions Justification:

A is Correct - Per EPIP-99 appendix K, only the EC is authorized to allow any exposures >

5 REM TEDE for protecting valuable equipment or life saving activities B is Wrong -

C is Wrong -

D is Wrong -

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 45 of 49 11/18/08

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 46 of 49 11/18/08 24 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 3 K/A #

2.3.14 Importance Rating:

3.80 You are the Unit 1 Control Room Supervisor with the following conditions:

Unit 1 is in Mode 4, proceeding to Mode 5 RCS pressure is 240 psia RCS temperature is 190ºF and lowering LPSI pump "A" is providing Shutdown Cooling (SDC) flow at 4100 gpm The Outage Supervisor requests that you shift SDC to CS pump "B" Which one of the following actions should you direct...

A.

that RCS pressure be lowered to within CS pump limitations B.

that RCS temperature be lowered to within CS pump limitations C.

Radiation Protection to survey the "B" train SDC system after the train swap is completed D.

entry into LCO 3.6.6, Containment Spray System, when the CS pump is aligned for SDC operations Answer:

C Associated KA:

L65102 Describe the purpose and conditions under which the Shut Down Cooling System is designed to function.

Reference Id:

Q10489 Difficulty:

3.00 Time to complete:

2 10CFR Category:

CFR 55.43 (4) 55.43 (4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.

Cognitive Level:

Comprehension / Anal Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40OP-9SI01, Shutdown Cooling Initiation - Tech Specs, LCO 3.6.6 K&A: Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Justification:

A is Wrong - seal pressure limit is 250 psia B is Wrong - seal temperature limit is 200 ºF C is Correct - rad levels are expected to increase significantly when initiating or swapping SDC trains. Limitations and Precautions

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 47 of 49 11/18/08 D is Wrong - LCO 3.6.6 applies 1-4

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 48 of 49 11/18/08 25 This Exam Level SRO Apears on:

SRO EXAM 2008 Tier 3 K/A #

2.4.8 Importance Rating:

4.50 Given the following conditions:

Unit 1 is operating at 100% power RU-6 (Nuclear Cooling Water) is in high alarm The Crew is performing actions per the Excessive RCS Leakrate, 40AO-9ZZ02 Alarm window 4A02A (RCP 1A TRBL) is alarming All available Charging Pumps are running Letdown is isolated PZR level is continuing to lower The CRS is expected to....

A.

trip the Reactor, exit 40AO-9ZZ02 and go to 40EP-9EO01, Standard Post Trip Actions.

B.

exit 40AO-9ZZ02 and initiate performance of 40AO-9ZZ04, RCP Motor Emergencies.

C.

continue 40AO-9ZZ02. If Nuclear Cooling Water is isolated for 10 minutes then trip the Reactor.

D.

trip the Reactor, trip the 1A RCP, verify reactivity conditions then continue performance of 40AO-9ZZ02 during 40EP-9EO01, SPTAs.

Answer:

A Associated KA:

L10343 Given that an ORP is being implemented describe the use of an AO or OP when the reactor trips or when performing an EOP Reference Id:

Q10478 Difficulty:

2.00 Time to complete:

2 10CFR Category:

CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level:

Memory Question Source:

New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AO-9ZZ02 (Excessive RCS Leakrate), 40DP-9AP16 (EOP Users Guide)

K&A: Knowledge of how abnormal operating procedures are used in conjunction with l EOPs.

Justification:

ES-401 Sample Written Examination Question Worksheet Form ES 401 - 5 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 49 of 49 11/18/08 A is Correct - reactor trip criteria is met (ZZ02)and the next directs go to SPTAs which means exit this AOP. LOCA has steps that address a high pressure seal cooler leak B is Wrong - the RCP trbl alarm requires performance of RCP Motor Emergencies, but not required to exit the current AOP also we still need to trip the reactor now C is Wrong - reactor needs to be tripped now not in 10 minutes if seal cooler is isolated D is Wrong - this would be correct for some AOPs that dosen't say "go to". verify reactivity then perform AOP and EOP concurrently Cognitive Level Summary Number of questions linked:

25 Percentage Memory 9

9 Comprehension 0

0 Analysis 0

0 Question Source Summary Number of questions linked to source:

25 Percentage New New 21 21 Modified INPO Bank Modified 0

PV Bank Modified 3

Total Modified 3

3 Bank INPO Bank Not Modified 0

PV Bank Not Modified 1

PV NRC Exam Question Not Modified 0

Total BANK 1

1

SRO ANSWER KEY

1. C

2. B

3. D

4. B

5. B B in lieu of A

6. A

7. A

8. B

9. B

10. A

11. A

12. A

13. B

14. D

15. D

16. B

17. D

18. A

19. D

20. D

21. A or C

22. C

23. A

24. C

25. A