Text

Initial Exam 2010-301 Draft RO Written Exam
	ML102520114
Person / Time
Site:	Browns Ferry
Issue date:	08/16/2010
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-259/10-301, 50-260/10-301, 50-296/10-301, ES-401-5 50-259/10-301, 50-260/10-301, 50-296/10-301
	Download: ML102520114 (492)
	v • d • e

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 ------

Tier # 1 G2.1.7 (10CFR 55.41.5)

Group # 1 ------

Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and K/A # 295001G2.1.7 instrument interpretation.

Importance Rating 4.4 ------

Proposed Question: #1 Unit 1 is recovering from a trip of Recirc Pump 1A AND while executing the actions of 1-AOI 1A, Recirc Pump Trip/Core Flow Decrease OPRMs Operable, the Unit Operator (UO) has just reported that the RECIRC PUMP 1A DISCHARGE VALVE, 1-FCV-68-3, has been MANUALLY opened.

The Balance of Plant (BOP) Operator then reports that Recirc Pump 1B has tripped AND the Unit has entered Region I of the Power to Flow Map.

Which ONE of the following completes the statement?

For these conditions, the required action in accordance with 1-AOI-68-1A is to ________.

A. insert a manual Reactor Scram.

B. commence a normal Reactor shutdown / cooldown.

C. close the Discharge Valve on the outlet of Recirc Pump 1B.

D. insert Control Rods on the Shove Sheet to exit Region I of the Power to Flow Map.

Proposed Answer: A Explanation A CORRECT: AOI-68-1A is entered; BOTH Recirc Pumps are now tripped.

(Optional): From this condition an immediate Rx Scram is directed iaw 1-AOI-68-1A.

B INCORRECT: Although this is a required action contained in 1-AOI-68-1A, it is an IF/THEN, which is dependent upon the IF of a single Recirc pump trip due to dual seal failure.

C INCORRECT: Although this is a required action contained in 1-AOI-68-1A, it is an IF/THEN, which is dependent upon the IF of a single Recirc pump trip.

D INCORRECT: Although this is a required action contained in 1-AOI-68-1A, in this case it would be overridden by the dual Recirc pump trip actions.

Region I is an Immediate Exit Region, but in this case you would NOT wait to manually drive Control Rods on the Shove Sheet (standard terminology).

RO Level Justification: Tests candidates ability to evaluate plant performance, i.e., knowing the status of Recirc Pump 1A and where they are in the recovery process and how the tripping of Recirc Pump 1B impacts this recovery. The candidate must then make an operational judgment based upon previous data.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 1-AOI-68-1A Rev 3 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: ___________________ (As available)

Question Source: Bank # X 0801 #1 Modified Bank # (Note changes or attach parent)

New Question History: HLT 0801 Last NRC Exam (07 / 2009)

(Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295003 Partial or Complete Loss of AC / 6 ------

Tier # 1 G2.1.27 (10CFR 55.41.7)

Group # 1 ------

Knowledge of system purpose and/or function.

K/A # 295003G2.1.27 Importance Rating 3.9 ------

Proposed Question: #2 Which ONE of the following completes the statement?

480 Volt Load Shed Logic receives a Common Accident Signal generated from __(1)__ AND is divisionalized on __(2)__ in regards to which board loads will actually be shed.

A. (1) RHR System instrumentation (2) Unit 1 B. (1) Core Spray System instrumentation (2) Unit 1 C. (1) RHR System instrumentation (2) Unit 3 D. (1) Core Spray System instrumentation (2) Unit 3 Proposed Answer: D Explanation A INCORRECT: See below for Part 1 on RHR vs. Core Spray. RHR and Core (Optional): Spray have identical initiation signals, which lends to plausibility. Unit 1 and 2 share 480 Volt Load Shed Logic and are dependent upon each other to function. This fact, in and of itself, lends plausibility to the logic being divisionalized on a priority basis.

B INCORRECT: First part correct (see below). Second part incorrect but plausible based on the premise discussed above.

C INCORRECT: First part incorrect for reasons discussed in A above.

Second part is correct.

D CORRECT: (See attached excerpts) Common Accident Signal Logic is generated from Core Spray Logic, as detailed in Lesson Plan OPL171.072.

Only Unit 3 is divisionalized RO Level Justification: Tests whether the candidate has knowledge of 480 Volt Load Shed Logic as it applies to a Loss of Offsite Power concurrent with a LOCA; both of which are required for it to function. This question also incorporates unit differences in the fact that Units 1 and 2 share Load Shed Logic and Unit 3 does not. Additionally, the question plays on the divisional aspects of load shed logic.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPL171.072, Rev. 11 (Attach if not previously provided) 3-AOI-57-1D, Rev. 6 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.2/ 3 ___________ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295004 Partial or Total Loss of DC Pwr / 6 ------

Tier # 1 AA1.03 (10CFR 55.41.7)

Group # 1 ------

Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: K/A # 295004AA1.03

A.C. electrical distribution Importance Rating 3.4 ------

Proposed Question: #3 Unit 2 was operating at 100% Reactor Power.

A ground AND subsequent fire in Shutdown Board 250V DC Distribution Panel SB-B resulted in de-energization of the SB-B panel AND trip of 4kV Shutdown Board B Normal Feeder Breaker.

Which ONE of the following completes the statements?

480V Shutdown Board 2A is __(1)__.

4kV Shutdown Board B __(2)__ automatically transfer to its alternate source.

A. (1) energized (2) will B. (1) de-energized (2) will C. (1) energized (2) will NOT D. (1) de-energized (2) will NOT Proposed Answer: D Explanation A INCORRECT: Part 1 incorrect - 480v Shutdown Board 2A is de-energized (Optional): with the loss of 4kV Shutdown Board B. The transfer to alternate power is manual. Plausible in that Unit 1 and 3 480v Shutdown Board A normal power supply is from 4kV Shutdown Board A. Part 2 incorrect - Each Shutdown Battery system supplies its respective 4KV Shutdown Board and 480V Shutdown Board. All control power transfers are manual. Plausible in that if control power transfer is automatic as board power supply is or control power was not from SB-B DC Distribution Panel, this would be the correct answer.

B INCORRECT: Part 1 correct - See explanation D. Part 2 incorrect - See explanation A.

C INCORRECT: Part 1 incorrect - See explanation A. Part 2 correct - See explanation D.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D CORRECT: Part 1 correct - 480v Shutdown Board 2A is deenergized with the loss of 4kV Shutdown Board B. It is the normal feeder to the 480v S/D Bd 2A and the transfer to alternate power is manual. Part 2 correct - Each Shutdown Battery system supplies its respective 4KV Shutdown Board and 480V Shutdown Board. All control power transfers are manual. With the loss of control power, normal automatic transfer to alternate power supply will not occur.

RO Level Justification: To successfully answer this question, candidate must recognize the impact of partial loss of DC (SB-B Distribution Panel) will have on control power to 4 kV Shutdown Board B and the impact of loss of 4kV Shutdown Board B will have on 480v Shutdown Board 2A. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.036 Rev 12 (Attach if not previously provided)

OPL171.037 Rev 12 0-OI-57B Rev 184 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.037 V.B.1__ (As available)

OPL171.036 V.B.6/8_

Question Source: Bank #

Modified Bank # OPL171.037 #51 (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Excerpt from OPL171.037 Rev 12

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

1. OPL171.037 51 Unit 2 was operating at 100% power (ALL ELECTRICAL SYSTEMS IN NORMAL ALIGNMENT) when a ground and subsequent fire in 250v DC distribution panel SB-B resulted in deenergization of the SB-B panel and trip of 4kv Shutdown board B normal feeder breaker.

ASSUME NO OPERATOR ACTIONS HAVE BEEN TAKEN Which ONE of the following is correct?

A. 4kv Shutdown Board B is energized from D/G B.

B. 4kv Shutdown board B is energized from its alternate feeder.

C. 480v RMOV board 2D is energized from its alternate feeder.

D. 480v Shutdown Board 2A is energized from its alternate feeder.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295005 Main Turbine Generator Trip / 3 ------

Tier # 1 AA2.08 (10CFR 55.41.10)

Group # 1 ------

Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP: K/A # 295005AA2.08

Electrical distribution status Importance Rating 3.2 ------

Proposed Question: #4 Unit 2 is operating at 100% Reactor Power when the following alarm AND indications occur:

EHC HYD FLUID HDR PRESS LOW, (2-9-7B, Window 1)

EHC Header Pressure is lowering

STANDBY EHC Pump is isolated and Red Tagged Which ONE of the following completes the statements?

A Main Turbine TRIP occurs at EHC Control Oil Pressure of __(1)__.

Following Main Turbine Generator TRIP, Shutdown Bus 2 board loads will be supplied by

__(2)__.

A. (1) 1300 psig.

(2) 161 kV sources.

B. (1) 1300 psig.

(2) 500 kV sources.

C. (1) 1100 psig.

(2) 161 kV sources.

D. (1) 1100 psig.

(2) 500 kV sources.

Proposed Answer: D Explanation A INCORRECT: First part incorrect - Plausible in that this is the EHC HYD (Optional): FLUID HDR PRESS LOW alarm set point. Second part incorrect -

Plausible in that Shutdown Buses have the capability of being powered from the 161 kV sources (via the Start Buses),

B INCORRECT: First part is incorrect as detailed in A above. Second part correct as detailed in D below.

C INCORRECT: First part is correct as detailed in D below. Second part incorrect as detailed in A above.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D CORRECT: First part correct - EHC Header Pressure of 1100 psig results in a Main Turbine Trip. Second part is correct - Although the Shutdown Buses have the capability of being powered from the 161 kV sources (via the Start Buses), there is nothing in the stem to indicate that 500 kV is locked out/unavailable. Therefore, in this particular case, Shutdown Buses will be powered from 500 kV backfeed.

RO Level Justification: Tests the candidates ability to determine electrical distribution status following a Main Turbine Generator Trip. Additionally, tests the candidates knowledge of Main Turbine Trip on low EHC Pressure. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 2-ARP-9-7B, Rev. 22 (Attach if not previously provided)

OPL171.010, Rev. 12 OPL171.036, Rev. 12 Proposed references to be provided to applicants during examination: NONE Learning Objective: _OPL171.134, V.B.9_____ (As available)

_OPL171.010, V.B.12 __

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295006 SCRAM / 1 ------

Tier # 1 AK3.03 (10CFR 55.41.5)

Group # 1 ------

Knowledge of the reasons for the following responses as they apply to SCRAM: K/A # 295006AK3.03

Reactor pressure response Importance Rating 3.8 ------

Proposed Question: #5 Unit 3 is operating at 100% power conditions with EHC in the PREFERRED mode of operation.

The reactor scrams on low water level with the following timeline:

The Scram report notes Reactor Pressure at 980 psig and lowering slowly.

One minute after the scram, the operator reports Reactor Pressure has turned at a low of 955 psig and is now rising.

Two minutes after the scram, the operator reports Reactor Pressure at 980 psig and rising at approximately 2 psi/sec.

Which ONE of the following completes the statement?

EHC is in __(1)__ Pressure Control AND the Main Turbine Bypass Valves __(2)__.

A. (1) Header (2) have failed to operate at their setpoint.

B. (1) Reactor (2) have failed to operate at their setpoint.

C. (1) Header (2) will open once they reach their setpoint.

D. (1) Reactor (2) will open once they reach their setpoint.

Proposed Answer: B Explanation A INCORRECT: first part incorrect - second part correct as detailed in B (Optional): below.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet B CORRECT: (See attached excerpts) While either mode of operation is permissible, BFN operates in REACTOR Pressure control to eliminate single failure vulnerabilities. But, if header pressure drops below 700 psig, EHC will auto swap to HEADER Pressure control. Stem conditions do not warrant an auto-swap. Thus, EHC remains in REACTOR Pressure control with the setpoint at 955 psig (approximate by procedure, but where we set it exactly). Normally, at 100% power, there is a delta between this setpoint and actual reactor pressure (1036 psig). But, following a scram, setpoint and actual reactor pressure converge to within a couple of psig; with Bypass Valves cycling to control. With Pressure rising past 980 psig two minutes after the scram, the Bypass Valves must have failed.

C INCORRECT: first part incorrect - second part incorrect as detailed in B above.

D INCORRECT: first part correct - second part incorrect as detailed in B above.

RO Level Justification: Tests the candidates knowledge of EHCs Reactor Pressure Control response following a Reactor Scram and the reason for the specific pressure response driven by the stem of the question. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.228, Rev. 4 (Attach if not previously provided) 3-OI-47, Rev. 89 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.1.b / 9.a________ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295016 Control Room Abandonment / 7 ------

Tier # 1 AA1.08 (10CFR 55.41.7)

Group # 1 ------

Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT: K/A # 295016AA1.08

Reactor pressure Importance Rating 4.0 ------

Proposed Question: #6 Due to toxic gas intrusion, the Unit 1 Control Room is being abandoned in accordance with 1-AOI-100-2, Control Room Abandonment. ALL IMMEDIATE Operator Actions have just been completed.

Which ONE of the following completes the statements?

UNTIL control is established at the Backup Control Panel, Reactor Pressure will be controlled by the __(1)__.

During depressurization / cooldown efforts at the Backup Control Panel, with Reactor Pressure at 58 psig the Operator will __(2)__.

A. (1) SRVs in Safety Mode.

(2) monitor RCIC operation while injecting.

B. (1) Turbine Bypass Valves.

(2) monitor RCIC operation while injecting.

C. (1) SRVs in Safety Mode.

(2) verify that RCIC has automatically isolated.

D. (1) Turbine Bypass Valves.

(2) verify that RCIC has automatically isolated.

Proposed Answer: B Explanation A INCORRECT: (See attached excerpts) Part 1 of A and C distractors (Optional): plays on a misconception. There are many Immediate Actions in AOI-100-

2. Occasionally, in the heat of the moment during execution of Abandonment actions (JPMs and Scenarios), candidates will close the MSIVs before leaving the Control Room because they remember that they do get closed; but, in reality, it is not until they are closed from the Backup Control Panel. Part 2 is correct in that RCIC is not shut down until 50 psig.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet B CORRECT: (See attached excerpts) Nothing in AOI-100-2 actions disables Turbine Bypass Valves -i.e., like putting EHC Pumps in Pull-to-Lock. Thus, until MSIVs are closed, Turbine Bypass Valves will control pressure. Once the Subsequent Actions are conducted on location at the Backup Control Panel, the MSIVs get closed, transitioning pressure control to a subset of the total available SRVs. RCIC would have normally isolated by now (at 60 psig - Units 1 &3); but, this isolation is defeated upon transferring control to the Backup Control Panel. Because RCIC is below its full-flow design spectrum of 150 - 1120 psig (Rx Pressure), system operation can be erratic and should be monitored closely.

C INCORRECT: Part 1 is incorrect for the same reason detailed in A above.

Part 2 is incorrect because the normal RCIC isolation at 60 psig is defeated upon transferring control to the Backup Control Panel.

D INCORRECT: Part 1 is correct. Part 2 is incorrect for the same reason detailed in C above.

RO Level Justification: Tests the candidates knowledge of Reactor Pressure Control as it relates to Control Room Abandonment. Along with this, Immediate Operator Actions, system interrelationships, and intricacies are also tested as they relate to the Control Room Abandonment procedure. This question is rated as C/A due to the requirement to assemble, sort, and integrate two distinct parts of the question to predict an outcome. This requires mentally using specific knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 1-AOI-100-2, Rev. 17 (Attach if not previously provided) 1-OI-71, Rev. 9 SSD 1P-071-0001A-00-02, Rev. 2 OPL171.040, Rev. 23 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.1 / 4 / 9 ________ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Excerpt from Setpoint and Scaling Document 1P-071-0001A-00-02 (Rev. 2)

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295018 Partial or Total Loss of CCW / 8 ------

Tier # 1 AK3.07 (10CFR 55.41.5)

Group # 1 ------

Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING K/A # 295018AK3.07 WATER:

Cross-connecting with backup systems Importance Rating 3.1 ------

Proposed Question: #7 Unit 3 is operating at 100% Reactor Power. A grid disturbance results in Loss of Offsite Power; BUT, power is quickly restored. The following conditions currently exist:

Raw Cooling Water (RCW) can NOT be restored

ONLY Reactor Building Closed Cooling Water (RBCCW) Pump 3A could be started Which ONE of the following identifies the reason Emergency Equipment Cooling Water (EECW) is cross-connected to RBCCW?

To provide cooling to _____.

A. RWCU Non-Regenerative Heat Exchanger to avoid resin damage.

B. Drywell Coolers to ensure Drywell Temperature limits NOT exceeded.

C. Reactor Recirculation Pump Sample Cooler to protect chemistry sample probes.

D. Spent Fuel Pool Cooling Heat Exchanger to ensure adequate decay heat removal.

Proposed Answer: B Explanation A INCORRECT: 1-FCV-70-48 closes automatically on RBCCW Pump (Optional): discharge header pressure at or below 57 psig. RWCU non-regenerative heat exchangers are on non-essential loop which is isolated with 1-FCV 48 closing.

B CORRECT: RBCCW SECTIONALIZING VLV, 1-FCV-70-48, closes automatically on RBCCW Pump discharge header pressure at or below 57 psig. Drywell Atmospheric Coolers are essential loads and remain cooled by RBCCW after 1-FCV-70-48, closes. Since RBCCW flow can only be restored to 1 Pump, 1-FCV-70-48 is not re-opened.

C INCORRECT: 1-FCV-70-48 closes automatically on RBCCW Pump discharge header pressure at or below 57 psig. Recirc Pump sample cooler is a non-essential load.

D INCORRECT: 1-FCV-70-48 closes automatically on RBCCW Pump discharge header pressure at or below 57 psig. Fuel Pool Cooling heat exchangers are on non-essential loop which is isolated with 1-FCV-70-48 closing.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: To correctly answer this question, the candidates must demonstrate knowledge of the reason for cross-connecting EECW to RBCCW with plant conditions such that there is a complete loss of RCW and a partial loss of RBCCW. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome.

This requires mentally using specific knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.016 Rev 17 (Attach if not previously provided)

OPL171.047 Rev 12 0-AOI-24 Rev. 3 3-AOI-70-1 Rev. 16 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.047_V.B.3/6_ (As available)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam RBS 08 #7 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.016 Revision 1716 Page 3 of 8 (1) Drywell accesses (not shown)

(2) Drywell penetrations (not shown)

(3) Pressure suppression chamber and pool (4) Vent pipes, header and downcomer (5) Torus - drywell vacuum breakers (6) Primary auxiliary systems TP-13 (a) Primary containment vent, purge and inerting system.

(b) Drywell air cooling system

1. Drywell coolers are designed to maintain drywell air Obj. V.B.10.b &

temperature between 135°F and 150°F. V.B.10.e Obj. V.B.19.b

a. Ten (10) cooling units are arranged in two (2)

TP-27 banks of five (5) units .

b. Units use RBCCW as cooling medium off the essential loop.

c. Powered from: Obj. V.B.18.a Units 1, 2, & 3 use a similar lineup. (# except U-1, B-2 is on 480V RMOV BD 1B)

A-1, A-2 A 480V S/D Bd DCN: 51090 B-1, B-2 # B 480V S/D Bd See 1/2-OI-70 A-3, A-4 A 480V RMOV Bd Illustration 2 B-3, B-4 B 480V RMOV Bd Table 1 A-5, B-5 C 480V RMOV Bd

d. Drywell blowers can be started using the control Obj. V.B.12 &

switch on panel 9-25. Any operating drywell V.B.19.b cooler will trip following a load shed signal (Unit 1 Obj. V.C.8 &

or 2 accident signal and any Unit 1/2 diesel V.C.10.b generator tied to its respective 4KV shutdown See 1 & 2-OI-70 board). Ill 2, table 1 (1) The load shed trip signal will clear after a 40 second time delay and all previously operating drywell coolers on the non-accident unit will automatically start provided their respective control switch is still in the normal-after-start position.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet PROCEDURAL EXCERPTS FROM 3-AOI-70-1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295019 Partial or Total Loss of Inst. Air / 8 ------

Tier # 1 AA2.02 (10CFR 55.41.10)

Group # 1 ------

Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: K/A # 295109AA2.02 Status of safety-related instrument air system loads (see AK2.1 -

AK2.19) Importance Rating 3.6 ------

Proposed Question: #8 Given the following plant conditions:

Unit 2 was at 100% Reactor Power when a transient occurred which resulted in a Reactor Scram

After stabilizing the unit, the scram signal is RESET

ALL eight (8) Scram Solenoid Group lights are ON

Approximately ten minutes later, the following conditions are present:

- RCW DISCH HDR PRESS LOW, (2-9-20A, Window 34), in alarm

- CRD ACCUM CHG WTR HDR PRESS HIGH, (2-9-5A, Window 10), in alarm

- Outboard MSIVs are CLOSED

- Inboard MSIVs are OPEN

- Scram Discharge Volume (SDV) Vent AND Drain Valves are CLOSED

- Scram Inlet AND Outlet Valves are OPEN Which ONE of the following describes the cause for the event?

A. Loss of Control Air B. Loss of Both RPS Buses C. Loss of Drywell Control Air D. Loss of 9-9 Cabinet 5, Unit Non-Preferred Proposed Answer: A Explanation A CORRECT: On loss of control pressure, all TCVs except for one TCV on (Optional): each of the RBCCW heat exchangers fail open, resulting in low RCW pressure. 85-11A/B fail closed resulting in high charging pressure.

Outboard MSIVs drift closed, Inboard MSIV are unaffected due to drywell control air. High steam line flow will not occur due to the unit scram on low scram pilot air pressure before MSIVs drift closed. SCRAM can be reset.

SCRAM INLET and OUTLET VALVEs, 2-FCV-85-39A(B) fail OPEN. CRD SCRAM DISCH VOL VENT and DRAIN VLVs fail CLOSED on loss of air.

B INCORRECT: Loss of RPS would not result in RCW pressure low alarm.

This is plausible because the scram would occur as well as scram valves open and SDV vents and drains closed, however these indications would NOT be appropriate AFTER the scram was reset. In fact, the scram could NOT be reset without RPS available.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet C INCORRECT: This is plausible because a loss of Drywell Control Air would cause MSIVs to close, however the INBOARD valves would close.

D INCORRECT: This is plausible because loss of 9-9 Cabinet 5, Unit Non-Preferred affects several of the indications given. See attached excerpts from 2-AOI-57-4. However, outboard MSIVs would not close and SDV vents and drains would not fail to re-open.

RO Level Justification: This question satisfies the K/A statement by requiring the candidate to use specific plant conditions to determine the effect of a loss of Control Air on safety related loads. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 2-AOI-32-2 Rev 32 (Attach if not previously provided)

OPL171.054 Rev 14 Proposed references to be provided to applicants during examination: NONE Learning Objective: _OPL171.054 V.B.9_ _ (As available)

Question Source: Bank # 0610 #47 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam BFN 0610 RO (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.054 Revision 14

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295021 Loss of Shutdown Cooling / 4 ------

Tier # 1 AK2.01 (10CFR 55.41.7)

Group # 1 ------

Knowledge of the interrelations between LOSS OF SHUTDOWN COOLING and the following: K/A # 295021AK2.01

Reactor water temperature Importance Rating 3.6 ------

Proposed Question: #9 Unit 3 is in Mode 4 with the following conditions:

Reactor Level band is (+) 70 to (+) 80 inches to support testing

ALL Reactor Recirc AND RWCU Pumps are isolated and tagged

RHR Loop I in Shutdown Cooling experiences an inadvertent Group 2 Isolation AND can NOT be restored In accordance with 3-AOI-74-1, Loss of Shutdown Cooling, which ONE of the following completes the statements?

Accurate Reactor Water Temperature __(1)__ available.

Reactor Coolant Stratification is indicated by __(2)__ .

A. (1) is (2) Feedwater Sparger temperature GREATER THAN OR EQUAL TO 200°F on any Vessel Feedwater Nozzle indication.

B. (1) is NOT (2) Feedwater Sparger temperature GREATER THAN OR EQUAL TO 200°F on any Vessel Feedwater Nozzle indication.

C. (1) is (2) Reactor pressure GREATER THAN 0 psig with any Reactor Coolant temperature indication GREATER THAN 212°F.

D. (1) is NOT (2) Reactor pressure GREATER THAN 0 psig with any Reactor Coolant temperature indication GREATER THAN 212°F.

Proposed Answer: B Explanation A INCORRECT: Part 1 incorrect - Plausible in that Reactor Level is high (Optional): enough to establish natural circulation. Candidate may believe natural circulation is adequate to provide accurate level indication. Part 2 correct -

See explanation B.

B CORRECT: Part 1 correct - In accordance with Loss of Shutdown Cooling, 3-AOI-74-1, accurate coolant temperatures will not be available if forced circulation is lost. Part 2 correct - Reactor Coolant Stratification is indicated by Feedwater Sparger temperature GREATER THAN OR EQUAL TO 200°F on any Vessel Feedwater Nozzle indication.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet C INCORRECT: Part 1 incorrect - See explanation A. Part 2 incorrect -

Plausible in that in accordance with Loss of Shutdown Cooling, 3-AOI 1, with the Reactor in Cold Shutdown Condition (Mode 4 or Mode 5) coolant stratification may be indicated by Reactor pressure above 0 psig with any reactor coolant temperature indication reading at or below 212 F D INCORRECT: Part 1 and 2 incorrect as explained above.

RO Level Justification: To successfully answer the question, the candidate must demonstrate knowledge of the interrelationship between loss of shutdown cooling and Reactor Water Temp.

This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.074 Rev 8 (Attach if not previously provided) 3-AOI-74-1 Rev 17 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.074 V.B.6 ___ (As available)

Question Source: Bank #

Modified Bank # 0707 Audit #49 (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet 0707 AUDIT

49 295021 SDC LOSS 25 The following conditions exist on Unit 3:

- Unit in Mode 5 with Shutdown Cooling aligned to RHR Loop I.

- RPV Temperature band of 80°F to 100°F.

- RPV level band of +50 to +70 inches to support testing.

- Day 2 of a scheduled 29 day outage.

- RHR Loop II is tagged.

- BOTH Reactor Recirc Pumps secured.

- Reactor Water Cleanup operating.

The following annunciators are received 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after taking the shift:

- RHR SYS I PUMP A TRIPPED, 3-XA-55-3D window 13.

- RHR SD CLG FLOW LOW, 3-XA-55-3D window 11.

Based on the above indications, which ONE of the below indications would represent Reactor Coolant Stratification _(1)_ and how could this be mitigated _(2)_?

A. (1) Differential temperature of > 40°F between Vessel Flange Drain Line and Vessel Feedwater Nozzle indications.

(2) Maximize Reactor Water Cleanup operation.

B. (1) Reactor pressure > 0 psig with any Reactor Coolant temperature indication >

212°F.

(2) Raise RPV water level.

C. (1) Feedwater Sparger temperature > 200°F on any Vessel Feedwater Nozzle indication.

(2) Raise RPV water level.

D. (1) Differential temperature of > 40°F between Vessel Bottom Head and Vessel Head Flange indications.

(2) Maximize Reactor Water Cleanup operation.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295023 Refueling Acc / 8 ------

Tier # 1 AA1.03 (10CFR 55.41.7)

Group # 1 ------

Ability to operate and/or monitor the following as they apply to REFUELING ACCIDENTS: K/A # 295023AA1.03

Fuel handling equipment Importance Rating 3.3 Proposed Question: # 10 Unit 1 is in a Refueling Outage. The Refueling Supervisor reports that an IRRADIATED fuel assembly has been seated in the WRONG location in the core. The grapple remains engaged on the bundle.

The following conditions are then noted:

Rising count rates on SRMs

SRM Period lights illuminated

Rising dose rates on the Refuel Floor Which ONE of the following describes an IMMEDIATE Operator action to be taken?

A. Verify Secondary Containment is intact.

B. If any CRD Pump is in service stop the CRD Pump C. If unexpected criticality is observed following control rod withdrawal, manually SCRAM the reactor.

D. Traverse the refueling bridge AND fuel assembly away from the reactor core, preferably to the area of the cattle chute.

Proposed Answer: D Explanation A INCORRECT: This is a required subsequent action of 1-AOI-79-1, Fuel (Optional): Damage During Refueling.

B INCORRECT: This is plausible because it is a required subsequent action of 1-AOI-79-2, not immediate action.

C INCORRECT: This is an immediate action per 2-AOI-79-2, however, only appropriate to perform if ALL Control Rods cannot manually be inserted. NO indication given to suspect otherwise, therefore this action would be inappropriate to take.

D CORRECT: In order to answer this question correctly the candidate must determine the appropriate condition and Immediate Action required by 1-AOI-79-2.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: This question satisfies the KIA statement by requiring the candidate to analyze specific plant conditions to determine appropriate actions to take with fuel handling equipment in response to inadvertent criticality. This question is rated as CIA due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 1-AOI-79-2 Rev. 0 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.060 V.B.3____ (As available)

Question Source: Bank #

Modified Bank # BFN 0610 #49 (Note changes or attach parent)

New Question History: Last NRC Exam BFN 2008 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295024 High Drywell Pressure / 5 ------

Tier # 1 EK1.01 (10CFR 55.41.9)

Group # 1 ------

Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE: K/A # 295024EK1.01

Drywell integrity: Plant-Specific Importance Rating 4.1 ------

Proposed Question: # 11 Which ONE of the following completes the statement?

The MAXIMUM Containment Pressure that Primary Containment Vent Valves can be opened AND closed is______.

A. 50 psig.

B. 55 psig.

C. 62 psig.

D. 65 psig.

Proposed Answer: B Explanation A INCORRECT: Plausibility based on recognizable value - Calculated (Optional): maximum pressure after blowdown (no pre-purge) Drywell is 49.6 psig (PUR 50.6 psig)

B CORRECT: Primary Containment Pressure Limit is defined to be the lesser of either: pressure capability of the containment, (~100 psig) or maximum containment pressure at which vent valves can be opened and closed to reject all decay heat from primary containment (55 psig), or maximum primary containment pressure at which MSRVs can be opened and will remain open (65 psig), or maximum containment pressure at which vent valves can be opened and closed to vent the RPV.

C INCORRECT: Plausibility based on recognizable value - The Drywell is ASME rated 62 psig, 110% of design pressure of 56 psig.

D INCORRECT: Plausibility based on recognizable value maximum primary containment pressure at which MSRVs can be opened and will remain open (65 psig)

RO Level Justification: To successfully answer this question, candidate must have knowledge of the effect of High Drywell Pressure on Drywell Integrity.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPL171.016 R. 17 / OPL171.203 R. 7 (Attach if not previously provided)

EOI Program Manual 0-V-D Rev 0 Proposed references to be provided to applicants during examination: NONE Learning Objective: _OPL171.016 V.B.2 __ (As available)

Question Source: Bank #

Modified Bank # Bruns 08 #50 (Note changes or attach parent)

New Question History: Last NRC Exam Brunswick 2008 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.203 Revision 7 Page 3 of 6

a. If primary containment pressure cannot be maintained below Pressure Suppression Pressure, emergency depressurization of the RPV is required to terminate, or reduce as much as possible, any continued primary containment pressure increase. The operator continues at Step PC/P-11.

2. Step PC/P-11

a. This signal step informs the operator that Procedure Use, actions to control RPV pressure must change in strategy immediately change because of present plant conditions.

b. When emergency RPV depressurization is required, the operator shall transfer RPV pressure control actions to C2, Emergency RPV Depressurization.

3. Step PC/P-12

a. Calculations have determined that primary containment integrity can be assured, and core damage (that might be caused by inability to vent the RPV to permit injection into the RPV) is prevented when suppression chamber pressure is maintained below 55 psig, Primary Containment Pressure Limit.

b. Primary Containment Pressure Limit is defined to be the lesser of either:

(1) pressure capability of the containment, Around 100#

or (2) maximum containment pressure at 55 #

which vent valves can be opened and Obj V.B.8/ V.C.8 closed to reject all decay heat from primary containment, or (3) maximum primary containment 65#

pressure at which MSRVs can be opened and will remain open, or

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.016 Revision 17

c. Design Specifications Obj. V.B.2 Obj. V.C.2 (1) Drywell internal design pressure

+56 PSIG(ASME rated 62 psig, 110% of design)

-2 PSIG B. Hardened Wetwell Vent System During emergency operation, to vent the Suppression Chamber with Suppression Chamber Pressure above 55 psig it is necessary to utilize the hardened wetwell vent system in accordance with the EOI's. This system will provide assurance of pressure relief through a path with scrubbing of fission products and an exhaust line to the stack.

e. Pressure in the drywell reaches a peak of 49.6 psig approximately 10 seconds after the accident, (Point B - Figure 8) after which the rate Point B - TP-8 of blowdown is decreasing and steam (encircled) condenses faster than the reactor is blowing down.

Excerpt from EOI Program Manual 0-V-D The maximum containment pressure that primary containment vent valves can be opened and closed is <A.61>.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Brunswick 2008 #50

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295025 High Reactor Pressure / 3 ------

Tier # 1 EK3.01 (10CFR 55.41.5)

Group # 1 ------

Knowledge of the reasons for the following responses as they apply to HIGH REACTOR PRESSURE: K/A # 295025EK3.01

Safety/relief valve opening Importance Rating 4.2 ------

Proposed Question: # 12 Which ONE of the following completes the statements?

The Limiting Condition for Operation (LCO) statement for Unit 1 Safety Relief Valves (SRVs),

LCO 3.4.3, requires operability of the safety function for __(1)__ SRVs in Modes 1, 2, and 3.

This ensures that the ASME Code Limit of __(2)__ is NOT exceeded following the Design Basis Event of simultaneous closure of ALL Main Steam Isolation Valves (MSIVs) at 100% Reactor Power.

A. (1) 12 (2) 1250 psig B. (1) 12 (2) 1375 psig C. (1) 13 (2) 1375 psig D. (1) 13 (2) 1250 psig Proposed Answer: B Explanation A INCORRECT: The first part is correct - See B below. Second part is (Optional): incorrect in that 1250 psig is Vessel Design Pressure versus the ASME Code Limit of 110% of Vessel Design Pressure, or 1375 psig.

B CORRECT: (See attached excerpts) Tech Spec LCO 3.4.3 requires only the safety function of 12 SRVs to be operable. The Bases Section on Applicable Safety Analyses discusses the reason why in relation to the ASME Code Limit.

C INCORRECT: The first part is incorrect in that the LCO does NOT require operability of ALL 13 SRVs, ONLY 12 SRVs. 13 is plausible in that most safety systems are required, as a whole, to be operable. The second part is correct.

D INCORRECT: Both parts are incorrect - See C for first part and A for second part.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet RO Level Justification: Tests the candidates knowledge of Technical Specifications and Bases for SRV operability. Embedded in the Tech Spec Bases is the reason for SRVs opening in relative to transient analyses for the BFN Facility.

Technical Reference(s): Unit 1 Tech Spec 3.4.3, Amendment 234 (Attach if not previously provided)

Unit 1 Tech Spec 3.4.3 Bases, Rev. 0 OPL171.009, Rev. 11 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.2 / 14.e ________ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295026 Suppression Pool High Water Temp. / 5 ------

Tier # 1 EA2.01 (10CFR 55.41.10)

Group # 1 ------

Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: K/A # 295026EA2.01

Suppression pool water temperature Importance Rating 4.1 ------

Proposed Question: # 13 Unit 3 is currently testing Safety Relief Valves (SRVs) at 10% Reactor Power with the following plant conditions:

Suppression Pool Single Element Temperature is 112 ºF

Suppression Pool Bulk (Average)Temperature is 96 ºF Which ONE of the following describes the required action relative to Suppression Pool Temperature?

A. Suspend testing of the SRVs IMMEDIATELY in accordance with Tech Specs.

B. Testing can continue UNTIL bulk temperature exceeds 110 ºF in accordance with Tech Specs.

C. Operate ALL available Suppression Pool Cooling as directed by EOI-2 Primary Containment Control.

D. Enter EOI-1 RPV Control from EOI-2 Primary Containment Control AND SCRAM the reactor as directed by the EOIs.

Proposed Answer: C Explanation A INCORRECT: Bulk temp above 105 ºF would require testing to be (Optional): suspended. However the bulk temp is the determining factor and not a single element.

B INCORRECT: Bulk temp above 110 ºF would require the Mode Switch be placed in Shutdown IMMEDIATELY in accordance with Tech Specs.

Testing would have to be stopped IMMEDIATELY upon exceeding 105 ºF.

C CORRECT: Bulk temperature is used and not a single point. (See attached excerpts) Entry into EOI-2 is warranted at 95 ºF and it dictates that if Suppression Pool Temperature cannot be maintained below this value, ALL available cooling is operated when adequate core cooling is assured.

D INCORRECT: Bulk Temp above 110 ºF would require entry into EOI 1 for reactor scram. However only a single point is above 110 ºF and not bulk, or average, temperature.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet RO Level Justification: Tests the candidates knowledge of High Suppression Pool Temperature.

Determination of appropriate temperature indication to use and the required actions for EOI strategies is required for the operator. The use of LCO limits and the actions directed by the EOIs make this a discriminating question for an operator. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome.

This requires mentally using specific knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 3-EOI-2, Rev. 8 (Attach if not previously provided)

EOIPM Section 0-V-D, Rev. 0 Unit 3 Tech Spec 3.6.2.1 Amm 212 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.10 / 11 _______ (As available)

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

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295028 High Drywell Temperature / 5 ------

Tier # 1 EK2.01 (10CFR 55.41.5)

Group # 1 ------

Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following: K/A # 295028EK2.01

Drywell spray: Mark-I&II Importance Rating 3.7 ------

Proposed Question: # 14 Unit 1 has scrammed from 100% Reactor Power with the following conditions:

A small, high pressure steam leak in the Drywell has caused a Drywell Temperature of 280 ºF and rising

Drywell Pressure is 15 psig and rising Which ONE of the following completes the statement?

IMMEDIATELY following the initiation of Drywell Sprays under the superheated conditions listed above, the Drywell is expected to have a __(1)__ pressure drop indicative of __(2)__ cooling being the dominant mechanism of heat transfer.

A. (1) slow, steady (2) convective B. (1) slow, steady (2) evaporative C. (1) rapid, large (2) convective D. (1) rapid, large (2) evaporative Proposed Answer: D Explanation A INCORRECT: This is incorrect because it is based upon initiating Drywell (Optional): Sprays with saturation conditions present in containment. At some point during the Drywell pressure drop, conditions will result in a transition to convective cooling as the dominant mechanism; but, not immediately following initiation of sprays.

B INCORRECT: First part incorrect - See A above. Second part is correct in relation to the stem, but not in relation to the first part of the question.

C INCORRECT: First part is correct in relation to the stem, but not in relation to the first part of the question.. Second part is incorrect - See A above.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D CORRECT: (See attached excerpt) Small, high pressure steam leaks in the Drywell result in high temperatures with superheated conditions.

Initiating Drywell Sprays under these conditions results in an immediate, rapid, large pressure reduction due to evaporative cooling per the EOI Program Manual Bases. At some point during the Drywell pressure drop, conditions will reach saturation and result in a transition to convective cooling, but not immediately following initiation of sprays.

RO Level Justification: Tests the candidates knowledge of the relationship of Drywell Temperature to the initiation of Drywell Sprays and the resulting effects. It also requires overall knowledge of the environmental effects of sprays on containment in relation to superheated vs.

saturated conditions. This question is rated as Memory or Fundamental Knowledge based upon the requirements to recall technical information.

Technical Reference(s): EOI Program Man. Sect. 0-V-D, Rev. 0 (Attach if not previously provided)

OPL171.201, Rev. 7 OPL171.203, Rev. 7 Proposed references to be provided to applicants during examination: NONE Learning Objective: _OPL171.201 V.B.12__ _ (As available)

_OPL171.203 V.B.4 / 13__

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295030 Low Suppression Pool Wtr Lvl / 5 ------

Tier # 1 EK1.02 (10CFR 55.41.8)

Group # 1 ------

Knowledge of the operational implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL: K/A # 295030EK1.02

Pump NPSH Importance Rating 3.5 ------

Proposed Question: # 15 Given the following Unit 2 conditions:

Drywell Pressure is stable at 6.2 psig

Suppression Chamber Pressure is stable at 5 psig

RHR Pump 2A is currently operating at the Net Positive Suction Head (NPSH) limit

A large, unisolable leak occurs just upstream of RHR PUMP 2B SUPPR SUCT VLV, 2-FCV-74-24 Which ONE of the following completes the statement?

As a result of the leak, the EOI-related NPSH limit for RHR Pump 2A becomes __(1)__; making cavitation __(2)__ likely for a given Suppression Pool Temperature and RHR Pump flow rate.

A. (1) more restrictive; (2) less B. (1) more restrictive; (2) more C. (1) less restrictive; (2) less D. (1) less restrictive; (2) more Proposed Answer: B Explanation A INCORRECT: First part correct (see B below). Second part incorrect (Optional): because cavitation becomes more likely for a lower torus level (pressure).

Plausible if the applicant assumes that the more restrictive limit somehow prevents cavitation.

B CORRECT: (See attached excerpts) To accommodate suppression pool water levels above the minimum LCO water level, suppression chamber airspace pressure is expressed as overpressure in the NPSH Limit.

Overpressure is the sum of suppression chamber pressure and the hydrostatic head of water above the minimum LCO water level and must be determined by the operator when using the NPSH Limit. As pressure lowers, cavitation becomes more likely.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet C INCORRECT: First part incorrect because the limit becomes more restrictive as torus level (pressure) lowers. Also incorrect because cavitation becomes more likely as the limit becomes more restrictive.

Plausible if applicant thinks that a less restrictive curve moves the pump further away from cavitation.

D INCORRECT: First part incorrect because the limit becomes more restrictive as torus level (pressure) lowers. Second part correct. Plausible if applicant thinks that the RHR pump operating point changes when torus pressure changes, i.e., flow changes.

RO Level Justification: Tests the candidates knowledge of NPSH theory and operational implications associated with a lowering Suppression Pool Level; which equates to pressure at the suction of the pump. Overpressure is the sum of suppression chamber pressure and the hydrostatic head of water above the minimum LCO water level and must be determined by the operator when using the NPSH Limit. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using specific knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.201, Rev. 7 (Attach if not previously provided)

EOI Program Man. Sect. 2-IV, Rev. 10 EOI Program Man. Sect. 2-VI-N, Rev. 2 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.11 / 12_________ (As available)

Question Source: Bank # Hatch 07 NRC Q#56 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Hatch 2007-2008 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet BANK QUESTION FROM HATCH NRC EXAM

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295031 Reactor Low Water Level / 2 ------

Tier # 1 EK1.03 (10CFR 55.41.10)

Group # 2 ------

Knowledge of the operational implications of the following concepts as they apply to REACTOR LOW WATER LEVEL K/A # 295031EK1.03

Water level effects on reactor power Importance Rating 3.7 ------

Proposed Question: # 16 Which ONE of the following completes the statements?

In EOI C-5, Level / Power Control, Reactor Water Level is lowered to less than (-) 50 inches to

__(1)__ thereby reducing reactor power. After Hot Shutdown Boron Weight is injected into the Reactor, level is raised in order to __(2)__.

A. (1) MAXIMIZE core inlet subcooling (2) promote mixing of the Boron throughout the core.

B. (1) reduce natural circulation driving head AND core flow (2) promote mixing of the Boron throughout the core.

C. (1) MAXIMIZE core inlet subcooling (2) allow MSIVs to be reopened to commence a normal Cooldown.

D. (1) reduce natural circulation driving head AND core flow (2) allow MSIVs to be reopened to commence a normal Cooldown.

Proposed Answer: B Explanation A CORRECT: Part 1 incorrect - Plausible in that core inlet subcooling does (Optional): play into the ATWS level control strategy. If the reactor is not shutdown, RPV water level must be controlled to minimize core inlet subcooling, thereby preventing or mitigating the consequences of any large irregular neutron flux oscillations induced by neutronic/thermal-hydraulic instabilities.

Part 2 correct - See Explanation B.

B CORRECT: Part 1 correct - Lowering RPV water level reduces natural circulation driving head and core flow, thereby reducing reactor power and the heat addition rate to the suppression pool. Part 2 correct - The Hot Shutdown Boron Weight (HSBW) is the least weight of soluble boron which, if injected into the RPV and mixed uniformly, will maintain the reactor shutdown under hot standby conditions. When an amount of boron sufficient to shutdown the reactor has been injected into the RPV, mixing is accomplished by raising RPV water level.

C INCORRECT: Part 1 incorrect - See Explanation A. Part 2 incorrect -

Plausible in that after Cold Shutdown Boron has been injected, EOI-1 directs commencing plant cooldown. If the condenser is available, it would be preferred to cooldown to the condenser.

D INCORRECT: Part 1 correct - See Explanation B. Part 2 incorrect - See Explanation C.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: Requires Knowledge of the operational implications of Water level effects on reactor power as it applies to REACTOR LOW WATER LEVEL to correctly answer.

Technical Reference(s): OPL171.205 Rev. 8 (Attach if not previously provided)

EOI Program Manual Sect. 0-V-K Rev. 0 Proposed references to be provided to applicants during examination: NONE Learning Objective: ___________________ (As available)

Question Source: Bank #

Modified Bank # LaSalle 08 #41 (Note changes or attach parent)

New Question History: Last NRC Exam LaSalle 2008 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.205 Revision 8 Page 7 of 12

b. Unless mitigated, these conditions ultimately result in loss of NPSH for ECCS pumps taking suction on the suppression pool, containment over pressurization, and (ultimately) loss of primary containment integritywhich in turn could lead to a loss of adequate core cooling and uncontrolled release of radioactivity to the environment.

c. These conditions, combined with the inability to shut down the reactor through control rod insertion, dictate a requirement to promptly reduce reactor power since, as long as these conditions exist, suppression pool heat up will continue.

d. Reactor power must be reduced so that injection of the hot shutdown weight of boron can be completed before suppression pool temperature exceeds the Heat Capacity Temperature Limit.

7. Step C5-7

a. If the conditions of Step C5-6 exist, the operator is or has been directed to reject as much heat as possible from the RPV to the main condenser (RC/P-7 second and third overrides)

b. To place all available suppression pool cooling into operation (Step SP/T-3)

c. To trip the recirculation pumps (Step RC/Q-7),

and to concurrently inject boron and manually insert control rods (Steps RC/Q-10 and RC/Q-21).

d. One additional action remains available to mitigate the consequences of a failure-to-scram condition: deliberately lowering RPV water level to effect a reduction in reactor power.

e. Lowering RPV water level reduces natural circulation driving head and core flow, thereby reducing reactor power and the heat addition rate to the suppression pool.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.205 Revision 8 Page 8 of 12 (2) Depressurizing the RPV is preferred over Up to this point, restoring RPV water level through the use only outside shroud of systems which inject inside the shroud systems were listed because of the large reactor power excursions which may result from the in-shroud injection of large volumes of relatively cold and unborated water.

15. Step C5-17 Obj.V.B.6c

a. The Hot Shutdown Boron Weight (HSBW) is the 67% SLC tank level least weight of soluble boron which, if injected into the RPV and mixed uniformly, will maintain the reactor shutdown under hot standby conditions.

b. Since boron injects into the lower plenum, little boron mixing occurs under these conditions.

Three-dimensional scale model tests indicate that the injected boron concentrates in the lower plenum and does not contribute to reactor shutdown until in-core distribution (mixing) is achieved.

c. When an amount of boron sufficient to shutdown the reactor has been injected into the RPV, mixing is accomplished by raising RPV water level, thereby raising natural circulation flow through the vessel.

16. Step C5-18

a. Maintaining RPV water level below the normal operating range suppresses reactor power by reducing natural circulation core flow. If RPV water level is lowered to and maintained near -

180, little if any natural circulation flow exists within the RPV.

b. Restoration of RPV water level to the normal control band is therefore delayed until the SLC Tank level reaches 67% which corresponds to the Hot Shutdown Boron Weight.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.205 Revision 8 Page 9 of 12 D. C5, Level/Power Control

1. Purpose of C5, Level/Power Control

a. The actions specified in C5 Level/Power Control effect control of RPV water level under conditions when it cannot be determined that reactor will remain subcritical under all conditions without boron.

b. The actions to control RPV water level in C5 differ from those in RC/L of EOI-1 to address four basic concerns:

(1) When boron is injected into the RPV, the systems used for control of RPV water level must be operated so as to minimize boron dilution and cold water injection, and to promote boron mixing.

(2) If the reactor is not shutdown, RPV water level must be controlled to minimize core inlet subcooling, thereby preventing or mitigating the consequences of any large irregular neutron flux oscillations induced by neutronic/thermal-hydraulic instabilities.

(3) If the reactor is not shutdown and suppression pool temperature continues to rise, RPV water level must be controlled not only to adequately cool the core and minimize inlet subcooling, but also to minimize suppression pool heatup.

(4) Even if boron has not been injected into the RPV and the reactor is shutdown on control rods under hot conditions, injection of cold water could cause criticality, with no negative reactivity feedback occurring until reactor power rises to the heating range.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown ------

/1 Tier # 1 EK2.13 (10CFR 55.41.7) Group # 1 ------

Knowledge of the interrelations between SCRAM CONDITION K/A # 295037EK2.13 PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN and the following:

Alternate boron injection methods: Plant-Specific Importance Rating 3.4 Proposed Question: # 17 Which ONE of the following completes the statements?

During Anticipated Transient Without Scram (ATWS) conditions on Unit 2, 2-EOI-1, RPV Control requires Standby Liquid Control (SLC) initiation __(1)__.

If the Squib Valves fail to actuate (fire) during execution of 2-EOI Appendix-3A, SLC Injection, Sodium Pentaborate can be injected with CRD Pump __(2)__ as directed by 2-EOI Appendix-3B, Alternate SLC Injection.

A. (1) BEFORE Suppression Pool Temperature rises to 110 ºF ONLY.

(2) 1B B. (1) BEFORE Suppression Pool Temperature rises to 110 ºF ONLY.

(2) 2A C. (1) BEFORE Suppression Pool Temperature rises to 110 ºF OR WHEN APRM Peak-to-Peak Oscillations persist above 25%.

(2) 1B D. (1) BEFORE Suppression Pool Temperature rises to 110 ºF OR WHEN APRM Peak-to-Peak Oscillations persist above 25%.

(2) 2A Proposed Answer: C Explanation A INCORRECT: First part incorrect - (See attached excerpts) Although SLC (Optional): initiation is required for this condition, it is NOT the ONLY condition where SLC initiation is required. Second part is correct - as detailed in C below.

B INCORRECT: First part incorrect - as detailed in A above. Second part is incorrect - (See attached excerpts) Unit 2 does not use its respective CRD Pump for Alternate Boron Injection, unlike Units 1 and 3. This is a unit difference specific to BFN.

C CORRECT: First part correct - (See attached excerpts) EOI-1, RC/Q, Steps 9 and 10 both result, when conditions are met, in the requirement to inject Boron. One criterion is based on power oscillations and the other is based upon Suppression Pool Temperature. They could happen concurrently, or otherwise. Second part correct - (See attached excerpts) 2-EOI Appendix 3B specifies, for Unit 2, that Unit 1s CRD Pump 1B is used when executing Alternate SLC Injection on Unit 2.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D INCORRECT: First part correct - as detailed in C above. Second part incorrect - as detailed in B above.

RO Level Justification: Tests the candidates knowledge of ATWS conditions relative to EOIs requiring SLC initiation. Additionally, tests the candidates knowledge of sources for Alternate Boron Injection that are unit specific; wherein a unit difference is tested. Compounding level of difficulty is the fact that Units 1 and 3 utilize Unit 2s SLC Tank with their installed respective pumps. Unit 2 utilizes Unit 1s SLC Tank and Unit 1s CRD Pump 1B for Alternate Boron Injection.

Technical Reference(s): 2-EOI-1, Rev. 12 (Attach if not previously provided)

OPL171.039, Rev. 16 2-EOI Appendix-3B, Rev. 5 3-EOI Appendix-3B, Rev. 4 Proposed references to be provided to applicants during examination: NONE Learning Objective: _OPL171.039, V.B.6__ (As available)

_OPL171.202, V.B.15 _

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Excerpt from 2-EOI-1, RPV Control, RC/Q leg

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Added to support plausibility

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295038 High Off-site Release Rate / 9 ------

Tier # 1 G2.4.9 (10CFR 55.41.10)

Group # 1 ------

Knowledge of low power/shutdown implications in accident (e.g.,

loss of coolant accident or loss of residual heat removal) mitigation K/A # 295038G2.4.9 strategies.

Importance Rating 3.8 ------

Proposed Question: # 18 Unit 1 has been operating for one week with increasing amounts of fuel bundle leaks.

Suppression efforts have been unsuccessful and the trigger point for shutting down the reactor on excessive Stack release rates is rapidly approaching when the following alarms are received :

MAIN STEAM LINE RADIATION HIGH-HIGH 1-RA-90-135C, (1-9-3A, Window 27)

OG AVG ANNUAL RELEASE RATE EXCEEDED 1-RA-90-157C (1-9-4C, Window 27)

Which ONE of the following completes the statements for this condition?

The requirement to insert a manual scram is driven by a valid __(1)__ alarm.

Immediately following the scram, the ARP-specific IF / THEN directive to CLOSE MSIVs is based upon a determination that __(2)__.

A. (1) MAIN STEAM LINE RADIATION HIGH-HIGH 1-RA-90-135C (2) releases are still in excess of Offsite Dose Calculation Manual limits.

B. (1) OG AVG ANNUAL RELEASE RATE EXCEEDED 1-RA-90-157C (2) the reactor will remain subcritical without boron under all conditions.

C. (1) MAIN STEAM LINE RADIATION HIGH-HIGH 1-RA-90-135C (2) the reactor will remain subcritical without boron under all conditions.

D. (1) OG AVG ANNUAL RELEASE RATE EXCEEDED 1-RA-90-157C (2) releases are still in excess of Offsite Dose Calculation Manual limits.

Proposed Answer: C Explanation A INCORRECT: First part correct - as detailed in C below. Second part is (Optional): incorrect in that action(s) will be required if ODCM limits are being exceeded; but closing of the MSIVs is not specified. The ARP for Main Steam Line Rad Hi-Hi is very specific on closing MSIVs if not in Level

/Power Control Contingency C-5 though.

B INCORRECT: First part incorrect - (See attached excerpts) The ARP for Offgas Average Annual Release Rate Exceeded is very specific on specifying a power reduction, but does not drive the scram directly; wherein the MS Line Rad Hi-Hi does. Second part correct - as detailed in C below.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet C CORRECT: (See attached excerpts) The Main Steam Line Rad Hi-Hi alarm, once validated, requires a core flow runback followed by a manual scram. Additionally, ARP specifies that if not in C-5 that MSIVs must be closed. If the reactor is shutdown under all conditions without boron, EOI Contingency C-5 will not be executed. Candidate must understand strategies associated with EOI/Contingency implementation.

D INCORRECT: Both parts incorrect - as detailed in A and B above.

RO Level Justification: Tests candidates knowledge of shutdown (ALL RODS IN) implications as they relate to excessive fuel failures inside the reactor core and the resultant high offsite release rates. As the ARP only specifies whether or not you are in C-5,additionally tests the candidates knowledge of strategies associated with EOI and EOI Contingency implementation.

Candidate must determine whether or not C-5 requires execution for these conditions. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 1-ARP-9-4C, Rev. 18 (Attach if not previously provided) 1-ARP-9-3A, Rev. 38 Proposed references to be provided to applicants during examination: NONE Learning Objective: _OPL171.009 V.B.14.a (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 600000 Plant Fire On Site / 8 ------

Tier # 1 AK1.02 (10CFR 55.41.5)

Group # 1 ------

Knowledge of the operational implications of the following concepts as they apply to PLANT FIRE ON SITE: K/A # 600000AK1.02

Fire fighting Importance Rating 2.9 ------

Proposed Question: # 19 The following plant conditions currently exist on Unit 3:

A Seal Oil Skid fire has erupted AND the sprinkler system has been manually initiated

Fire header pressure has been 115 psig for 25 seconds after actuation of the sprinkler system

A small leak in the Drywell resulted in Drywell Pressure of 3 psig and steady Which ONE of the following completes the statement?

Based on these conditions, the Diesel Fire Pump ______.

A. AND ALL THREE Electric Fire Pumps are operating.

B. AND ALL THREE Electric Fire Pumps are in standby.

C. is in standby AND ONE Electric Fire Pump is operating.

D. is in standby AND TWO Electric Fire Pumps are operating.

Proposed Answer: D Explanation A INCORRECT: Two Electric Fire Pumps are running but Diesel Fire Pump is (Optional): not. If system header pressure is not >120 psig 45 seconds after the initiation signal, the Diesel Fire Pump automatically starts. (ONLY 25 sec has elapsed)

B INCORRECT: Automatic start of the Fire Pumps is locked out on High Drywell Pressure (2.45 psig) in conjunction with Low Reactor Pressure (450 psig) or Low Low Low Reactor Water Level (-122 in.) AND Diesel Generators are supplying power to the 4kV Shutdown Boards. With no conditions resulting in D/Gs supplying the 4 kV Shutdown boards, the Fire Pumps are not locked out.

C INCORRECT: Two Electric Fire Pumps are running. Plausible in that candidate may believe that manual initiation of the sprinkler system would not result in automatic start of one Electric Fire Pump.

D CORRECT: The first fire pump will automatically start on any spray, sprinkler or fog system manual or automatic actuation. This initial fire pump auto-start is based on a sensed fire condition; NOT on low pressure. If system header pressure is not >120 psig 15 seconds after the initiation signal, a second Fire Pump automatically starts.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet RO Level Justification: Tests the candidates knowledge of interlocks associated with fire pumps in response to a plant fire on site. Additionally, the question tests the candidates knowledge of the impact of high drywell pressure on the fire pumps start logic.

Technical Reference(s): OPL171.049 Rev 15 (Attach if not previously provided) 0-OI-26 Rev 90 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.4_____________ (As available)

Question Source: Bank #

Modified Bank # OPL171.049 #23 (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 700000 Generator Voltage and Electric Grid Disturbances / 6 ------

Tier # 1 AA1.03 (10CFR 55.41.10)

Group # 1 ------

Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: K/A # 700000AA1.03

Voltage regulator controls Importance Rating 3.8 ------

Proposed Question: # 20 Unit 3 is operating at 80% Reactor Power AND the crew has entered 0-AOI-57-1E, Grid Instability, due to the 500 kV system voltage being at 541 kV. The crew reaches the following step in the procedure:

LOWER reactive power until system voltage returns to 530 kV Which ONE of the following identifies how to lower reactive power AND the 161 kV Capacitor Bank Status that will restore the system voltage in accordance with 0-AOI-57-1E?

A. Depress the EHC Load Set LOWER pushbutton, 3-HS-47-75C; Check the 161 kV Capacitor Banks are IN service.

B. Depress the EHC Load Set LOWER pushbutton, 3-HS-47-75C; Check the 161 kV Capacitor Banks are OUT of service C. Place the Generator Field Voltage Auto Adjust (90P), 3-HS-57-26, to the LOWER position; check the 161 kV Capacitor Banks are IN service.

D. Place the Generator Field Voltage Auto Adjust (90P), 3-HS-57-26, to the LOWER position; check the 161 kV Capacitor Banks are OUT of service.

Proposed Answer: D Explanation A INCORRECT: Part 1 and 2 incorrect - Depressing the EHC load set (Optional): LOWER pushbutton would have an effect on load / voltage at current power levels; but, is not a procedurally allowed action. Additionally, the 161 kV Capacitor Banks are not in service and will not aid in restoring high system voltage.

B INCORRECT: Part 1 incorrect (See above) - Part 2 is correct as required by 0-AOI-57-1E (See below).

C INCORRECT: Part 1 is correct and Part 2 is incorrect.

D CORRECT: (See attached excerpt) Part 1 correct - Per 0-AOI-57-1E, LOWER reactive power to system voltage returns to 530KV OR UNTIL Generator Reactive Power reaches -150 MVAR, Per 3-OI-47, To adjust GENERATOR MVAR, 3-EI-57-51, in the positive or lagging direction, PLACE GENERATOR FIELD VOLTAGE AUTO ADJUST (90P), 3-HS 26, in RAISE UNTIL desired MVAR is indicated. Part 2 correct - Per 0-AOI-57-1E, CHECK 161KV Cap Banks are OUT of service.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet RO Level Justification: Tests the candidates ability to recognize the need and method to adjust the voltage regulator controls to lower reactive power during grid instability conditions.

Additionally, knowledge of the role the Capacitor Banks provide in this condition is necessary.

This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using specific knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 0-AOI-57-1E Rev 7 (Attach if not previously provided) 3-OI-47 Rev 89 OPL171.036 Rev. 12 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.13 / 14 ________ (As available)

Question Source: Bank #

Modified Bank # HLT 0801 Q#20 (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet BANK QUESTION THAT WAS MODIFIED

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295002 Loss of Main Condenser Vac / 3 ------

Tier # 1 AK2.02 (10CFR 55.41.10)

Group # 2 ------

Knowledge of the interrelations between LOSS OF MAIN CONDENSER VACUUM and the following: K/A # 295002AK2.02

Main turbine Importance Rating 3.1 ------

Proposed Question: # 21 Given that Main Condenser Vacuum is degrading, which ONE of the following completes the statements?

A RISING Off-Gas flow on OG FLOW TO 6-HOUR HOLDUP VOLUME, 3-FR-66-20, would be indicative of __(1)__.

To ensure a Manual Scram is inserted prior to automatic action occurring, a Control Room Panel 3-9-6 Hotwell Pressure reading of __(2)__ inches Hg Vacuum would be a valid Trigger Value in accordance with OPDP-1, Conduct of Operations.

A. (1) air in-leakage to the Main Condenser.

(2) 22.5 B. (1) First Stage Steam Jet Air Ejector stalling.

(2) 22.5 C. (1) air in-leakage to the Main Condenser.

(2) 25 D. (1) First Stage Steam Jet Air Ejector stalling.

(2) 25 Proposed Answer: C Explanation A INCORRECT: First part is correct - see C below. Second part is incorrect (Optional): - see C below. So, in this case, the unintended consequence (AUTOMATIC Rx Scram) would have already occurred. If the candidate were to set the Trigger Value off of the actual setpoint (-21.8 in.), this value would be chosen. The value of -25 inches would be too far away to be a valid Trigger Value in this case, wherein they may still be attempting to lower power.

B INCORRECT: (See attached excerpts). First part incorrect in that according to 3-AOI-47-3 specifically, First Stage SJAE stalling will cause REDUCED Off-Gas flows, but will still result in the same consequences.

Second part is incorrect - see A above.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet C CORRECT: (See attached excerpts). According to 3-AOI-47-3 specifically, a RISING Off-Gas flow rate is indicative of Condenser Air In-leakage. It goes on to discuss the OE where the procedurally-specified, actual trip setpoint for the instruments of -21.8 in. Hg Vacuum does not correspond to the same observable value in the Control Room. The Control Room indication value of approximately -24.3 (but well before -22.5 in.) is where the Main Turbine actually trips on Low Condenser Vacuum. OPDP-1 sets forth requirements on establishing Trigger Values for Manual Insertion of a Reactor Scram in cases such as this.

D INCORRECT: First part is incorrect - see B above. Second part is correct.

RO Level Justification: Tests the candidates knowledge of potential transient conditions that can impact condenser vacuum, along with the subsequent impact to the Main Turbine (and Reactor) itself. An element of Conduct of Operations is tested with setting a Trigger Value. Additionally, plant Operating Experience is also tested in the relationship of the trip setpoint to where the turbine actually trips based upon Control Room indications. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome.

This requires mentally using specific knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 3-AOI-47-3, Rev. 11 (Attach if not previously provided) 3-OI-47, Rev. 89 OPDP-1, Rev. 15 OPL171.010, Rev. 12 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.12 / 23_________ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295009 Low Reactor Water Level / 2 ------

Tier # 1 AK1.05 (10CFR 55.41.10)

Group # 2 ------

Knowledge of the operational implications of the following concepts as they apply to LOW REACTOR WATER LEVEL: K/A # 295009AK1.05

Natural circulation Importance Rating 3.3 ------

Proposed Question: # 22 Unit 2 is in Mode 4 with the following conditions:

Reactor Level is (+) 45 inches

ALL Shutdown Cooling has been lost Which ONE of the following identifies the reason that 2-AOI-74-1, Loss of Shutdown Cooling, requires a HIGHER Reactor Water Level established AND maintained?

The HIGHER Reactor Water Level ______.

A. provides additional mass of water in the Reactor Vessel to delay boiling.

B. floods the Moisture Separators which provides a path for natural circulation.

C. allows the Main Steam Line Drains to provide a drain path for feed AND bleed.

D. provides greater Net Positive Suction Head for the Reactor Water Cleanup Pumps.

Proposed Answer: B Explanation A INCORRECT: Although additional mass of water would delay boiling, the (Optional): reason level is raised to provide path for Natural Circulation.

B CORRECT: If forced circulation is lost level is raised to (+) 80 inches per 2-AOI-74-1 to flood the Moisture Separators and provide a path for natural circulation.

C INCORRECT: Feed and Bleed through MSL Drains would mitigate a loss of Shutdown Cooling but level is not raised to the MSL level of (+) 117 inches RPV Water Level.

D INCORRECT: It is true that raising level would provide greater Net Positive Suction Head for RWCU Pump; however, strategy to raise level would not be used if any forced circulation is available. Therefore, RWCU would be out of service.

Justification: Candidate must recognize the implications of low reactor water level, i.e. < (+) 80 inches with a loss of Shutdown Cooling and the reason for raising level.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 2-OI-74 Rev. 150 (Attach if not previously provided) 2-AOI-74-1 Rev. 33 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.074 V.B.7____ (As available)

Question Source: Bank # DAEC 07 #49 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Duane Arnold 07 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Duane Arnold NRC 2007

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295010 High Drywell Pressure / 5 ------

Tier # 1 AA1.06 (10CFR 55.41.7)

Group # 2 ------

Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE: K/A # 295010AA1.06

Leakage detection systems Importance Rating 3.3 ------

Proposed Question: # 23 Unit 2 is at 75% Reactor Power when DRYWELL NORM OPERATING PRESS HIGH, (2-9-3B, Window 19) is received. Drywell Pressure is 1.6 psig AND slowly trending up.

Which ONE of the following completes the statements?

In attempting to determine whether the Technical Specification UNIDENTIFIED leakage rate was rising, the operator would evaluate pump-out AND fill-rates for the Drywell __(1)__ Drain Sump.

If the sump fills faster than the preset allowable time, then the Fill-Rate Timer logic will feed directly into the respective alarm for __(2)__.

A. (1) Floor (2) Excessive Sump Pump Operation B. (1) Equipment (2) Excessive Sump Pump Operation C. (1) Floor (2) Drain Sump Level Abnormal D. (1) Equipment (2) Drain Sump Level Abnormal Proposed Answer: A Explanation A CORRECT: (See attached excerpts) Per TS 3.4.4, RCS Operational (Optional): Leakage, Operational leakage shall be limited to 5 gpm Unidentified leakage. BOTH Floor and Equipment Drains are utilized in calculating operational leakage. In the case of UNIDENTIFIED, this leakage is collected in the Floor Drain Sump; versus IDENTIFIED leakage being collected in the Equipment Drain Sump. Part 2 - correct in that, although counterintuitive in comparison, the fill rate timer does not feed into the Abnormal Sump Level Alarm(s); it feeds into the Excessive Sump Pump Operation Alarm(s), per ARP-9-4C.

B INCORRECT: First part incorrect - as detailed in A above. Second part correct - as detailed in A above.

C INCORRECT: First part correct - as detailed in A above. Second part correct - as detailed in A above.

D INCORRECT: First part incorrect - as detailed in A above. Second part correct - as detailed in A above.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet RO Level Justification: To correctly answer, candidate must demonstrate ability to monitor Leakage detection systems in response to HIGH DRYWELL PRESSURE and use the data to determine Tech Spec Operational Leakage. This question is rated as MEM due to the requirement to recall facts.

Technical Reference(s): OPL171.016, Rev. 17 (Attach if not previously provided)

U2 TS 3.4.4 Amm. 253 2-ARP-9-4C, Rev. 30 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.087 V.B.8____ (As available)

OPL171.016 V.B.14/16___

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295022 Loss of CRD Pumps / 1 ------

Tier # 1 G2.2.38 (10CFR 55.41.10)

Group # 2 ------

Knowledge of conditions and limitations in the facility license.

K/A # 295022G2.2.38 Importance Rating 3.6 ------

Proposed Question: # 24 Unit 2 is operating at 100% Reactor Power when the running CRD pump trips AND actions to restore a CRD pump have NOT been successful. The following alarm is subsequently received during efforts to restore one CRD Pump:

CONTROL ROD DRIVE UNIT HIGH TEMP, (2-9-5A, Window 17), is in alarm Which ONE of the following identifies the setpoint for this alarm AND the required action in accordance with 2-ARP-9-5A, Panel 9-5 2-XA-55-5A?

A. 250 °F; declare the affected Control Rod(s) SLOW B. 250 °F; declare the affected Control Rod(s) INOPERABLE C. 350 °F; declare the affected Control Rod(s) SLOW D. 350 °F; declare the affected Control Rod(s) INOPERABLE Proposed Answer: C Explanation A INCORRECT: (See attached excerpts) First part incorrect - Per Tech Spec (Optional): 3.1.4 Bases, temperatures are permitted to rise to 350 °F prior to affecting Scram times. Then, they would be declared SLOW per note 1 of T.S. 3.1.4 -

1 table; making the second part correct.

B INCORRECT: First part incorrect - as detailed in A above. Second part incorrect in that no procedural guidance is established at BFN for this possibility. All procedures distinctly delineate a declaration of SLOW.

C CORRECT: The candidate must determine that no CRD pump is operating based on indications given. (See attached excerpts) Per T.S. 3.1.4 Bases and 2-TI-393, temperatures are permitted to rise to 350 °F prior to affecting Scram times. Then, they would be declared SLOW per note 1 of T.S. 3.1.4 -

1 table in accordance with 2-TI-393 and ARP-9-5A.

D INCORRECT: First part correct as detailed in C above. Second part is incorrect as detailed in B above.

RO Level Justification: Tests the candidates knowledge of the implications of a loss of CRD Pumps and the subsequent impact on CRD Mechanism temperatures as they relate to Browns Ferry Technical Specifications. This question is rated as C/A due to the requirement to assemble, sort, and integrate two distinct parts of the question to predict an outcome. This requires mentally using specific knowledge and its meaning to predict the correct outcome.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): U2 Tech Spec 3.1.4, Am.253 (Attach if not previously provided)

U2 Tech Spec Bases 3.1.4, Rev. 9 2 -ARP-9-5A, Rev. 45 2-TI-393, Rev. 2 Proposed references to be provided to applicants during examination: NONE Learning Objective: _OPL171.006 V.B.18 / 22 (As available)

Question Source: Bank # X 0801 #25 Modified Bank # (Note changes or attach parent)

New Question History: HLT 0801 Last NRC Exam (07 / 2009)

(Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295029 High Suppression Pool Wtr Lvl / 5 ------

Tier # 1 EK3.03 (10CFR 55.41.10)

Group # 2 ------

Knowledge of the reasons for the following responses as they apply to HIGH SUPPRESSION POOL WATER LEVEL: K/A # 295029EK3.03

Reactor SCRAM Importance Rating 3.4 ------

Proposed Question: # 25 In accordance with the EOI Program Manual, which ONE of the following completes the statements?

With the reactor operating at 100% power, a Suppression Pool Water Level that is continuously

__(1)__ will result in entry into the Action Required area of Curve 4, SRV Tail Pipe Limit.

Eventually, a Manual Scram is directed from the Suppression Pool Level Control (SP/L) leg of EOI-2, Primary Containment Control, with the purpose being to attempt to lower __(2)__

relative to the curve.

A. (1) rising ONLY (2) Reactor Pressure B. (1) rising ONLY (2) Suppression Chamber Pressure C. (1) rising OR lowering (2) Reactor Pressure D. (1) rising OR lowering (2) Suppression Chamber Pressure Proposed Answer: A Explanation A CORRECT: (See attached excerpts) A continuously rising water level in (Optional): the Suppression Pool will eventually exceed Curve 4 (approx 16.75 feet @

100% power). EOI-1 entry in this case would be because level cannot be maintained in the safe area of Curve 4 for the SRV Tail Pipe limit. Bases documents provide the supporting insight on the necessity to attempt to lower reactor pressure relative to the curve.

B INCORRECT: First part correct, as detailed in A above. Second part plausible, but incorrect, based upon the fact that the candidate is not given the curve itself and Suppression Chamber Pressure is a notable parameter associated with other EOI-related curves.

C INCORRECT: First part incorrect, in that rising will exceed the curve, but lowering will not exceed the curve. In the absence of the curve, the candidate could incorrectly determine that uncovering of the SRV tail pipe is also a factor in the Level Limit. Other related EOI curves (HCTL and PSP) can be impacted by a rising or lowering level. Thus, without a reference, this is very plausible. Second part correct, as detailed in A above.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D INCORRECT: Both parts incorrect, but plausible, as detailed in B and C above.

RO Level Justification: Tests the candidates knowledge of EOI Program Bases associated with entering EOI-1 from EOI-2 on a high Suppression Pool Water Level; and why the Scram, in particular, is directed. Because the candidate is not provided with a reference in this case or told the exact point at which EOI-1 entry is required, this question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome.

This requires mentally using specific knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 1-EOI-2, Rev. 0 (Attach if not previously provided)

EOI Program Man., Sect. 0-V-D, Rev. 0 OPL171.203, Rev. 7 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.11 ____________ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet APPLICABLE TO ALL UNITS IN THIS CASE (UNIT 1 EXAMPLE)

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet INFO SUPPORTING DISTRACTORS C AND D

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295034 Secondary Containment Ventilation High Radiation / 9 ------

Tier # 1 EA1.02 (10CFR 55.41.7)

Group # 2 ------

Ability to operate and/or monitor the following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION: K/A # 295034EA1.02

Process radiation monitoring system Importance Rating 3.9 ------

Proposed Question: # 26 On Unit 3, a Refueling Accident has occurred resulting in the following conditions:

ALL Refuel Zone Radiation Monitor Channels are reading 65 mr/hr

Control Room Ventilation Rad Monitors 90-259A/B are reading 155 cpm

ALL Reactor Zone Radiation Monitor Channels are reading 68 mr/hr Based on these conditions, which ONE of the following identifies the status of plant systems?

A. NO Standby Gas Treatment Systems are in service; NO CREV are in service.

B. ALL Standby Gas Treatment Systems are in service; NO CREV are in service.

C. NO Standby Gas Treatment Systems are in service; ONLY the selected CREV is in service.

D. ALL Standby Gas Treatment Systems are in service; ONLY the selected CREV is in service.

Proposed Answer: A Explanation A CORRECT: Radiation Levels at the Refuel Zone Radiation Monitors and (Optional): Reactor Zone Radiation Monitor are below the automatic initiation set point of 72 mr/hr for both CREV and SGTS Initiation. Control Room Ventilation Rad Monitors 90-259A/B are reading 155 cpm which is above the ALERT alarm set point but is less than the initiation set point of 221 cpm with 2 minute time delay.

B INCORRECT: Standby Gas Treatment Systems will not be in service.

Second part is correct.

C INCORRECT: First part is correct. Second part is incorrect, no CREV will be in service.

D INCORRECT: Both parts are incorrect as explained above.

RO Level Justification: Candidate must recognize automatic initiation conditions to demonstrate ability to monitor and operate process radiation monitoring as it applies to Secondary CTMT Ventilation High Radiation. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPL171.067 Rev. 16 (Attach if not previously provided)

OPL171.018 Rev. 10 3-OI-90 Rev. 55 Proposed references to be provided to applicants during examination: NONE Learning Objective: _OPL171.067 V.B.2__ (As available)

Question Source: Bank #

Modified Bank # 0801 #10 (Note changes or attach parent)

New Question History: Last NRC Exam BFN 0801 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments: Conditions in the stem were modified such that one of the distracters became the correct answer making this a significantly modified question.

OPL171.067 Revision 16

a. Automatic start signals are:

(1) High radiation of 221 cpm above background + 2 Min TD (270 cpm Tech Specs) in air inlet ducts to Control Room from (Radiation monitor RM 90-259A Units 1 & 2, Radiation monitor RM 90-259B Unit 3). Either monitor starts selected CREV unit.

(2) Reactor zone ventilation systems radiation high >72 MR/hr (3) Refuel zone ventilation systems radiation high >72 MR/hr (1) Low reactor water level at +2 inches above instrument zero (2) High primary containment pressure

>2.45 psig

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.018 Revision 10

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet BFN 0801 NRC #10 On Unit 3, a Refueling Accident has occurred resulting in the following conditions:

ALL Refuel Zone Radiation Monitor Channels are reading 65 mr/hr

Control Room Ventilation Rad Monitors 90-259A/B are reading 100 cpm

ALL Reactor Zone Radiation Monitor Channels are reading 75 mr/hr Based on these conditions, which ONE of the following identifies the status of plant systems?

A. NO Standby Gas Treatment Systems are in service; NO CREV is in service.

B. ALL Standby Gas Treatment Systems are in service; NO CREV is in service.

C. NO Standby Gas Treatment Systems are in service; ONLY the selected CREV is in service.

D. ALL Standby Gas Treatment Systems are in service; ONLY the selected CREV is in service.

ANSWER: D

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 295036 Secondary Containment High Sump/Area Water Level / 5 ------

Tier # 1 EA2.01 (10CFR 55.41.10)

Group # 2 ------

Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER K/A # 295036EA2.01 LEVEL:

Operability of components within the affected area Importance Rating 3.0 ------

Proposed Question: # 27 A Condensate Transfer System leak spraying on Unit 1 Loop II Core Spray Room Cooler has resulted in the following:

Loop II Core Spray Room Cooler has tripped AND will NOT reset

CORE SPRAY LOOP II PUMP ROOM FLOOD LEVEL HIGH, (1-9-4C, Window 31), is in alarm Which ONE of the following completes the statements?

Loop II Core Spray __(1)__operable.

Entry into 1-EOI-3, Secondary Containment Control, __(2)__ required.

A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Proposed Answer: C Explanation A INCORRECT: Part 1 incorrect - See explanation B. Part 2 correct - See (Optional): explanation C.

B INCORRECT: Part 1 incorrect - Plausible in that the Core Spray System will function with the CS Room Cooler out of service. Part 2 incorrect -

Plausible in that not all alarms associated with degrading conditions occur at the EOI Entry level.

C CORRECT: Part 1 correct - Per TR 3.5.3, the equipment area cooler associated with each Core Spray Pump must be operable when that Core Spray System is considered to be operable. With the area cooler inoperable, Condition A requires the pumps served by the cooler be declared inoperable immediately. Part 2 correct - The Reactor Building floor drain sump High-High level (66) is an EOI-3 entry condition.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D INCORRECT: Part 1 correct and Part 2 incorrect as explained above.

Justification: Candidate must recognize the impact of the leakage in the area and associated loss of Loop I Core Spray Room Cooler on the associated Core Spray System operability. Since question can be answered knowing 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Tech Spec Actions, this is an RO question. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL 171.204 Rev. 7 (Attach if not previously provided)

U1 TRM, Section 3.5.3 Rev. 0 1-ARP-9-4C Rev. 18 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.204 V.B.2 ___ (As available)

OPL171.045 V.B.4 / 6_

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.204 Revision 7 Page 3 of 52 A secondary containment floor drain sump water level above maximum normal operating level is an indication that steam or water may be discharging into secondary containment. Maximum normal operating floor drain sump water level is defined to be the highest value of secondary containment floor drain sump water level expected to occur during normal plant operating conditions with all directly associated support and control systems functioning properly.

f. Area water levels above 2 inches Secondary containment area water level above maximum normal operating level is an indication that steam or water may be discharging into secondary containment. Maximum normal operating secondary containment water level is defined to be the highest value of secondary containment area water level expected to occur during normal plant operating conditions with all directly associated support and control systems functioning properly.

g. Area radiation level above the maximum normal operating value of Table 4.

Secondary containment area radiation level above the maximum normal operating value of Table 4 is an indication that water from a primary system, or from a primary to secondary system leak, may be discharging into secondary containment. Maximum normal operating secondary containment area radiation level is defined to be the highest value of secondary containment areas radiation expected to occur during normal plant operating conditions with all directly associated support and control system functioning properly.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Example of elevated parameter alarm to support distractors Drywell Pressure Abnormal alarms before EOI Entry of 2.45 psig

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 203000 RHR/LPCI: Injection Mode ------

Tier # 2 A1.01 (10CFR 55.41.5)

Group # 1 ------

Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI: INJECTION MODE (PLANT K/A # 203000A1.01 SPECIFIC) controls including:

Reactor water level Importance Rating 4.2 ------

Proposed Question: # 28 Given the following conditions:

Unit 2 has experienced a Loss of Coolant Accident (LOCA)

Drywell Sprays are required in accordance with Primary Containment Control, 2-EOI-2 Which ONE of the following plant conditions must exist prior to opening BOTH the Residual Heat Removal (RHR) SYS I Inboard AND Outboard Drywell Spray Valves?

A. Reactor Level must be greater than (-) 155 inches (Emergency Range) with ONLY the CONT SPRAY VLV SEL SWITCH in SELECT.

B. Reactor Level must be greater than (-) 162 inches (Post Accident Range) with ONLY the CONT SPRAY VLV SEL SWITCH in SELECT.

C. Reactor Level is greater than (-) 183 inches (Post Accident Range) with ONLY the CONT SPRAY VLV SEL SWITCH in SELECT.

D. Reactor Level is less than (-) 200 inches (Post Accident Range) with ONLY the 2/3 CORE HEIGHT KEYLOCK BYPASS SWITCH in BYPASS.

Proposed Answer: C Explanation A INCORRECT: With RPV level > -155 inches adequate core cooling is (Optional): assured by submergence and therefore spraying containment is allowed. If candidate determines that top of active fuel verses 2/3 core height is necessary, it becomes plausible. Also level must be above -183" not -155" B INCORRECT: With RPV level > -162 inches (top of active fuel) adequate core cooling is assured. If candidate determines that top of active fuel versus 2/3's core height is necessary, it becomes plausible. Also level must be above -183" not -162" C CORRECT: OPL171.044, TP 33 shows that under the conditions only the CONT SPRAY VL V SEL SWITCH in SELECT is required to allow spraying containment. Contact K 14A1B is closed if level is above 2/3's core height

(-183") as referenced on the Post Accident range (-268" to +60"). Contact K61A1B is closed due to an accident signal (level <-122" on the Wide range level instruments). Therefore to complete the logic only the SELECT switch is required to be closed which energizes relays K58A1B (Seal In) and K50A/B which allows spraying containment.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D INCORRECT: With RPV level < -200 inches, you are below 2/3's core height which requires both the CONT SPRAY VL V SEL SWITCH in SELECT and 2/3 CORE HEIGHT KEYLOCK BYPASS switch in BYPASS.

Justification: This question satisfies the KIA statement by requiring the candidate to use specific values of reactor water level to determine the conditions which allow diverting RHR from a LPCI Injection lineup to containment control. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 2-OI-74 Rev. 150 (Attach if not previously provided)

OPL171.044 Rev. 17 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.044 V.B.10___ (As available)

Question Source: Bank # BFN 0610 #1 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam BFN 2008 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 203000 RHR/LPCI: Injection Mode ------

Tier # 2 A1.04 (10CFR 55.41.5)

Group # 1 ------

Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI: INJECTION MODE (PLANT K/A # 203000A1.04 SPECIFIC) controls including:

System pressure Importance Rating 3.6 ------

Proposed Question: # 29 Unit 1 was operating at 100% Reactor Power when a LOCA occurred resulting in the following:

Reactor Pressure is 405 psig

Reactor Level is (-) 140 inches Which ONE of the following completes the statement?

The RHR SYS I LPCI OUTBD INJECT VALVE, 1-FCV-74-52, is __(1)__ AND the RHR SYS I MIN FLOW VALVE, 1-FCV-74-7, is __(2)__.

A. (1) OPEN (2) CLOSED B. (1) CLOSED (2) CLOSED C. (1) OPEN (2) OPEN D. (1) CLOSED (2) OPEN Proposed Answer: C Explanation A INCORRECT: Part 1 correct - See Explanation C. Part 2 incorrect - See (Optional): Explanation B.

B INCORRECT: Part 1 incorrect - Plausible in that the Reactor Pressure associated with the LPCI Injection Valve interlock could be confused with the RHR Shutoff Head Pressure of 320 psig. Part 2 incorrect - Plausible in that Reactor Pressure is less than Shutoff Head for Condensate Booster Pumps which have similar pump design criteria and could therefore be confused with RHR Shutoff Head Pressure.

C CORRECT: Part 1 correct - Reactor Water Level is less than RHR LPCI Initiation Level of (-) 122 inches and Reactor Pressure is less than LPCI Injection Valve interlock of 450 psig. Therefore, the LPCI injection valves are open. Part 2 correct - Reactor Pressure is greater than the RHR Pumps Shutoff Head of 320 psig. With system flow less than 5800 gpm, the LPCI Minimum Flow Valves will be open.

D INCORRECT: Part 1 incorrect - See Explanation B. Part 2 correct - See Explanation C

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: To successfully answer, candidate must have knowledge of RHR System response in LPCI Mode to demonstrate ability to predict and/or monitor changes in parameters associated with system pressure.

Technical Reference(s): OPL171.044 Rev. 17 (Attach if not previously provided) 0-TI-394 Rev. 4 / 1-OI-74 Rev. 69 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.044_V.B.18__ (As available)

Question Source: Bank # La Salle 08 #14 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam La Salle 2008 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments: Question identified as a Bank question although it has been modified from original question associated with Core Spray System at La Salle. Adapted to RHR LPCI for BFN. Does not meet the criteria of a significantly modified question since no distracters were significantly changed.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 205000 Shutdown Cooling ------

Tier # 2 K3.05 (10CFR 55.41.7)

Group # 1 ------

Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING K/A # 205000K3.05 MODE) will have on the following:

Fuel pool cooling assist: Plant-Specific Importance Rating 2.6 ------

Proposed Question: # 30 On Unit 3, RHR Pump 3C has been placed in Supplemental Fuel Pool Cooling.

M 48 A

M 12 M 47 35 M M M 13 36 M M B

1 24 M M 2 25 3-FCV-74-1 / 12 / 24 / 35 - SUPPR POOL SUCT VLVs

- ALL other valves associated with Shutdown Cooling Which ONE of the following completes the statements?

Suction from Fuel Pool Cooling ties into RHR at point __(1)__. A Shutdown Cooling Isolation

__(2)__ result in LOSS of Supplemental Fuel Pool Cooling.

A. (1) A (2) will B. (1) B (2) will C. (1) A (2) will NOT D. (1) B (2) will NOT

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: D Explanation A INCORRECT: First part incorrect - (See attached) - the tap for (Optional): Supplemental Fuel Pool Cooling suction ties in just before the 13 valve, which is also in the Shutdown Cooling suction path, BUT NOT between the 47 and 48 valves. Second part incorrect - in that the 47 and 48 valves do, in fact, receive a close signal as a function of a Shutdown Cooling Isolation signal (logic attached FCV-74-47 AND 48); and if this were the proper configuration, the potential closing of these valves would isolate the path.

B INCORRECT: First part correct - (See attached) - the tap for Supplemental Fuel Pool Cooling suction ties in just before the 13 valve, which is also in the Shutdown Cooling suction path,. Second part incorrect

- in that to lose Sup. Fuel Pool Cooling from this lineup, the 13 valve (associated w/ RHR Pump C) would have to travel closed on an isolation signal from Shutdown Cooling; and it does NOT receive a close signal as a function of a Shutdown Cooling Isolation signal (similar logic attached FCV-74-2).

C INCORRECT: Part 1 incorrect - as detailed in A above. Part 2 correct -

but, for a different configuration. (See attached procedural excerpt) This is plausible in that leads are lifted to relays in this procedural sequence and valve control circuits are manipulated to off-normal conditions. This could just as easily have been performed to prevent closure of one of the Shutdown Cooling Isolation Valves; the 47 valve in this case, to keep the flowpath available (as the loop will be declared inoperable for LPCI anyway). Additionally, due to the availability of the ADHR System, this is a very infrequently performed procedure sequence; adding to the level of difficulty.

D CORRECT: (See attached) - the tap for Supplemental Fuel Pool Cooling suction ties in just before the 13. Part 2 correct - (see attached) because the tap is downstream of the 47 & 48 valve, a Shutdown Cooling Isolation signal would NOT cause a loss of suction path while in Supplemental Fuel Pool Cooling.

Justification: Requires Knowledge of the effect that a SHUTDOWN COOLING SYSTEM Isolation will have on Supplemental Fuel Pool Cooling. Adding to the level of difficulty, the availability of a primary cooling system (ADHR) yields the fact that this lineup is rarely used at BFN. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPL171.044 Rev. 17 (Attach if not previously provided) 3-OI-74 Rev. 95 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.044 V.B.3 / 10 / 19 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 206000 HPCI ------

Tier # 2 K2.02 (10CFR 55.41.7)

Group # 1 ------

Knowledge of electrical power supplies to the following:

System pumps: BWR-2,3,4 K/A # 206000K2.02 Importance Rating 2.8 ------

Proposed Question: # 31 Which ONE of the following completes the statement?

The power supply to the Unit 2 HPCI Aux Oil Pump is ________.

A. 250 VDC RMOV BD 2A.

B. 250 VDC RMOV BD 2B.

C. 480 VAC RMOV BD 2A.

D. 480 VAC RMOV BD 2B.

Proposed Answer: A Explanation A CORRECT: 250 VDC RMOV BD 2A is the power supply to the HPCI Aux (Optional): Oil Pump. See Attached Electrical Lineup Checklist.

B INCORRECT: This is, in fact a power supply to HPCI components; just not the Aux Oil Pump. Refer to attached PRESTARTUP REQUIREMENTS.

This is also a primary power supply to RCIC components.

C INCORRECT: This is, in fact a power supply to HPCI components; just not the Aux Oil Pump. Refer to attached PRESTARTUP REQUIREMENTS.

This is also a primary power supply to RCIC components.

D INCORRECT: This is, in fact a power supply to HPCI components; just not the Aux Oil Pump. Refer to attached PRESTARTUP REQUIREMENTS.

This is also a primary power supply to RCIC components.

RO Level Justification: Tests whether the candidate has knowledge of power supplies to HPCI components, including the HPCI Auxiliary Oil Pump. Level of difficulty is compounded by the similarities of HPCI and RCIC in conjunction with the complex electrical distribution system at BFN. HPCI is a Div II System with B Logic as the primary logic; but it comes from an A Board.

RCIC is the opposite - A Logic from a B Board. This often creates confusion between the power supplies for the two systems.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 2-OI-73, Rev. 83 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.1/7____________ (As available)

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

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 211000 SLC ------

Tier # 2 A3.01 (10CFR 55.41.7)

Group # 1 ------

Ability to monitor automatic operations of the STANDBY LIQUID CONTROL SYSTEM including: K/A # 211000A3.01

Pump discharge pressure: Plant-Specific Importance Rating 3.5 ------

Proposed Question: # 33 Unit 3 is executing 3-EOI-1, RPV Control, due to a Scram AND an ATWS. The Unit Operator (UO) initiates Standby Liquid Control (SLC) per 3-EOI Appendix-3A, SLC Injection. The following is observed TEN minutes later:

SLC Storage Tank Level is 79%

SLC Pump Discharge Pressure is 1100 psig and steady

Reactor Pressure is 1000 psig Based upon the ABOVE indications, which ONE of the following completes the statement?

The running SLC Pump is discharging __(1)__ AND the blue SQUIB VALVE A and B CONTINUITY lights, on Panel 3-9-5, are expected to be __(2)__ for this condition.

A. (1) to the Reactor Vessel (2) illuminated B. (1) to the Reactor Vessel (2) extinguished C. (1) through a Relief Valve (2) illuminated D. (1) through a Relief Valve (2) extinguished Proposed Answer: B Explanation A INCORRECT: First part correct - see B below. Second part incorrect in (Optional): that if the Squib Valves fire as intended, the blue continuity lights will be extinguished. In reality, for the blue continuity lights, either state is plausible.

B CORRECT: (See attached excerpts) Being a positive displacement pump, SLC Pump discharge pressure should be at or slightly higher than RPV pressure. Additionally, the tank level lowering at approximately 1% per minute supports injection to the RPV. If the Squib Valves fire as intended, the blue continuity lights will be extinguished. This fact is verified in 3-EOI Appendix 3A as a function of proper system operation.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet C INCORRECT: First part incorrect in that the SLC Relief Valve setpoint is 1425 psig + 75 psig. Thus, indicated pressure would be significantly higher if the Relief Valve was the discharge path. Also, indicated tank level would not lower if the Relief Valve was open; as the relief discharges back to the tank. The second part is also incorrect for same reason detailed in A above.

D INCORRECT: First part incorrect - see C above. Second part is correct, as detailed in B above.

RO Level Justification: Tests the candidates ability to monitor SLC System operations in reference to SLC Pump Discharge Pressure and relationship to injection along with tank level indications. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using specific knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.039, Rev. 16 (Attach if not previously provided) 3-EOI Appendix 3A, Rev. 1 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.3.e/f___________ (As available)

_V.B.5 / 6 ___________

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.039 Revision 16 Page 3 of 7 a) The total tank capacity is 4,901 gallons; however, the overflow is connected at the tank level corresponding to 4,850 gallons.

b) Normal storage tank level is 85.6% to 95.4%, which

provides 4150 to 4626 gallons of solution for injection into the reactor vessel.

c) Storage tank level is measured by an air bubbler Obj. V.B.3.g system, (supplied by control air) which senses the Obj. V.C.2.g amount of backpressure applied by the head of water in the tank.

d) The storage tank air sparger is:

(1) Supplied by service air.

(2) Used to mix the sodium pentaborate solution during initial storage tank filling and prior to routine sampling.

e) Storage tank heater:

(1) Heats storage tank water to 80° F for initial Obj. V.D.3.b sodium pentaborate solution mixing. Obj. V.E.3.b (2) Maintains the sodium pentaborate solution >10° Obj. V.B.3.c F above the solution saturation temperature. Obj. V.C.2.c (3) Controlled with the heater control in ON or AUTOMATIC position.

(a) In ON, the heater will stay on continuously.

(b) In AUTOMATIC, the heater will energize to maintain the solution at the temperature setpoint on the controller.

(c) If the tank heater is being controlled in ON or AUTOMATIC and the tank solution level lowers to 830 gallons, the heater will automatically cut off, to prevent possible damage from overheating.

(4) Powered from 480V Reactor Building Vent Obj. V.B.5.c Board. Obj. V.C.4.d (5) Installed in a dry well to allow heater removal without draining the tank.

f) Storage tank outlet strainer:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet PICTURE FROM UNIT 3 SIMULATOR FOR COMPARISON

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 209001 LPCS ------

Tier # 2 K1.08 (10CFR 55.41.7)

Group # 1 ------

Knowledge of the physical connections and/or cause-effect relationships between the LOW PRESSURE CORE SPRAY (LPCS) K/A # 209001K1.08 SYSTEM and the following:

A.C. electrical power Importance Rating 3.2 ------

Proposed Question: # 32 Unit 2 has experienced a LOCA with the following plant conditions:

Drywell Pressure is 3.5 psig and rising

Reactor Water Level is (-) 120 inches and lowering

Reactor Pressure is 105 psig and lowering

4kV Shutdown Board C is locked out Which ONE of the following predicts the total injection flowrate for the Loop 2 Core Spray Pumps? (Assume no operator actions)

A. 0 gpm.

B. 2400 gpm.

C. 6250 gpm.

D. 9100 gpm.

Proposed Answer: A Explanation A CORRECT: (See attached excerpts) Although RPV Level initiation of (-)

(Optional): 122 inches has not been reached, Core Spray should have auto-started on Drywell Pressure > 2.5 psig with Reactor Pressure < 450 psig. Each loop of Core Spray is designed to supply 6250 gpm against head of 105 psig. With 4 kV SD Board C locked out, CS Pump 2B is de-energized and CS Pump 2D is interlocked to not auto-start. System 2 CS flow would be 0 gpm under these conditions.

B INCORRECT: Value of 2400 gpm based on expected Min flow for Core Spray. If power loss had affected System 1 Inboard Injection Valve, Pumps would be running on Min Flow between 2200 gpm and 2600 gpm.

C INCORRECT: Plausibility based on impact of loss of 4kV Shutdown Board C. The power loss does not affect A and C Core Spray. Pump A is supplied from SD Board A and Pump C is supplied from SD Board B.

System 1 Inboard Injection Valve is power from 480 RMOV Shutdown Board 2A which is still energized by SD Board A D INCORRECT: Value of 9100 gpm is plausible and corresponds to expected flow for pump run out. For the identified plant conditions, Core Spray Pumps are not in a run out condition.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet RO Level Justification: Tests the candidates knowledge of Core Spray AC power supplies and the cause-effect relationship of losing an AC power board when initiation conditions are present.

This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using specific knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.045 Rev 15 (Attach if not previously provided) 2-OI-75, Rev. 95 Proposed references to be provided to applicants during examination: NONE Learning Objective: __V.B.2/3/4_________ (As available)

Question Source: Bank #

Modified Bank # HLT 0801 Q#16 (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet BANK QUESTION THAT WAS MODIFIED

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 212000 RPS ------

Tier # 2 A2.09 (10CFR 55.41.5)

Group # 1 ------

Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM (RPS); and (b) based on those predictions, K/A # 212000A2.09 use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

High containment/drywell pressure Importance Rating 4.1 Proposed Question: # 34 Unit 2 has inserted a manual Reactor Scram. Several control rods failed to insert on the scram.

Plant conditions are as follows:

Reactor Power is 3%

Reactor Pressure is 960 psig AND controlled by EHC

Drywell Pressure is 2.5 psig

Mode Switch is in Shutdown

SCRAM DISCH VOLUME HI LEVEL BYPASS Switch is in NORMAL

Reactor Water Level is (-) 55 inches NOTE: 2-EOI Appendix 1F - Manual Scram 2-EOI Appendix 2 - Defeating ARI Logic Trips Which ONE of the following is required to reset the Scram?

A. Install jumpers per 2-EOI Appendix 1F AND Reset ARI.

B. Install jumpers per 2-EOI Appendix 1F AND Defeat ARI per 2-EOI Appendix 2.

C. Manually insert control rods using the RMCS until APRM DOWNSCALE / OPRM INOP, (2-9-5A, Window 4) clears.

D. Place the SDV Hi Hi Wtr Trip Bypass Keylock Switch to BYPASS until EAST / WEST CRD DISCH VOL WTR LVL HIGH HALF SCRAM, (2-9-4A, Windows 1/29) clear.

Proposed Answer: B Explanation A INCORRECT: is incorrect because ARI must be inhibited or scram air (Optional): pressure will not recover to close the Scram valves, also the SDV vent and Drain valves must be closed.

B CORRECT: In accordance with EOI Appendix 1F, Manual Scram, Jumpers must be installed to defeat RPS Scrams, ARI Defeated per EOI Appendix 2, RPS Reset, then SDV Vent and Drain Valves verified closed.

C INCORRECT: is incorrect because clearing the APRM downscale annunciator will have no effect on the RPS system, the RPS trip in SHUTDOWN is set at 15%.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D INCORRECT: is incorrect because bypassing the SDV and draining the SDV will not allow RPS to be reset with a high drywell pressure and low reactor water level scram in.

Justification: Requires candidate to demonstrate ability to predict the impacts of High drywell pressure on the REACTOR PROTECTION SYSTEM (RPS); and based on those predictions, use EOI Appendix to correct the consequences of those abnormal conditions. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 2-EOI Appendix 1F Rev. 4 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: ___________________ (As available)

Question Source: Bank # Brunswick 07 #10 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Brunswick 2007 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 215003 IRM ------

Tier # 2 A4.04 (10CFR 55.41.7)

Group # 1 ------

Ability to manually operate and/or monitor in the control room:

IRM back panel switches, meters, and indicating lights K/A # 215003A4.04 Importance Rating 3.1 ------

Proposed Question: # 35 Given the following plant conditions:

Unit 3 Reactor startup preparations are in progress with NO rods withdrawn

Instrument Mechanics (IM) are performing the Intermediate Range Monitor (IRM)

Functional Surveillance

NO IRMs are currently bypassed

The IM has placed the "INOP / INHIBIT" toggle switch for the 'H' Channel IRM in the "INHIBIT" position Which ONE of the following describes the IRM trip function that is bypassed as a result of this action?

A. IRM "High Voltage Low" INOP TRIP.

B. IRM "Loss of +/- 24 VDC" INOP TRIP.

C. IRM "Module Unplugged" INOP TRIP.

D. IRM "Mode Switch Out of Operate" INOP TRIP.

Proposed Answer: D Explanation A INCORRECT: This INOP trip will still function. Each of the possible (Optional): answers will typically initiate an INOP trip of its associated IRM channel, therefore each distractor is plausible.

B INCORRECT: See explanation A C INCORRECT: See explanation A D CORRECT: INOP/INHIBIT Pushbuttons (toggle sw for Unit 3) are pushed/flipped to bypass the INOP trip that results from taking mode switch S-1 out of "OPERATE." They are used to allow testing of other scram or rod block signals from the IRM drawer into RPS/RMCS without them being masked by the INOP trip.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: This question satisfies the K/A statement by requiring the candidate to use specific component manipulations to correctly determine the response of the IRM system. Level of Knowledge Justification: This question is rated as MEM due to the requirement to recall or recognize discrete bits of information.

Technical Reference(s): OPL171.020 Rev. 11 (Attach if not previously provided) 3-OI-92A Rev. 15 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.020 V.B.5 / 7_ (As available)

Question Source: Bank # BFN 0610 #7 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam BFN 0610 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 215003 IRM ------

Tier # 2 A4.05 (10CFR 55.41.7)

Group # 1 ------

Ability to manually operate and/or monitor in the control room:

Trip bypasses K/A # 215003A4.05 Importance Rating 3.4 ------

Proposed Question: # 36 Unit 1 is in Mode 2 with the following conditions:

Source Range Monitor (SRM) A is reading 6.2 x 104 cps

SRM D mode switch (S-1) is in the STANDBY position

Intermediate Range Monitor (IRM) D is downscale on Range 1 (output has been lost)

IRM C is reading 85 of 125 scale on Range 8

ALL other IRMs are reading mid scale on Range 8 OR 9 Based on the above indications, which ONE of the following has caused a Rod Block signal to be generated?

A. IRM High.

B. SRM High.

C. IRM Downscale.

D. SRM Inoperable.

Proposed Answer: D Explanation A INCORRECT: IRM High Flux Rod Block Trip occurs at >104.6 on 125 (Optional): SCALE. Plausible in that reading is above level which IRM is required to be ranged up in accordance with 1-GOI-100-1A, but less than the Rod Block signal.

B INCORRECT: SRM A is elevated but below its High Flux Rod Block set point of 6.8 x 104 cps.

C INCORRECT: Loss of IRM detector output would result in a rod block based on IRM downscale. However, this trip is bypassed with Detector on Range 1.

D CORRECT: SRM B Mode Switch being placed in STANDBY will result in a SRM Inop alarm with a concurrent rod block. However, this function is bypassed with IRMs on Range 8. Since IRM D is on Range 1 due to the operability issue, the bypass logic is not made up.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: To successfully answer this question, candidate must recognize those conditions which will cause IRM / SRM Rod Block signals and when those trips are bypassed. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.020 Rev 11 / 1-OI-92A Rev 8 (Attach if not previously provided)

OPL171.019 Rev 13 / 1-OI-92 Rev 6 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.020 V.B.5 ___ (As available)

OPL171.019 V.B.5/V.B.8 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 215004 Source Range Monitor ------

Tier # 2 G2.2.2 (10CFR 55.41.7)

Group # 1 ------

Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. K/A # 215004G2.2.2 Importance Rating 4.6 ------

Proposed Question: # 37 A plant start up on Unit 3 is in progress. A control rod block has occurred. The following nuclear instrument indications are noted:

SRM A SRM B SRM C SRM D Position Full in Mid-position Mid-position Full in Counts (CPS) 9.5x103 95 80 8.0x103 IRM A IRM B IRM C IRM D IRM E IRM F IRM G IRM H 25/125 15/125 35/125 55/125 75/125 75/125 30/125 25/125 Range 3 Range 2 Range 3 Range 3 Range 2 Range 2 Range 3 Range 3 Which ONE of the following identifies the MINIMUM action needed to clear the ROD WITHDRAWAL BLOCK?

A. Insert SRM B ONLY B. Insert SRM B AND SRM C C. Range up on IRM B AND IRM F to range 3 D. Range up on IRM E AND IRM F to range 3 Proposed Answer: B Explanation A INCORRECT: Plausible in that with IRM C on range 3, candidate may (Optional): believe SRM C Detector Not Full In Rod Block is bypassed. However, with any associated IRM (A, C, E or G) not on range 3, the trip remains in force.

B CORRECT: SRM RETRACT NOT PERMITTED will alarm and cause a rod block with SRM counts <145cps with associated IRMs Range 2 and the Detector not Full In.

C INCORRECT: Plausible in that it would clear the Control Rod Block from SRM B. However, it would result in IRM B causing a rod block due to IRM downscale.

D INCORRECT: Plausible in that ranging up IRM E and F would not result in an IRM downscale rod block. However, a rod block would remain with IRM B still on range 2.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: Candidate must demonstrate ability to manipulate the console controls for SRMs as required to operate the facility between shutdown and designated power levels.

Technical Reference(s): 3-OI-92 Rev. 13 (Attach if not previously provided)

OPL171.019 Rev. 13 Proposed references to be provided to applicants during examination:

Learning Objective: OPL171.019 V.B.8____ (As available)

Question Source: Bank #

Modified Bank # Perry 09 #37 (Note changes or attach parent)

New Question History: Last NRC Exam Perry 2009 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet PERRY NRC EXAM - 2009 QUESTION RO 49 A plant start up is in progress. A control rod block has occurred. The following nuclear instrument indications are noted:

SRM A SRM B SRM C SRM D Position Full in Mid-position Mid-position Full in Counts (CPS) 9.5x104 95 80 8.0x104 IRM A IRM B IRM C IRM D IRM E IRM F IRM G IRM H 25/125 15/125 35/125 55/125 75/125 75/125 30/125 25/125 Range 3 Range 2 Range 3 Range 3 Range 2 Range 2 Range 3 Range 3 What is the minimum action needed to clear the ROD WITHDRAWAL BLOCK?

A. Only Insert SRM B B. Insert SRM B and SRM C C. Range up on IRM B & IRM F to range 3 D. Range up on IRM E & IRM F to range 3

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 215005 APRM / LPRM ------

Tier # 2 K4.01 (10CFR 55.41.7)

Group # 1 ------

Knowledge of AVERAGE POWER RANGE MONITOR / LOCAL POWER RANGE MONITOR (APRM / LPRM) SYSTEM design K/A # 215005K4.01 feature(s) and/or interlocks which provide for the following:

Rod withdrawal blocks Importance Rating 3.7 ------

Proposed Question: # 38 Unit 2 APRMs have the following indications:

APRM 1 - 106%

APRM 2 - 104%

APRM 3 - 104%

APRM 4 - 105%

Recirc Loop A flow 60%

Recirc Loop B flow 64%

Which ONE of the following identifies the expected plant response to these conditions?

A. Control Rod Withdrawal Block ONLY B. Half Scram AND Control Rod Withdrawal Block C. Full Scram AND Control Rod Withdrawal Block D. Flow Compare Inverse Video Alarm on ODA ONLY Proposed Answer: A Explanation A CORRECT: w = (60 + 64)/2 = 62%

(Optional): rod block setpoint = (.66(62) + 59) = 99.92%

scram setpoint = (.66(62) + 65) = 105.92%

All APRM channels are >the rod block set point.

B INCORRECT: ONLY APRM 1 is above the STP calculated upscale Scram set point of 105.92. PRNM system only provides half scrams during voter testing. Plausible in that typical RPS logic results in a half scram with one channel above the trip set point.

C INCORRECT: Only 1 channel is above the upscale set point. Requires 2 APRM inputs above setpoint (.66w + 65) to initiate a Full Reactor Scram.

D INCORRECT: Flow compare function looks for 5% mismatch between flows for same loop. Additionally, a Control Rod Withdrawal Block will occur with current conditions.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: Question requires knowledge of APRM design features and interlocks which provide Control Rod Withdrawal Blocks to successfully answer. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.148 Rev 12 (Attach if not previously provided) 2-OI-92C Rev. 34 2-OI-92B Rev. 38 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.148_V.B.31__ (As available)

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

New Question History: Last NRC Exam BFN 0606 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 217000 RCIC ------

Tier # 2 K6.04 (10CFR 55.41.7)

Group # 1 ------

Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR CORE ISOLATION COOLING SYSTEM K/A # 217000K6.04 (RCIC):

Condensate storage and transfer system Importance Rating 3.5 ------

Proposed Question: # 39 After a Reactor Scram on Unit 2, the following plant conditions exist:

Main Turbine Bypass Valves failed closed

HPCI AND RCIC have been MANUALLY started in CST to CST pressure control mode

Subsequently, Condensate Storage Tank (CST) level dropped to 6500 gallons Assuming NO operator action has been taken, which ONE of the following completes the statement?

RCIC is __(1)__ with suction from the __(2)__.

A. (1) operating at shutoff head (2) CST.

B. (1) operating in pressure control (2) CST.

C. (1) operating at shutoff head (2) Suppression Pool.

D. (1) pumping to the CST (2) Suppression Pool.

Proposed Answer: A Explanation A CORRECT: Part 1 correct - At ~7000 gallons in the CST, HPCI auto swaps (Optional): from CST suction to Suppression Pool (Torus) suction. When this occurs the CST Test Return Isolation valve, 2-FCV-73-36, receives a close signal from the Torus suction valves opening; to prevent pumping the Torus to the CST. RCIC uses the HPCI Test Return line for flow path to the CST with RCIC connecting upstream of 2-FCV-73-36. RCIC min flow valve will not open with the absence of an initiation signal. Part 2 correct - Normal standby lineup has RCIC suction aligned to the CST. RCIC does not have an automatic suction swap from CST to Suppression Pool.

B INCORRECT: Part 1 incorrect - plausible in that the isolation of the CST test return valves is in response to HPCI low CST suction swap. With RCIC not having a low CST suction swap, candidate may fail to recognize RCIC flow path is also affected. Part 2 correct as explained above.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet C INCORRECT: Part 1 correct as detailed in explanation A. Part 2 is incorrect but plausible in that HPCI does have automatic suction swap to the Suppression Pool with CST level < 7000 gallons.

D INCORRECT: Parts 1 and 2 incorrect but plausible as explained above.

Justification: This question satisfies the K/A statement by requiring the candidate to use specific plant conditions to determine the effect of low CST level on RCIC operation. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.040 Rev. 23 (Attach if not previously provided)

OPL171.042 Rev. 20 2-OI-71 Rev. 59 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.040 V.B.11 __ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 218000 ADS ------

Tier # 2 K4.02 (10CFR 55.41.7)

Group # 1 ------

Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) design feature(s) and/or interlocks which provide for the following: K/A # 218000K4.02

Allows manual initiation of ADS logic Importance Rating 3.8 ------

Proposed Question: # 40 A Recirculation Loop leak results in a Unit 2 Drywell Pressure of 2.5 psig.

Six minutes later, plant conditions are as follows:

Reactor Water Level is (-) 110 inches

Drywell Pressure is 5.1 psig

Core Spray Pumps 2A AND 2D are being manually started

NO other ECCS Pumps are available Which ONE of the following identifies the status of ADS?

A. ADS Valves will NOT Automatically actuate BUT can be opened MANUALLY.

B. ADS Valves will open IMMEDIATELY if Reactor Water Level reaches Level 1.

C. ADS Valves will open 95 seconds after the 2A AND 2D Core Spray Pumps started.

D. ADS Valves will open IMMEDIATELY after the 2A AND 2D Core Spray Pumps started.

Proposed Answer: A Explanation A CORRECT: Following conditions must be met before ADS Initiation will (Optional): occur: Two coincidental signals of High Drywell Pressure 2.45 psig and Reactor Level 1 (-) 122 inches or Reactor Level 1 (-) 122 inches for 265 seconds plus confirmatory low Reactor Level (+) 2 inches and any RHR Pump or either A or B and C or D Core Spray Pumps running. This answer is correct because the Level 1 initiation signal has not been satisfied.

B INCORRECT: This is incorrect because when level 1 is reached, the 95 second timer has to run out before ADS will initiate. Plausible if candidate thinks conditions already met for 95 second timer to start C INCORRECT: The 95 second time delay does not start until three indications are provided (reactor vessel (+) 2 inches, and reactor vessel

(-) 122 inches, and Drywell pressure 2.45 psig, or at or (-) 122 inches for 265 seconds. Plausible in that candidate may confuse Level 1 for 265 seconds with High Drywell Pressure for more than 265 seconds.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D INCORRECT: This is incorrect because although 1 RHR or 2 Core Spray pumps must be running, ADS will not initiate until RPV level reaches Level

1. Plausible in that candidate may confuse Level 1 for 265 seconds with High Drywell Pressure for more than 265 seconds and that conditions already met to start the 95 second timer.

Justification: To correctly answer this question, candidate must recognize condition not met for automatic initiation of ADS requiring manual operation of valves to initiate ADS. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.043 Rev 13 (Attach if not previously provided) 2-OI-1 Rev. 46 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.043_V.B.4___ (As available)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam BFN 0801 #40 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet BFN 0801 NRC #40 A Recirculation Loop leak results in Unit 2 Drywell Pressure of 2.5 psig.

Six minutes later, plant conditions are as follows:

Reactor water level is (-) 110 inches and lowering slowly

Drywell pressure is 5.1 psig A Unit Operator manually starts Core Spray Pumps 2A AND 2C.

Which ONE of the following identifies the status of ADS?

A. ADS 95-second timer is still reset (i.e., has NOT yet started).

B. ADS Valves will open IMMEDIATELY after the Core Spray Pumps starts.

C. ADS Valves are closed but will open 95 seconds after the Core Spray Pumps start.

D. ADS Valves are closed but will open IMMEDIATELY when Reactor Level reaches Level 1.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 218000 ADS ------

Tier # 2 K4.03 (10CFR 55.41.7)

Group # 1 ------

Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) design feature(s) and/or interlocks which provide for the following: K/A # 218000K4.03

ADS logic control Importance Rating 3.8 ------

Proposed Question: # 41 A small break LOCA has occurred on Unit 2 with a failure of ALL high pressure injection.

Conditions have deteriorated to the point of automatic initiation of ADS.

Which ONE of the following describes when the ADS Valves will close?

A. When Reactor Pressure drops to 150 psig.

B. When ALL Low Pressure ECCS Pumps are secured.

C. When Reactor Water Level rises above (-) 122 inches.

D. When Reactor Pressure lowers to 20 psig above Suppression Chamber Pressure.

Proposed Answer: D Explanation A INCORRECT: Reactor Pressure of 150 psig has no affect on ADS Logic.

(Optional): Plausible in that it is a recognizable value associated with ADS. ADS valves are not required to be OPERABLE with reactor steam dome pressure less than 150 psig.

B INCORRECT: The Low Pressure ECCS pumps need to be running to initiate ADS, but a seal in maintains initiation logic even if Low Pressure ECCS Pumps are removed from service. Plausible in that candidate may not recognize this portion of the logic is sealed in.

C INCORRECT: Level 1 (-122 inches) is required to initiate ADS, but a seal in maintains initiation logic even after Reactor Level rises above - 122 inches.

Plausible in that candidate may not recognize this portion of the logic is sealed in.

D CORRECT: ADS SRVs will auto close with a differential pressure < 20 psig.

Justification: Tests candidates knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) design feature(s) and interlocks which provide for ADS logic control.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPL171.009 Rev.11 (Attach if not previously provided)

QPL171.043 Rev. 13 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.009 V.B.2______ (As available)

OPL171.043 V.B.3______

Question Source: Bank # BFN 2004 #18 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam BFN 2004 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 223002 PCIS/Nuclear Steam Supply Shutoff ------

Tier # 2 K1.04 (10CFR 55.41.7)

Group # 1 ------

Knowledge of the physical connections and/or cause-effect relationships between the PRIMARY CONTAINMENT ISOLATION K/A # 223002K1.04 SYSTEM (PCIS) / NUCLEAR STEAM SUPPLY SHUT-OFF and the following:

High pressure coolant injection: Plant-Specific Importance Rating 3.5 Proposed Question: # 42 Which ONE of the following will result in a HPCI Group 4 Isolation on Unit 2?

A. Reactor Pressure of 108 psig.

B. HPCI Pump Room Temperature of 170º F.

C. HPCI Steam Line Flow at 150% of rated for 5 seconds.

D. HPCI Pressure between Exhaust Rupture Discs of 12 psig.

Proposed Answer: D Explanation A INCORRECT: This pressure would cause Group 4 Isolation on Unit 1 (Optional): ONLY. Unit 1 Reactor Pressure low pressure set point is 110 psig. Unit 2 Group 4 set point is 105 psig.

B INCORRECT: Pump Room Isolation Temperature is 185 º F. If Torus Area Temp > 165 º F a Group 4 Isolation will occur.

C INCORRECT: HPCI isolates on high steam line flow of 200% of rated for 3 seconds. This Steam Line flow rate is above Group 1 isolation of 135% and Group 4 time delay of 3 seconds is exceeded.

D CORRECT: HPCI High Pressure Between Rupture Discs of 10 psig results in a Group 4 Isolation.

Justification: Tests candidates knowledge of parameters and setpoints that will result in HPCI Isolation from the Primary Containment Isolation System.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 2-OI-73, Rev. 83 (Attach if not previously provided)

OPL171.042, Rev.20 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.042 V.B.2 ___ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 223002 PCIS/Nuclear Steam Supply Shutoff ------

Tier # 2 K1.08 (10CFR 55.41.7)

Group # 1 ------

Knowledge of the physical connections and/or cause-effect relationships between the PRIMARY CONTAINMENT ISOLATION K/A # 223002K1.08 SYSTEM (PCIS) / NUCLEAR STEAM SUPPLY SHUT-OFF and the following:

Shutdown cooling system/RHR Importance Rating 3.4 Proposed Question: # 43 Preparations are underway to place Unit 2 in Cold Shutdown following a Scram. When the operator started the 2B RHR Pump for Shutdown Cooling (SDC), Reactor Water Level lowered to 0 inches.

Which ONE of the following completes both of the following statements for using RHR Loop 1 LPCI to restore vessel level in accordance with 2-AOI-74-1, Loss of Shutdown Cooling?

The RHR SYS 1 SD CLG INBD INJECT ISOL RESET pushbutton, 2-XS-74-126, __(1)__ to be depressed.

Following the start of Loop 1 RHR Pump, the operator is required to open __(2)__.

A. (1) is required (2) RHR SYS I OUTBD INJECT VALVE, 2-FCV-74-52.

B. (1) is required (2) RHR SYS I INBD INJECT VALVE, 2-FCV-74-53.

C. (1) is NOT required (2) RHR SYS I OUTBD INJECT VALVE, 2-FCV-74-52.

D. (1) is NOT required (2) RHR SYS I INBD INJECT VALVE, 2-FCV-74-53.

Proposed Answer: B Explanation A INCORRECT: (See attached excerpts) Part 1 correct - A Group II Isolation (Optional): signal has been initiated at + 2 inches. Per 2-AOI-74-1, The RHR SYS 1 SD CLG INBD INJECT ISOL RESET pushbutton, 2-XS-74-126 is required to be depressed. Part 2 is incorrect 74-52 is unaffected by the isolation signal, but will need to be re-throttled following re-establishment of flow [5.2.4].

B CORRECT: (See attached excerpts) A Group II Isolation signal has been initiated at + 2 inches. Per 2-AOI-74-1, The RHR SYS 1 SD CLG INBD INJECT ISOL RESET pushbutton, 2-XS-74-126 is required to be depressed. 2-FCV-74-53 is affected by the isolation signal, and will need to be re-opened, [5.2.3].

C INCORRECT: Part 1 is incorrect as detailed in B above. Part 2 is incorrect as detailed in A above.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D INCORRECT: Part 1 is incorrect and part 2 is correct.

RO Level Justification: Tests the candidates knowledge of physical connections (logic) and cause-effect relationships between PCIS and the Shutdown Cooling Mode of RHR. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using specific knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 2-AOI-74-1, Rev. 33 (Attach if not previously provided) 2-OI-74, Rev. 150 OPL171.017, Rev. 15 OPL171.044, Rev. 17 Proposed references to be provided to applicants during examination: NONE Learning Objective: _OPL171.017 V.B.2.g_/ 4 __ (As available)

_OPL171.044 V.B.10 / 19___

Question Source: Bank # X 0801 # 30 Modified Bank # (Note changes or attach parent)

New Question History: HLT 0801 Last NRC Exam (7 / 2009)

(Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 239002 SRVs ------

Tier # 2 K2.01 (10CFR 55.41.7)

Group # 1 ------

Knowledge of electrical power supplies to the following:

SRV solenoids K/A # 239002K2.01 Importance Rating 2.8 ------

Proposed Question: # 44 Which ONE of the following completes the statements?

ALTERNATE electrical power for those Unit 3 Safety Relief Valve (SRV) Solenoids, where available, is supplied from 250 VDC __(1)__.

Upon experiencing undervoltage conditions on the normal power supply, the transfer to SRV Solenoid alternate power supplies __(2)__.

A. (1) RMOV Boards ONLY.

(2) occurs automatically.

B. (1) RMOV Boards ONLY.

(2) MUST be performed manually.

C. (1) RMOV Boards AND Battery Boards.

(2) occurs automatically.

D. (1) RMOV Boards AND Battery Boards.

(2) MUST be performed manually.

Proposed Answer: C Explanation A INCORRECT: First part incorrect. Second part correct- see C below. ALL (Optional): primary sources of power are from 250 VDC RMOV Boards, lending plausibility to the first part.

B INCORRECT: Both parts incorrect - see C below. During Control Room Abandonment (See attached 3-AOI-100-2 Excerpt), manual transfers associated with power supplies are necessary, lending plausibility.

C CORRECT: (See attached Lesson Plan excerpts) - Primary power supplies to SRVs are from ONLY 250 VDC RMOV Boards. Alternate power supplies are from BOTH 250 VDC RMOV AND Battery Boards.

Undervoltage relays, located in the Remote Shutdown Panels, will automatically transfer power supplies on a loss of normal voltage.

D INCORRECT: First part correct. Second part incorrect- see C above.

RO Level Justification: Tests whether the candidate has knowledge of power supplies to SRV solenoids and how those power supplies interrelate. Adding to the level of difficulty, these valves with alternate power supplies are utilized at the Remote Shutdown Panel; where a MANUAL transfer of power supplies to EMERGENCY is initiated. Additionally, normal power supplies are distributed among the three 250 VDC boards such that candidate may assume there is adequate time to manually transfer power, as the SRV LCO is predicated upon the Safety Mode only.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPL171.043, Rev. 13 (Attach if not previously provided)

OPL171.009, Rev. 11 3-AOI-100-2, Rev. 18 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.3/5____________ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 259002 Reactor Water Level Control ------

Tier # 2 G2.2.40 (10CFR 55.41.10)

Group # 1 ------

Ability to apply technical specifications for a system.

K/A # 259002G2.2.40 Importance Rating 3.4 ------

Proposed Question: # 45 The following conditions exist on Unit 1:

Reactor Power is 28%

NORMAL RANGE Level indicator, 1-LI-3-208D, is failed HIGH (> 60 inches)

The Unit Operator subsequently observes that NORMAL RANGE Level indicator, 1-LI-3-208A, is drifting upscale.

Which ONE of the following completes the statements?

Tech Spec 3.3.2.2, Feedwater and Main Turbine High Water Level Trip Instrumentation,

__(1)__ applicable for the current plant conditions.

If 1-LI-3-208A reaches FULL scale, the running RFPTs __(2)__ trip.

A. (1) is (2) will B. (1) is NOT (2) will C. (1) is (2) will NOT D. (1) is NOT (2) will NOT Proposed Answer: C Explanation A INCORRECT: Part 1 correct - See Explanation C. Part 2 incorrect - See (Optional): Explanation B.

B INCORRECT: Part 1 is incorrect - Plausible in that Reactor Power is less than 30%. Other Instrumentation TS associated with the Main Turbine are NOT applicable with Power < 30%. Example - Main Turbine Stop Valve Closure / Control Valve Fast Closure, TS 3.3.1.1. Part 2 incorrect -

Plausible in that with 2 channels upscale, candidate may believe conditions are met for Level 8 Reactor Feed Pump Trip.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet C CORRECT: Part 1 is correct - TS 3.3.2.2, Feedwater and Main Turbine High Water Level Trip Instrumentation is applicable with Reactor Power 25%. Part 2 is correct either 208A and 208C or 208B and 208D must be picked up to trip the RFPTs. Combination of A and D channels will not cause a trip.

D INCORRECT: Part 1 incorrect - See Explanation B. Part 2 correct - See Explanation C.

Justification: Question requires candidate to demonstrate ability to apply Tech Specs for Reactor Level Instrumentation by recognizing condition which the associated Tech Spec would be applicable. Per Tech Spec 3.3.2.2, feedwater and main turbine high water level trip instrumentation is designed to detect a potential failure of the Feedwater Level Control System that causes excessive feedwater flow. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.026 Rev. 14 (Attach if not previously provided)

OPL171.003 Rev. 19 U1 TS 3.3.2.2 Am 234 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.003 V.B.20___ (As available)

OPL171.026 V.B.5____

Question Source: Bank #

Modified Bank # 171.026 #3 (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.026 Revision 14 Page 3 of 7

a. The ELEC position of the OVERSPEED TEST OI-3 section 8.9 TRIP LOCKOUT switch removes electrical overspeed trip for testing. All other trips remain functional.

b. Amber light below tachometer on 9-6 and Unit difference locally will be lit when electrical overspeed condition is reached. (Unit 3 flashes, Unit 2 does not.)

c. Testing of the turbine stop valves is required but the high pressure stop valve can only be tested if the HP control valve is fully closed.

Depressing the pushbutton on 9-6 causes the valve to close until it reaches its fully closed position or the pushbutton is released.

d. The Low Pressure Stop Valve can be tested at any time. Depressing the pushbutton on 9-6 causes the valve to travel to the mid (50%)

position and remain until the pushbutton is released.

e. High Water Level Trip

1) High water level trip at 55 comes off of These are LS-3-208A, B, C, D. uncompensated indicators

2) Logic is such that it is 2-out-of-2 taken once. For example, in order for a full turbine trip to occur, either 208A and 208C or 208B and 208D must be picked up.

3) Trip Channel A is 208A & 208C; Trip Channel B is 208B & 208D.

4) Two sets of indicating lights (red & green) are installed on panel 9-5 and two reset switches. Normal condition - Green Light on; Trip condition - Red light on;

5) Ready to reset condition - Green & Red lights on

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

. OPL171.026 3 The following conditions exist on Unit 2:

100% Reactor Power

NORMAL RANGE Level indicator, 2-LI-3-208D, is failed high (>60 inches)

The Unit Operator subsequently observes that NORMAL RANGE Level indicator, 2-LI-3-208A, is drifting upscale.

Which ONE of the following describes what action(s), if any, would occur should 2-LI-3-208A reaches full scale?

A. NO trip action would occur.

B. ONLY the Main Turbine would trip.

C. ONLY the running RFPTs would trip.

D. The running RFPTs AND Main Turbine would trip.

ANSWER: A

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 261000 SGTS ------

Tier # 2 A1.01 (10CFR 55.41.5)

Group # 1 ------

Ability to predict and/or monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM (SGTS) K/A # 261000A1.01 controls including:

System flow Importance Rating 2.9 ------

Proposed Question: # 46 Which ONE of the following completes the statements?

Following automatic initiation, Standby Gas Treatment System (SGTS) flow to STACK can be monitored in __(1)__ .

SGTS is designed such that a MINIMUM of__(2)__ SGTS Subsystem(s) can maintain a negative 1/4-inch of H20 vacuum in Secondary Containment with a MAXIMUM inleakage flow of 12,000 scfm.

A. (1) Unit 1 Control Room ONLY (2) ONE B. (1) ALL 3 Control Rooms (2) ONE C. (1) Unit 1 Control Room ONLY (2) TWO D. (1) ALL 3 Control Rooms (2) TWO Proposed Answer: D Explanation A INCORRECT: Part 1 incorrect - Plausible in that some SGTS indications (Optional): are available in ALL 3 Control Rooms and some are not. Additionally, per 0-OI-65, Standby Gas Treatment System, Precautions and Limitations, it is recommended that the trains be started from the Units 1 and 2 Control Rooms due in part to the availability of instrumentation. Part 2 incorrect -

SGT System is designed such that two subsystems are required to perform SGT Design Function. Plausible in that EOI App 12 only requires at least one SGTS running for CTMT Venting.

B INCORRECT: Part 1 correct - See Explanation D. Part 1 incorrect - See Explanation A.

C INCORRECT: Part 1 incorrect - See Explanation A. Part 1 correct - See Explanation D.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D CORRECT: Part 1 correct - SGTS Total Flow is determined by taking sum of Flow to Stack Indicators 0-FI-65-50B/1(2)(3) and 0-FI-65-71B/1(2)(3).

Indicators are located on Panels 1-9-20(Unit 1), 2-9-20(Unit 2), and 3 20(Unit 3). Part 2 correct - Upon a secondary containment isolation, the SGT System is designed such that two subsystems maintain a negative 1/4-inch of H20 vacuum in Secondary Containment with an inleakage flow of 12,000 scfm.

Justification: Question tests candidates Ability to monitor changes in system flow associated with operating the STANDBY GAS TREATMENT SYSTEM (SGTS).

Technical Reference(s): O-OI-65 Rev. 52 (Attach if not previously provided)

OPL171.018 Rev. 10 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.018 V.B.1___ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 262001 AC Electrical Distribution ------

Tier # 2 K5.02 (10CFR 55.41.5)

Group # 1 ------

Knowledge of the operational implications of the following concepts as they apply to A.C. ELECTRICAL DISTRIBUTION: K/A # 262001K5.02

Breaker control Importance Rating 2.6 ------

Proposed Question: # 47 A 4 kV breaker was racked in following maintenance on its associated pump. The breaker was then closed. Thirty minutes later, the breaker experiences a loss of DC Control Power.

Which ONE of the following completes the statement for the loss of DC Control Power?

The breaker __(1)__ AND __(2)__.

A. (1) will trip OPEN on power loss (2) CAN be closed LOCALLY at least once if it becomes necessary.

B. (1) will trip OPEN on power loss (2) CANNOT be operated LOCALLY, even if it becomes necessary.

C. (1) CANNOT be operated remotely (2) CAN be closed LOCALLY at least once if it becomes necessary.

D. (1) CANNOT be operated remotely (2) CANNOT be operated LOCALLY, even if it becomes necessary.

Proposed Answer: C Explanation A INCORRECT: Breakers do not trip open on loss of control power. Second (Optional): part is correct.

B INCORRECT: Breakers do not trip open on loss of control power. Local tripping and one closing locally are available.

C CORRECT: No remote operation is available when control power is lost, but local tripping is always available. When the breaker was closed prior to the loss of control power, the charging motor energized to charge the springs, so even after control power was lost, the springs were charged and available for one subsequent closure, if attempted.

D INCORRECT: First part correct - See C above. Second part incorrect since breaker can be opened one time locally.

RO Level Justification: Candidate must recognize operational implications of loss of control power on 4 kV breaker operations to successfully answer this question. This question is rated as MEM based upon requiring the recalling of facts.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPL171.036 Rev. 12 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: (As available)

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

New Question History: Last NRC Exam River Bend 08 #46 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 262002 UPS (AC/DC) ------

Tier # 2 K3.08 (10CFR 55.41.7)

Group # 1 ------

Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.)will have on the K/A # 262002K3.08 following:

Computer operation: Plant-Specific Importance Rating 2.7 ------

Proposed Question: # 48 Which ONE of the following completes the statements?

The Unit 2 AND Unit 3 Integrated Computer Systems (ICS) are fed from __(1)__ inverter(s).

If normal power (inverter output) is lost, the Unit 2 AND 3 ICS swap to alternate __(2)__.

A. (1) a common (2) without interruption B. (1) separate (2) without interruption C. (1) a common (2) after a 5 second time delay D. (1) separate (2) after a 5 second time delay Proposed Answer: B Explanation A INCORRECT: Part 1 incorrect - Unit 2 AND 3 ICS are supplied from (Optional): separate inverters. Plausible in that the power supplies for Units 2 & 3 are at the same location - U3 Turbine Bldg Elev. 565 (Room at the east end).

Additionally, there are multiple systems, components, and functions shared between Units throughout the site. Part 2 correct - See explanation B.

B CORRECT: Part 1 correct - Unit 2 UPS Inverter AC supply is 480V Common Bd 2, Comp 9A and DC supply is Batt Bd 4, Bkr 316. Unit 3 UPS Inverter AC supply is480V Common Bd 3, Compt 8B and DC Supply is Batt Bd 6, Bkr. 316. The UPS consists of an inverter/rectifier and a regulating transformer. The UPS feeds a distribution panel from which the ICS computers are fed. Part 2 correct - Power Supply for Units 1, 2 and 3 ICS Computers is from an uninterruptible power supply (UPS). Upon loss of the normal AC power to the rectifier, the DC source will provide power to the Inverter. A static switch (throw over) is provided such that if power from the inverter is interrupted, it will switch to the regulating transformer.

C INCORRECT: Part 1 incorrect - See explanation A. Part 2 incorrect - The 5 second time delay is plausible in that on a loss of 120 VAC I&C Buses, the transfer switch operates after a 5 second time delay. The time delay transfer allows for momentary outages.

D INCORRECT: Part 1 correct - See explanation B. Part 2 incorrect - See explanation C.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: Requires knowledge of ICS Power Supplies including effect of loss of normal power supply on ICS to correctly answer the question.

Technical Reference(s): OPL171.099 Rev. 9 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.099 V.B.1a___ (As available)

Question Source: Bank #

Modified Bank # OPL171.099 04 (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet I&C Power System:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Browns Ferry Operations Bank OPL171.099 04 Which of the following describes the power supplies for the Unit 2 and Unit 3 ICS Computers?

A. Unit 2 and Unit 3 ICS Computers are both powered from one uninterruptible power supply inverter.

B. Unit 2 and Unit 3 ICS Computers are each powered by their own separate uninterruptible power supply inverter.

C. Unit 2 ICS is fed by an uninterruptible power supply inverter, while Unit 3 is fed by Battery Board 1.

D. Unit 3 ICS is fed by an uninterruptible power supply inverter, while Unit 2 is fed by Battery Board 1.

ANSWER: B

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 263000 DC Electrical Distribution ------

Tier # 2 A2.02 (10CFR 55.41.5)

Group # 1 ------

Ability to (a) predict the impacts of the following on the D.C.

ELECTRICAL DISTRIBUTION SYSTEM; and (b) based on those K/A # 263000A2.02 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Loss of ventilation during charging Importance Rating 2.6 Proposed Question: # 49 Which ONE of the following completes the statements relating to Plant/Station Battery Room HVAC Systems?

If these systems are NOT operating properly, the concern is that __(1)__.

Because of this, provisions are provided in plant procedures to utilize __(2)__.

A. (1) lead-calcium batteries tend to release toxic gas into the atmosphere at temperatures above 90 ºF.

(2) an Emergency Exhaust Fan ONLY.

B. (1) the design limit for hydrogen concentration in the rooms may be reached during battery charging operations.

(2) an Emergency Exhaust Fan ONLY.

C. (1) lead-calcium batteries tend to release toxic gas into the atmosphere at temperatures above 90 ºF.

(2) an Emergency Exhaust Fan AND/OR Portable Temporary Ventilation Equipment.

D. (1) the design limit for hydrogen concentration in the rooms may be reached during battery charging operations.

(2) an Emergency Exhaust Fan AND/OR Portable Temporary Ventilation Equipment.

Proposed Answer: D Explanation A INCORRECT: Lead-calcium batteries suffer degraded performance at high (Optional): temperatures but do not release toxic gas as a result. (See Attached Excerpts) An Emergency Exhaust Fan is provided with operating instructions provided in Section 5.12 of 0-OI-31. But, there is another option provided in addition to the Emergency Exhaust Fan; which is portable temporary ventilation provided in Section 8.15 of 0-OI-31.

B INCORRECT: (See Attached Excerpts) First part correct in that hydrogen buildup to explosive levels is the concern. Second part incorrect as detailed in A above.

C INCORRECT: First part incorrect as detailed in A above. (See Attached Excerpts) Second part is correct in that an Emergency Exhaust Fan is provided with operating instructions provided in Section 5.12 of 0-OI-31.

AND operation / placement of portable temporary ventilation provided in Section 8.15 of 0-OI-31.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D CORRECT: First part correct in that hydrogen buildup to explosive levels is the concern. Second part is correct in that an Emergency Exhaust Fan is provided with operating instructions provided in Section 5.12 of 0-OI-31.

AND operation / placement of portable temporary ventilation provided in Section 8.15 of 0-OI-31.

RO Level Justification: Tests the candidates knowledge of the impacts of a loss / malfunction of ventilation during charging activities on the batteries. In addition, procedurally-directed strategies that are available in the event of that loss/malfunction are tested. This question is rated as MEMORY as it requires a recall of facts.

Technical Reference(s): 0-OI-31, Rev. 136 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: ___________________ (As available)

Question Source: Bank #

Modified Bank # HLT 0707 Q # 23 (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet HLT 0707 NRC EXAM Question 23

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 264000 EDGs ------

Tier # 2 A3.02 (10CFR 55.41.7)

Group # 1 ------

Ability to monitor automatic operations of the EMERGENCY GENERATORS (DIESEL / JET) including: K/A # 264000A3.02

Minimum time for load pickup Importance Rating 3.1 ------

Proposed Question: # 50 Which ONE of the following completes the statement in accordance with Tech Spec 3.8.1, AC Sources - Operating?

On a Loss of Offsite Power, simultaneous with an ECCS initiation signal on Unit 1, the MAXIMUM allowed time for Emergency Diesel Generators to energize their associated Shutdown Boards is ____ seconds.

A. 4 B. 7 C. 10 D. 14 Proposed Answer: C Explanation A INCORRECT: Recognizable value for D/G Air Start Sequence - If the (Optional): engine fails to achieve 125 rpm in 4 seconds after start signal, this is a failure to start and the air starting motors shutdown.

B INCORRECT: Recognizable as the time second group of auto-connected loads is sequenced following D/G output breaker closing on DGVA sequencing.

C CORRECT: Per TS 3.8.1, On an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ECCS initiation signal, DG must auto-starts from standby condition and energize permanently connected loads in 10 seconds.

D INCORRECT: Recognizable as the time third group of auto-connected loads is sequenced following D/G output breaker closing on DGVA sequencing.

Justification: To demonstrate the ability to monitor automatic operation of D/G following Loss of Offsite Power in conjunction with an ECCS initiation signal, candidate must know the minimum time required to energize permanently connected loads. Question requires knowledge of bases for TS 3.8.1 LCO statement (above the line) and is therefore an RO question.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPL171.038, Rev. 17 (Attach if not previously provided)

U1 TS 3.8.1 Am 235 U1 TS BASES 3.8.1 Rev. 52 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.038 V.B.1 _ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 264000 EDGs ------

Tier # 2 A3.04 (10CFR 55.41.7)

Group # 1 ------

Ability to monitor automatic operations of the EMERGENCY GENERATORS (DIESEL / JET) including: K/A # 264000A3.04

Operation of the governor control system on frequency and voltage control Importance Rating 3.1 ------

Proposed Question: # 51 Emergency Diesel Generator (DG) 3EA was started for its Monthly Load Test Surveillance.

Which ONE of the following will occur if the DGs output breaker is closed with the DG Mode Selector Switch in the UNITS IN PARALLEL position?

A. The zero droop governor advances the fuel supply to the diesel to raise output frequency to the governors setpoint. This will cause the DG Output Breaker to trip on overload.

B. The speed regulator lowers the fuel supply to the diesel to lower output voltage to the governors setpoint. The will cause the DG Output Breaker to trip on undervoltage.

C. The zero droop governor advances the fuel supply to the diesel to raise output frequency to the governors setpoint. This will cause the DG to trip on overspeed.

D. The speed regulator lowers the fuel supply to the diesel to lower output voltage to the governors setpoint. This will cause the DG Output Breaker to trip on reverse power.

Proposed Answer: A Explanation A CORRECT: The speed regulator senses output frequency, but now the (Optional): generator output frequency is fixed by the other loads on the grid. If the diesel speed setpoint is higher than grid frequency, the zero droop governor will keep advancing the fuel supply to the diesel in order to try and raise grid/DG output frequency to the governors setpoint. This will cause the diesel to overload. (495 amps.)

B INCORRECT: First part is incorrect. With DG Mode Selector Switch in the UNITS IN PARALLEL position, DG is in Zero Droop Operation. Second part incorrect.

C INCORRECT: First part is correct but second part is incorrect. Grid will maintain DG speed at Grid frequency.

D INCORRECT: Both parts are incorrect as explained above.

Justification: Requires knowledge of how D/G responds in UNITS IN PARALLEL Mode to demonstrate ability to monitor D/G automatic operation.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPL171.038 Rev. 17 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.038 V.B.6_ __ (As available)

Question Source: Bank # OPL171.038 #1 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 300000 Instrument Air ------

Tier # 2 A4.01 (10CFR 55.41.7)

Group # 1 ------

Ability to manually operate and/or monitor in the control room:

Pressure gauges K/A # 300000A4.01 Importance Rating 2.6 ------

Proposed Question: # 52 Unit 2 is at 100% Reactor Power when a Control Air leak results in the following indication:

Based upon the ABOVE indications, which ONE of the following is correct?

A. SERVICE AIR XTIE VLV, 0-FCV-33-1, is CLOSED.

B. CONDENSATE DEMIN BYPASS VALVE, 1-FCV-2-130, is OPEN.

C. Unit 2 OUTBOARD MAIN STEAM ISOLATION VALVES are CLOSED.

D. Unit 2 to Unit 3 CONTROL AIR CROSSTIE, 2-PCV-032-3901, is CLOSED.

Proposed Answer: D Explanation A INCORRECT: SERVICE AIR XTIE VLV 0-FCV-33-1 opens at Control Air (Optional): System Pressure of 85 psig. Plausible in that this valve has both an automatic opening and automatic closing function associated with degraded Control Air Pressure. Current reading of 62 psig is less than automatic opening set point and greater than the automatic re-closing set point of 30 psig.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet B INCORRECT: CONDENSATE DEMIN BYPASS VALVE, 1-FCV-2-130 fails open with Control Air Pressure less than 50 psig. Plausible in that this valve will fail open with degraded Control Air Pressure which has not yet been reached.

C INCORRECT: Main Steam Isolation Valves close with Control Air System Pressure of 45 psig. Plausible in that the MSIVs will fail closed with degraded Control Air Pressure which has not yet been reached.

D CORRECT: Unit 2 to Unit 3 Crosstie Valve 2-PCV-032-3901 closes with Control Air Pressure less than 65 psig and will not re-open until Control Air Pressure is 85 psig.

Justification: Tests for required knowledge to demonstrate ability to monitor Control Air Pressure Gauges in the control room. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 0-OI-32 Rev. 125 (Attach if not previously provided)

OPL171.054 Rev. 14 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.054 V.B.3____ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.054 Revision 13 (Typo in Lesson Plan. This is actually in Rev. 14)

Appendix C Page 60 of 73

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet PICTURE FROM SIMULATOR FOR COMPARISON

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 400000 Component Cooling Water ------

Tier # 2 K6.05 (10CFR 55.41.7)

Group # 1 ------

Knowledge of the effect that a loss or malfunction of the following will have on the CCWS: K/A # 400000K6.05

Pumps Importance Rating 3.0 ------

Proposed Question: # 53 The 4KV Shutdown Board A is being fed from its Diesel Generator.

With RHR Service Water (RHRSW) Pump A1 aligned to Emergency Equipment Cooling Water (EECW), Reactor Water Level subsequently drops to (-) 122 inches.

Which ONE of the following completes the statement?

RHRSW Pump A1 will __________.

A. NOT trip.

B. trip AND NOT restart.

C. trip AND then restart after 14 seconds.

D. trip AND then restart after 28 seconds.

Proposed Answer: C Explanation A INCORRECT: The shutdown boards will load shed their respective EECW (Optional): loads when a shutdown board undervoltage condition exists or a LOCA signal in conjunction with a loss of offsite power is received.

B INCORRECT: A1 EECW Pump will trip but second part is incorrect as explained in C.

C CORRECT: Under normal conditions, a Common Accident Signal - Low Low Low Reactor water level will auto trip the Diesel Generator output breaker. With the "A" 4KV Shutdown Board being fed from its diesel generator, the breaker trip results in "A" 4KV S/D Bd Undervoltage. The shutdown boards will load shed their respective EECW loads when a shutdown board undervoltage condition exists or a LOCA signal in conjunction with a loss of offsite power is received. When any EECW pump receives an automatic start signal, it will start after a 14 second time delay if its 4kV shutdown board is being fed from its diesel generator.

D INCORRECT: When any EECW pump receives an automatic start signal, it will start after a 28 second time delay if normal voltage is available to its 4kV shutdown board. Normal voltage is not available in this case.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: Question tests candidates knowledge of effect of loss of EECW pump following Common Accident Signal on the EECW system. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome.

This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.051 Rev. 16 (Attach if not previously provided) 0-OI-67 Rev. 89 OPL171.038 Rev. 17 0-OI-82 Rev. 106 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.051 V.B.9____ (As available)

Question Source: Bank # OPL171.051-27 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL.171.051 Revision 16 Page 3 of 10 (1) The signals that start the A3 and C3 pumps and the B3 and D3 pumps also start the B1 and D1 pumps and the A1 and C1 pumps, respectively. One pump should be valved into EECW header service and off RHRSW header service and the pump started at any time that a normally assigned EECW pump is out of service.

Pump Out Valve In Of Service and Start A3 A1 B3 B1 C3 C1 D3 D1 (2) RHRSW/EECW pumps A3, B3, C3 and Obj. V.B.8 D3 (A1, B1, C1 and D1, if aligned) auto Obj. V.C.6 start as follows: Obj. V.D.6 Obj. V.E.11

common accident signal of 2.45 psig DW pressure with 450 psig Rx pressure, OR

common accident signal of -122" vessel level (Level 1) is received, OR

low RCW header pressure is sensed at the Control Air compressors (<30 psig), OR

low RCW header pressure is sensed at the RBCCW heat exchangers (<15 psig).

(3) RHRSW/EECW pumps B3, D3 (A1, C1 Pumps fed from if aligned) will auto start as follows: Unit 1 & 2.

when any Unit 1 or 2 Core Spray Obj. V.B.8/V.B.9 pump starts, OR Obj. V.C.6/V.C.7

any Unit 1 or 2 EDG start Obj. V.D.7

(> 125 RPM).

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL.171.051 Revision 16 Page 4 of 10 (4) RHRSW/EECW pumps A3, C3 (B1, D1 if aligned) will auto start as follows: Obj. V.E.12/V.D.7

when any Unit 3 Core Spray Pumps fed from pump starts, OR Unit 3

any Unit 3 EDG start

(> 125 RPM).

(5) The preferred alternate pump for any of the A3 - D3 pumps WILL NOT auto start on the same unit CS pump start or DG start signal as the primary pump therefore an alternate pump must be running to maintain EECW operability.

(6) When any EECW pump receives an Obj. V.B.9 automatic start signal, it will start after a Obj. V.C.7 28 second time delay if normal voltage is available to its 4kV shutdown board.

If its 4kV shutdown board is being fed from its diesel generator it will start after a 14 second time delay. (These pump start time delays are board specific)

E. Chlorination of EECW Piping

1. Hypochlorite addition for EECW system helps prevent Obj.V.B.4.h the accumulation of Asiatic clams in its piping as well as heat exchangers that it serves. The Calgon Company has been awarded and is assigned chemistry control for all raw water systems at BFN.

2. **NRC Generic Letter 89-13 and SOER 84-1 express **SOER 84-001 the significance of bio-fouling in raw water system heat exchangers for safety systems. Should the chlorination fail to prevent asiatic clam infestations, Plant/industry heat exchanger fouling could cause multiple failures experience of emergency equipment to meet their design criteria.

Operators should be aware that mechanical [NCO-90-002-005]

maintenance and Chemistry will be monitoring the system for biofouling/fouling. If one heat exchanger shows evidence of fouling, the operator should highly suspect fouling in redundant safety system components and take appropriate actions to see that those redundant components are tested. Biofouling has caused inoperable EECW heat exchangers on the Diesel Generators and the RHR seal heat exchangers at BFNP.

F. Chemistry Control

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.051 27 The A 4KV Shutdown Board is being fed from its Diesel Generator and ALL other Shutdown Boards are powered from their NORMAL power supplies.

Which ONE of the following completes the statement?

With the A1 RHRSW Pump aligned to EECW, AND Reactor Water Level subsequently drops to (-)122 inches, A1 RHRSW Pump would __________.

A. NOT trip.

B. trip AND NOT restart.

C. trip AND then restart after 14 seconds.

D. trip AND then restart after 28 seconds.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 201002 RMCS ------

Tier # 2 A2.04 (10CFR 55.41.5)

Group # 2 ------

Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, K/A # 201002A2.04 use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Control rod block Importance Rating 3.2 Proposed Question: # 54 Unit 3 is at 88% Reactor Power with the Control Rod Exercise Test for Withdrawn Control Rods, 3-SR-3.1.3.3, in progress when the following indications are received:

APRM DOWNSCALE / OPRM INOP, (3-9-5A, Window 4) is in alarm

APRM 1 indicates 0%

Which ONE of the following completes the statement?

This condition will result in a Control Rod __(1)__ requiring __(2)__ to continue the surveillance.

A. (1) withdrawal block ONLY (2) bypassing APRM 1 B. (1) withdrawal block ONLY (2) placing APRM 1 Mode Switch to INOP C. (1) withdrawal AND insert block (2) bypassing APRM 1 D. (1) withdrawal AND insert block (2) placing APRM 1 Mode Switch to INOP Proposed Answer: A Explanation A CORRECT: Part 1 Correct - APRM Downscale will result in a Control Rod (Optional): withdrawal block ONLY with Mode Switch in RUN. Part 2 Correct - In accordance with 3-ARP-9-5A, IF APRM failed downscale, THEN BYPASS channel. REFER TO 3-OI-92B.

B INCORRECT: Part 1 Correct. Part 2 Incorrect - Removing APRM Mode Switch from OPER position will result in a trip signal. Plausible in that the APRM is Inoperable.

C INCORRECT: Part 1 Incorrect - A Control Rod insert block signal will not be generated from an APRM downscale. Plausible in that various RMCS signals do result in a Control Rod insert block signal. Part 2 Correct.

D INCORRECT: Parts 1 and 2 incorrect as explained above.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: To answer this question, candidate must recognize impact of APRM Downscale on RMCS and identify actions required to correct the abnormal condition to resume Control Rod movement. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 3-ARP-9-5A Rev. 40 (Attach if not previously provided)

OPL171.029 Rev. 13 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.029 V.B.7____ (As available)

OPL171.148 V.B.13___

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam La Salle 08 #34 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 215002 RBM ------

Tier # 2 A3.04 (10CFR 55.41.7)

Group # 2 ------

Ability to monitor automatic operations of the ROD BLOCK MONITOR SYSTEM including: K/A # 215002A3.04

Verification of proper functioning / operability: BWR-3,4,5 Importance Rating 3.6 ------

Proposed Question: # 55 Unit 2 is at 75% Reactor Power with a Control Rod sequence exchange in progress when the following alarm is received:

RBM HIGH / INOP, (2-9-5A, Window 24)

Which ONE of the following completes the statement?

The setpoint for this annunciator is __(1)__ AND the power level displayed on the RBM recorder is determined using the mid-level LPRMs AND __(2)__level LPRMs.

A. (1) 117%

(2) A B. (1) 117%

(2) D C. (1) 121.8%

(2) A D. (1) 121.8%

(2) D Proposed Answer: B Explanation A CORRECT: Part 1 correct - See explanation B. Part 2 incorrect - The (Optional): RBM does not use any input from the A level LPRMS.

B CORRECT: Part 1 correct - The RBM High alarm set point is 117% with STP at 60% to 80%. Part 2 correct - The A RBM channel selects two B level and two D level LPRMS, as well as all 4 C level LPRMs. The B RBM channel selects the remaining two B and D level LPRMs and all four C level LPRMs.

C INCORRECT: Part 1 incorrect - 121.8 % is the set point for 25% to 60%

STP. Part 2 incorrect as explained in A.

D INCORRECT: Part 1 incorrect as explained above. Part 2 correct as explained above.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: To demonstrate ability to monitor automatic operation of the Rod Block Monitor, candidate must know trip set points at various power levels.

Technical Reference(s): OPL171.148 Rev. 12 (Attach if not previously provided) 1-ARP-9-5A Rev. 13 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.148 V.B.23/26 (As available)

Question Source: Bank # X (Hatch 09 Audit)

Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet HATCH 2009 Audit

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 216000 Nuclear Boiler Inst. ------

Tier # 2 A1.02 (10CFR 55.41.5)

Group # 2 ------

Ability to predict and/or monitor changes in parameters associated with operating the NUCLEAR BOILER INSTRUMENTATION K/A # 216000A1.02 controls including:

Removing or returning a (sensor) transmitter to service Importance Rating 2.9 ------

Proposed Question: # 56 Unit 1 is at 100% Reactor Power. Normal Range Level Transmitter, 1-LT-3-60 is removed from service for maintenance with its input to Feedwater Level Control (FWLC) System bypassed.

During retest of 1-LT-3-60, Instrument Mechanics inadvertently equalize the Normal Range Level Transmitter, 1-LT-3-53.

Which ONE of the following completes the statement?

Indicated Reactor Water Level on Panel 1-9-5 RX WTR LEVEL NORMAL RANGE, 1-LI-3-53 will be __(1)__ AND the input into the FWLC System from 1-LT-3-53 __(2)__ be automatically bypassed.

A. (1) downscale (2) will B. (1) downscale (2) will NOT C. (1) upscale (2) will D. (1) upscale (2) will NOT Proposed Answer: C Explanation A INCORRECT: Part 1 incorrect - With variable and reference leg pressures (Optional): equalized, instrument will indicate upscale not downscale. Part 2 correct -

See explanation C B INCORRECT: Part 1 incorrect as explained above. Part 2 is incorrect -

Plausible in that with one channel already bypassed in FWLC, candidate may believe a second channel removed from service will not result in automatically bypassing its input. If two level signals are BAD or invalid, the algorithm will average the remaining two levels and will control on that value. In this instance the two remaining signals are compared to each other. If they deviate by more than 8 inches, a process alarm will be generated, but neither will be declared invalid.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet C CORRECT: Part 1 correct - The lower the sensed pressure difference the higher the indicated level (Pref - Pvar = P). With variable and reference leg pressures equalized the pressure difference will be 0 and the instrument will indicate upscale. Part 2 correct - The RFW Control System will use a level signal provided the system determines the signal to be good and valid.

A GOOD level signal is one that has NOT failed and is on scale. A VALID level signal is one that does NOT deviate from the average (or median) level by more than 8 inches. When the RFWCS declares a level signal bad or invalid, then the level instrument is automatically bypassed.

D INCORRECT: Part 1 correct as explained in C. Part 2 incorrect as explained in B.

Justification: Required ability to predict affect on Level Indication and FWLC if a Normal Range Level Channel is inadvertently removed from service with another Normal Range Level Channel already out of service.

Technical Reference(s): OPL171.003 Rev. 19 / 1-OI-3 Rev. 22 (Attach if not previously provided)

OPL171.012 Rev. 13 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.003 V.B.1/V.B.11 (As available)

OPL171.012 V.B.6 ___

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Susquehanna 08 Last NRC Exam #34 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.012 Page 4 of 7 Revision 13

h. If two level signals are BAD or invalid, the algorithm will average the remaining two levels and will control on that value. In this instance the two remaining signals are compared to each other. If they deviate by more than 8 inches, a process alarm will be generated, but neither will be declared invalid.

i. If three level signals are BAD or invalid, the algorithm will control on the remaining signal alone.

j. If all four level signals are BAD or invalid, the algorithm will transfer the system to Manual control mode, and generate a process alarm.

Should not be able to manually bypass all 4 (using pushbuttons)

2. Main Steam Flow Obj. V.D.5

a. Four steam flow differential pressure Obj. V.B.1 transmitters provide square-rooted signals corresponding to 0 to 5 Mlb/hr flow rates.

(actual 4.6 to 4.7Mlb/hr)

b. The control algorithm checks the input signal quality and discards BAD data signals.

c. Each steam flow signal is adjusted for a flow nozzle adiabatic expansion factor, which is a function of the nozzle geometry and the ratio of the nozzle throat pressure to inlet pressure.

d. The algorithm calculates the average steam line flow and derives a total steam flow by multiplying the average by 4.

e. The total flow is further compensated for density based on the reactor pressure.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 230000 RHR/LPCI: Torus/Pool Spray Mode ------

Tier # 2 A4.04 (10CFR 55.41.7)

Group # 2 ------

Ability to manually operate and/or monitor in the control room:

Minimum flow valves K/A # 230000A4.04 Importance Rating 3.1 ------

Proposed Question: # 57 Unit 1 RHR Loop I is started in Suppression Pool Spray Mode.

Which ONE of the following completes the statement?

RHR SYSTEM I MIN FLOW VALVE, 1-FCV-74-7, will automatically close if flow is _____.

A. 2600 gpm for 10 seconds.

B. 5800 gpm for 10 seconds.

C. 2600 gpm with NO time delay.

D. 5800 gpm with NO time delay.

Proposed Answer: B Explanation A INCORRECT: Flow is incorrect but time delay is correct. Plausible in that (Optional): this is the set point for Core Spray Minimum Flow Valve.

B CORRECT: The RHR minimum flow valve 1-FCV-74-7 closes on a flow of 5800 gpm after a 10 second TD.

C INCORRECT: Flow and time delay are incorrect.

D INCORRECT: Flow is correct but time delay ins incorrect. Plausible in that the Core Spray Minimum Flow Valve has no time delay.

Justification: Requires knowledge of expected automatic operation of RHR Minimum Flow Valve while in Suppression Pool Spray Mode to correctly answer.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 1-OI-74 Rev. 69 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: OPL171.044 V.B.10__ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 233000 Fuel Pool Cooling/Cleanup ------

Tier # 2 K2.02 (10CFR 55.41.7)

Group # 2 ------

Knowledge of electrical power supplies to the following:

RHR pumps K/A # 233000K2.02 Importance Rating 2.8 ------

Proposed Question: # 58 Which ONE of the following completes the statement for requirements detailed in 2-OI-74, Residual Heat Removal System?

The NORMAL power supply to the pump(s) used for the PREFERRED method for Supplemental Fuel Pool Cooling is a ________.

A. 4 kV Shutdown Board.

B. 4 kV Common Board.

C. 480 V Shutdown Board.

D. 480 V Reactor Building Vent Board.

Proposed Answer: D Explanation A INCORRECT: The RHR Pumps can be used for Fuel Pool Cooling; but are (Optional): NOT preferred. If the candidate believes they are, then this is the power supply to the four RHR Pumps generically.

B INCORRECT: This is actually an ALTERNATE upstream power supply board to the board which powers the RHR Drain Pumps; made 4kV to balance out the question. Candidate could potentially believe RHR Pumps are powered from this set of boards (lower probability).

C INCORRECT: Due to the relative importance of the RHR System as a whole, the candidate may believe that this is a safety-related load. If that were the case, it would be powered by this set.

D CORRECT: (See attached excerpts) OI-74 specifies exactly that the RHR Drain Pumps are PREFERRED over the RHR Pumps for Fuel Pool Cooling applications. Lesson Plan OPL171.044 indicates two reasons why

- RHR Drain Pump flowrates closely match that of the FPC Pumps and to avoid Min Flow issues on RHR Pumps. Attachment 3 to OI-74 delineates power supplies to both the RHR Drain Pumps and the RHR Pumps, with 480 V Reactor Bldg Vent Boards supplying the RHR Drain Pumps.

RO Level Justification: Tests candidates knowledge of power supplies of RHR-related pumps that are utilized for Supplemental Fuel Pool Cooling and the relationship of these pumps to the available lineups. This question is rated as C/A due to the requirement to assemble, sort, and integrate two distinct parts of the question to predict an outcome. This requires mentally using specific knowledge and its meaning to predict the correct outcome.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 2-OI-74, Rev. 150 / OPL171.044, Rev. 17 (Attach if not previously provided) 2-OI-74 Att. 3, Rev. 139 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.3 / 5___________ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 234000 Fuel Handling Equipment ------

Tier # 2 K5.02 (10CFR 55.41.5)

Group # 2 ------

Knowledge of the operational implications of the following concepts as they apply to FUEL HANDLING EQUIPMENT: K/A # 234000K5.02

Fuel handling equipment interlocks Importance Rating 3.1 ------

Proposed Question: # 59 On Unit 3, the Mode Switch is in REFUEL AND ALL control rods are inserted. The Refueling Bridge operator grappled a fuel bundle, raised the grapple, AND commenced moving the bundle towards the core.

Which ONE of the following describes what will result as the Refueling Bridge moves towards the core?

The Refueling Bridge _____.

A. continues over the core AND initiates a control rod block.

B. continues over the core AND causes NO other protective actions.

C. stops before it reaches the core AND initiates a control rod block.

D. stops before it reaches the core AND causes NO other protective actions.

Proposed Answer: A Explanation A CORRECT: With a loaded grapple, a rod block is generated when the (Optional): Refueling Bridge is over the core.

B INCORRECT: Would be true with unloaded grapple.

C INCORRECT: Would be true with one rod withdrawn and second rod selection attempted.

D INCORRECT: Would be true with one rod withdrawn.

Justification: Requires knowledge of operational implications of Fuel Handling Equipment and Rod Block interlocks to correctly answer. Question involves the mental process of understanding the material by relating it to its own parts.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 0-GOI-100-3A Rev. 53 (Attach if not previously provided)

OPL171.053 Rev. 17 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.053 V.B.4 / 5_ (As available)

Question Source: Bank # DAEC 07 #35 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Duane Arnold 2007 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

MONORAIL MONORAIL ES-401 FRAME MOUNTED FUEL GRAPPLE FRAME MOUNTED FUEL GRAPPLE OPL171.053 MOUNTED LOADED FUEL GRAPPLE MOUNTED HOIST LOADED FUEL GRAPPLE ONE ROD HOIST LOADED LOADED HOIST LOADED >400 LBf 1000 LBf NOT FULL UP HOIST LOADED >400 LBf 1000 LBf NOT FULL UP WITHDRAWN

>400 LBf >400 LBf Revision 17 Appendix C ONE ROD Page 5 of 6 WITHDRAWN NOT ALL SELECTION RODS IN OF SECOND ROD SERVICE REFUEL REFUEL SERVICE SELECTION PLATFORM PLATFORM PLATFORM PLATFORM OF SECOND NEAR OR OVER HOIST LOADED HOIST LOADED NEAR OR OVER ROD CORE

>400 LBf CORE >400 LBf MODE SWITCH MODE SWITCH IN "STARTUP" IN " REFUEL "

MODE MODE SWITCH SWITCH IN IN "STARTUP" "REFUEL" REFUEL PLATFORM Sample Written Examination NEAR OR OVER ROD BLOCK CORE STOP REFUEL PLATFORM TRAVEL SERVICE MONORAIL TOWARD CORE FRAME MOUNTED MOUNTED PLATFORM HOIST LOADED HOIST LOADED HOIST LOADED

>400 LBf >400 LBf

>400 LBf Question Worksheet POSITION POSITION NOT ALL POSITION POSITION NORMAL FULL NOT ALL NOT ALL NOT ALL FULL LOWER RODS IN

<8 FT. BELOW <8 FT. BELOW UP RODS IN RODS IN REF. FLOOR RODS IN REF. FLOOR REFUEL LOAD PLATFORM REFUEL REFUEL LOAD

< SLACK CABLE NEAR OR OVER PLATFORM LOAD PLATFORM >JAM LOAD SET POINT CORE NEAR OR OVER >JAM NEAR OR OVER >JAM CORE CORE STOP SERVICE STOP FRAME STOP MONORAIL STOP STOP PLATFORM MOUNTED HOIST MOUNTED HOIST GRAPPLE GRAPPLE HOIST RAISE OR LIFT RAISE OR LIFT LOWER RAISE OPERATION Form ES-401-5

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 241000 Reactor/Turbine Pressure Regulator ------

Tier # 2 K6.06 (10CFR 55.41.7)

Group # 2 ------

Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR / TURBINE PRESSURE REGULATING K/A # 241000K6.06 SYSTEM:

Reactor pressure ------

Importance Rating 3.8 Proposed Question: # 60 Unit 3 is at 100% Reactor Power with the EHC system in Header Pressure Control.

Which ONE of the following would be the result if the output of one of the two header pressure transmitters fails UPSCALE?

A. The Reactor Scrams on MSIV Closure.

B. The Reactor Scrams on High Reactor Power.

C. The Reactor Scrams on High Reactor Pressure.

D. The other header pressure transmitter maintains Reactor Pressure.

Proposed Answer: A Explanation A CORRECT: With EHC Control System in HEADER PRESSURE (Optional): CONTROL, a single Header pressure input fails high with the reactor mode switch is in the RUN position, a Group 1 isolation will occur when steam line pressure lowers to 852 psig, resulting in a reactor scram B INCORRECT: Plausible in that if EHC Pressure Control Signal output signal had failed low rather than transmitter output, would result in Turbine Control Valves closing, steam flow to be restricted, and Reactor pressure to increase resulting in high Reactor Power. EHC Pressure Control Signal output failing low would also result in Bypass Valves remaining closed.

C INCORRECT: Plausible in that if EHC Pressure Control Signal output signal had failed low rather than transmitter output, would result in Turbine Control Valves closing, steam flow to be restricted, and Reactor pressure to increase. EHC Pressure Control Signal output failing low would also result in Bypass Valves remaining closed D INCORRECT: With EHC Control System in HEADER PRESSURE CONTROL, a single Header pressure input fails low. The following may occur: The EHC Control System automatically bypasses the applicable input. Therefore, if the output one of the two header pressure transmitters failed downscale instead of upscale, this would be the correct answer.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: Requires Knowledge of the effect that a malfunction of the Reactor Pressure signal to EHC Logic will have on the REACTOR / TURBINE PRESSURE REGULATING SYSTEM.

This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.228 Rev 4 (Attach if not previously provided) 3-AOI-47-2 Rev. 6 / 3-OI-47 Rev. 89 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.228 V.B.1____ (As available)

Question Source: Bank # OPL171.230 #5 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 268000 Radwaste ------

Tier # 2 K3.04 (10CFR 55.41.5)

Group # 2 ------

Knowledge of the effect that a loss or malfunction of the RADWASTE will have on the following: K/A # 268000K3.04

Drain sumps Importance Rating 2.7 ------

Proposed Question: # 61 Unit 2 Turbine Building Floor Drain Sump Pump A has automatically started on high level when the following alarm is received:

FD COLLECTOR TANK LEVEL HIGH, (0-25-17B, Window 17)

Which ONE of the following completes the statement?

Turbine Building Floor Drain Sump Pump A will ____.

A. trip IMMEDIATELY.

B. continue to run with NO discharge flow path.

C. continue to pump to the Floor Drain Collector Tank.

D. continue to run with discharge aligned to the Waste Collector Tank.

Proposed Answer: C Explanation A INCORRECT: Plausible in that it is a common feature for pump to trip if (Optional): receiving tank level high or low flow. Example - If Cond Head Tank Level High alarms, both condensate transfer pumps secure on high level.

B INCORRECT: Plausible in that it is logical to isolate inputs to tanks on high level and some pumps will not trip even with the low flow condition.

Example - If RCIC is operating in CST to CST mode and the Test Return isolates, RCIC will continue to operate dead headed. Min flow valve will not function with absence of initiation signal.

C CORRECT: There are no automatic features associated with FD COLLECTOR TANK LEVEL HIGH. Turbine Building Floor Drain Sump Pump A will continue to pump to the Floor Drain Collector tank until high sump level is cleared.

D INCORRECT: Plausible in that it is common feature to re-direct tank inputs on a high tank level. Example - If Laundry Drain Tank Level High is received and FCV-77-179 is open to tank A, it will close to tank A and open to tank B.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: Question tests Candidates knowledge of impact of high level in Floor Drain Collector Tank on Turbine Building Floor Drain Sump Pumps. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): OPL171.084 Rev. 5 (Attach if not previously provided) 0-ARP-25-17B Rev. 5 Proposed references to be provided to applicants during examination: NONE Learning Objective: ___________________ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 OPL 171.084 Revision 5 CROSSTIE TO WASTE COLLECTOR Page 61 of 8 DRYWELL & REACTOR BLDG.

BACKWASH RECEIVER PIT RADWASTE BUILDING TURBINE BUILDING SYSTEM (Figure 3) TO WASTE VENT TO COLLECTOR EXHAUST CROSSTIE TO AH TANK DUCT P FT E FLOOR DRAIN SUMPS FLOOR DRAIN SUMP FLOOR DRAIN SUMPS CHEMICAL WASTE TANK FLOOR DRAIN SUMPS RHR SYSTEM DRAINS WASTE COLLECTOR CE FE AO H/L A SYSTEM (Figure 3)

DISCHARGE FLOOR DRAIN AO H TO DRUMS FILTER A L FLOOR DRAIN AO BACKWASH LT COLLECTOR PRECOAT TANKS TANK AO FLOOR FLOOR DRAIN DRAIN LT SAMPLE CHEMICAL DRAINS SAMPLE TANK A TANK B LS AO PRECOAT REACTOR BUILDING RETURN AO AO DECON DRAINS AO LS CONDENSATE DEMIN Sample Written Examination TO WASTE FLOOR DRAIN BACKWASH DECON DRAINS COLLECTOR PUMPS RECEIVING CHEMICAL ADDITION CHEMICAL DRAINS PRECOAT HS H ADDITION A L FLOOR DRAIN FR SAMPLE PUMPS CHEMICAL WASTE TANK LT FROM FROM FIT WASTE LAUNDRY AO SAMPLE DRAIN TANKS FILTER Question Worksheet LS FCV FROM WASTE FIT EVAPORATOR MONITORING TANKS SHIELDING AO TO DISCHARGE CHEMICAL CANAL AO WASTE PUMPS RE FCV TO WASTE TO COOLING EVAPORATOR TOWER BLOWDOWN PROCESS RADIATION MONITOR Form ES-401-5

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 272000 Radiation Monitoring System ------

Tier # 2 A3.02 (10CFR 55.41.7)

Group # 2 ------

Ability to monitor automatic operations of the RADIATION MONITORING SYSTEM including: K/A # 272000A3.02

Offgas system isolation indications Importance Rating 3.6 ------

Proposed Question: # 62 Which ONE of the following completes the statement?

MAIN STEAM LINE RAD HIGH-HIGH / INOP, (1-9-3A, Window 27), alarms at __(1)__ Normal Full Power Background radiation level AND ALL monitors at this radiation level__(2)__ result in a trip AND isolation of the Mechanical Vacuum Pumps.

A. (1) 1.5 times (2) will B. (1) 1.5 times (2) will NOT C. (1) 3 times (2) will D. (1) 3 times (2) will NOT Proposed Answer: C Explanation A INCORRECT: Part 1 incorrect - Plausible in that this is the set point for (Optional): MSL RAD HIGH alarm. Part 2 correct - See Explanation C.

B INCORRECT: Part 1 incorrect - See Explanation A. Part 2 incorrect -

Plausible in that similar radiation monitoring system, Offgas Post Treatment Radiation Monitor does not result in an Isolation of Offgas until Hi-Hi-Hi Rad Level is received. Also, could be confused with MSIVs which do NOT isolate at all on elevated MSL Radiation levels.

C CORRECT: Part 1 correct - MAIN STEAM LINE RAD HIGH-HIGH / INOP (55-3A-27) alarm at a radiation level of 3 times the Normal Full Power Background radiation level. Part 2 correct - Mechanical Vacuum Pumps trip and isolate on High-High MSL Radiation 3 X NFP Background.

D INCORRECT: Part 1 correct - See Explanation C. Part 2 incorrect - See Explanation B.

Justification: Candidate must know set point and resulting actions with MSL Rad High-High to demonstrate ability to monitor automatic operations of the RADIATION MONITORING SYSTEM including trip and isolation of the Mechanical Vacuum Pumps which are part of the Offgas System.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPL171.033 Rev. 13 (Attach if not previously provided) 1-OI-66 Rev. 22 / 1-9-3A Rev. 38 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.033_V.B.4___ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 286000 Fire Protection ------

Tier # 2 G2.2.42 (10CFR 55.41.10)

Group # 2 ------

Ability to recognize system parameters that are entry-level conditions for Technical Specifications. K/A # 286000G2.2.42 Importance Rating 3.9 ------

Proposed Question: # 63 Which ONE of the following completes the statement for the MIMIMUM requirements for High Pressure Fire Pumps in accordance with Fire Protection Report Volume 1?

The High Pressure Fire Protection System shall be operable at ALL times with ______ aligned to the fire suppression header.

A. ONE Diesel Fire Pump B. ONE Electric Fire Pump C. TWO Electric Fire Pumps D. ONE Diesel Fire Pump AND ONE Electric Fire Pump Proposed Answer: D Explanation A INCORRECT: Plausible in that typical system pressure demand is such that (Optional): one Fire Pump will operate in case of a fire in the buildings.

B INCORRECT: Plausible in that typical system pressure demand is such that one Fire Pump will operate in case of a fire in the buildings and Electric Fire Pump Power Supplies are from 4 kV Shutdown Boards.

C INCORRECT: Plausible in that two Fire Pumps are required to be operable and Electric Fire Pump Power Supplies are from 4 kV Shutdown Boards.

D CORRECT: Two High Pressure Fire Pumps shall be operable and aligned to the high pressure fire header as specified in the Fire Protection Report Volume 1.

Justification: Candidate must know how many High Pressure Fire Pumps are required by Fire Protection Report Volume 1 to correctly answer the question.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPL171.049 Rev. 15 (Attach if not previously provided)

Fire Protection Report Volume 1 Rev. 6 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.049 V.B.6____ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 290003 Control Room HVAC ------

Tier # 2 K4.01 (10CFR 55.41.7)

Group # 2 ------

Knowledge of CONTROL ROOM HVAC design feature(s) and/or interlocks which provide for the following: K/A # 290003K4.01

System initiations/reconfiguration: Plant-Specific Importance Rating 3.1 ------

Proposed Question: # 64 Which ONE of the following completes the statements?

When BOTH CREV trains are operable, the preferred position for CREV UNIT PRIMARY SELECTOR, 0-XSW-031-7214, is in __(1)__ .

If the SELECTED CREV Train AUTO-INITIATE / TEST switch is placed to the INITIATE / TEST position the initiation sequence starts __(2)__.

A. (1) TRAIN A.

(2) immediately.

B. (1) TRAIN B.

(2) immediately C. (1) TRAIN A.

(2) after 30 seconds.

D. (1) TRAIN B.

(2) after 30 seconds.

Proposed Answer: A Explanation A CORRECT: Part 1 correct - When both CREV trains are operable, the (Optional): preferred position for CREV UNIT PRIMARY SELECTOR, 0-XSW-031-7214, is in TRAIN "A" which makes the "A" CREV the lead train. Part 2 correct - If the selected trains switch is put in the INITIATE/TEST position that train will immediately enter its initiation sequence, B INCORRECT: Part 1 incorrect - Train A is Normally the Selected Train.

Plausible in that either Train of CREV can be selected as Lead Train. Part 2 correct - See Explanation A.

C INCORRECT: Part 1 correct - See Explanation A. Part 2 incorrect - If the selected trains switch is put in the INITIATE/TEST position that train will immediately enter its initiation sequence, Plausible in that the STANDBY train initiation sequence is delayed 30 seconds if the trains switch is put in the INITIATE/TEST position.

D INCORRECT: Part 1 and 2 are incorrect as explained above.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Justification: Question requires plant-specific knowledge of Control Room Emergency Ventilation interlocks which provide for system initiations and reconfiguration to successfully answer.

Technical Reference(s): OPL171.067 Rev. 16 (Attach if not previously provided) 0-OI-31 Rev. 136 Proposed references to be provided to applicants during examination: NONE Learning Objective: __________________ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.067 Revision 16 Page 4 of 4

a. Manual initiation of the emergency mode Adherence to of operation can be performed from the procedures control room by operation of the AUTO- INPO SER 03-05 INITIATE/TEST switch (putting switch in Obj.V.B.4/V.B.2 INITIATE/TEST position) at Pnl 2-9-22.

This operation results in energizing the CR1 relay for that train/division and isolation of the control room dampers.

Only one solenoid must be energized to close these dampers. Therefore, either test switch will initiate a damper isolation.

b. One switch alone in the INITIATE/TEST Normally A is position will NOT result in full functionality selected unit via of the CREVS units. If that train is not the switch in CREV selected unit, then operation of that train room. If A is will be delayed by approx. 30 seconds, inoperable, switch waiting for the selected train. This delay 0-XSW-031-7214 will result in the operator waiting to see SYSTEM PRIORITY the result of his operation of the switch. SELECTOR The operator will see the amber light lit, SWITCH is placed in indicating energization of the CR 1 relay TRAIN B position to and the solenoid for isolation damper start it without time closing, but will see no activity of the delay.

CREVS unit until the delay timer has timed out.

c. If the selected trains switch is put in the INITIATE/TEST position that train will immediately enter its initiation sequence, with the dampers red light being lit as well as the green, indicating travel of the damper toward the open position.

However, should there be any failure of the selected unit; the standby unit will not start. This is because the CR1 relay for the standby unit was not actuated.

d. Therefore, when manually initiating emergency operation of the new CREVS units, it is important to put the AUTO-INITIATE/TEST switches of BOTH trains to the INITIATE/TEST position.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO 290002 Reactor Vessel Internals ------

Tier # 2 K1.12 (10CFR 55.41.6)

Group # 2 ------

Knowledge of the physical connections and/or cause-effect relationships between REACTOR VESSEL INTERNALS and the K/A # 290002K1.12 following:

SLC Importance Rating 3.4 ------

Proposed Question: # 65 Which ONE of the following completes the statement?

The Standby Liquid Control (SLC) System Injection Spargers __(1)__ provides for sodium pentaborate injection __(2)__ the Reactor Core Plate.

A. (1) inner tube (2) above B. (1) inner tube (2) below C. (1) outer tube (2) above D. (1) outer tube (2) below Proposed Answer: B Explanation A INCORRECT: First part correct; but, SLC injects below the Core Plate as (Optional): detailed below in B.

B CORRECT: (See attached Lesson Plan excerpt) The inner tube penetrates the vessel inside the shroud near the core edge, terminating as a perforated tube below the core plate. It acts as the sodium pentaborate injection line.

C INCORRECT: The outer tube penetrates the vessel inside the shroud near the core edge, and terminates in the core plate. SLC injects below the Core Plate as detailed below in B.

D INCORRECT: It is not the outer tube, as discussed in C above. The second part of the statement is correct.

RO Level Justification: Tests whether the candidate has knowledge of the physical connections between Reactor Vessel Internals and SLC. Non-Licensed Operators are only required to know the function of the Injection Sparger itself, not broken down to the level of an inner/outer tube relationship or its relationship to Reactor Vessel Internals.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPL171.039, Rev. 16 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.5.b____________ (As available)

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

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO G2.1.25 (10CFR 55.41.10) Tier # 3 ------

Ability to interpret reference materials, such as graphs, ------ ------

Group #

curves, tables, etc.

K/A # G2.1.25 Importance Rating 3.9 ------

Proposed Question: # 66 Which ONE of the following completes the statement?

In accordance with the EOI Program Manual derivation, Line 1 on Curve 6, Pressure Suppression Pressure, above, corresponds to the Suppression Pool Water Level at which the A. Downcomer Vents become uncovered.

B. HPCI Turbine Exhaust opening becomes uncovered.

C. Safety Relief Valve (SRV) Tailpipe openings become uncovered.

D. Control Room Suppression Pool Water Narrow Range Level Indication goes off scale low.

Proposed Answer: A Explanation A CORRECT: (See attached excerpt) According to the EOI Program Manual, (Optional): 11.5 feet (or Line 4) is the Suppression Pool Water Level which corresponds to the elevation of the downcomer vent openings.

B INCORRECT: The HPCI Turbine Exhaust becomes uncovered in the range of but above this value (at 12.75 feet) and is a significant direct Suppression Chamber Air Space pressurization event if HPCI remains running. PSP would be quickly exceeded.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet C INCORRECT: SRV Tailpipes become uncovered around 5.5 feet. This is plausible because of the required ED at 11.5 feet. Normally, an ED on a parameter such as this is accomplished before you lose the ability to do so safely (within Safety Analyses assumptions).

D INCORRECT: Plausible because the X-Axis is based upon Suppression Pool Water Level and Narrow Range goes off-scale low at -25 inches which corresponds to approximately 13 feet.

RO Level Justification: Tests the candidates ability to interpret Pressure Suppression Pressure Curve bounding limitations on Suppression Chamber Pressure versus Suppression Pool Level.

Technical Reference(s): OPL171.201, Rev. 7 (Attach if not previously provided)

EOI Program Manual Sect. 2-VI-H, Rev. 9 0-TI-394, Rev. 4 Proposed references to be provided to applicants during examination: Embedded EOI Curve 6 - PSP Learning Objective: _V.B.12 ____________ (As available)

Question Source: Bank # X Modified Bank # Hatch 07 NRC Q#67 (Note changes or attach parent)

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments: This question was originally developed for an Audit Exam.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet BANK QUESTION THAT WAS MODIFIED

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet ILLUSTRATION 1 EXCERPT

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO G2.1.27 (10CFR 55.41.7) Tier # 3 ------

Knowledge of system purpose and/or function. ------

Group # ------

K/A # G2.1.27 Importance Rating 3.9 ------

Proposed Question: # 67 Which ONE of the following completes the statement?

In accordance with 10CFR50.46, Acceptance Criteria for Emergency Core Cooling Systems (ECCS) For Light-Water Nuclear Power Reactors, all of the following are design functions of Browns Ferry ECCS with the EXCEPTION of ________.

A. maintaining peak cladding temperature less than or equal to 2600 ºF.

B. maintaining core geometry such that the core remains amenable to cooling.

C. minimizing total cladding oxidation to less than or equal to 17% of the total cladding thickness prior to oxidation.

D. minimizing total hydrogen generation to less than or equal to 1% of the hypothetical amount possible if all of the cladding were to react chemically with water or steam.

Proposed Answer: A Explanation A CORRECT: The calculated maximum fuel element temperature specified in (Optional): 10CFR50.46 is 2200 ºF versus 2600 ºF, which is the melting point of Stainless Steel according to 0-TI-394.

B INCORRECT: This is a specified variable in 10CFR50.46.

C INCORRECT: This is a specified variable in 10CFR50.46.

D INCORRECT: This is a specified variable in 10CFR50.46.

RO Level Justification: Tests the candidates ability to recall the specified criteria of 10CFR50.46 as it applies to Browns Ferry ECCS. Compounding the level of difficulty is the addition of wording (above and beyond what is normally memorized). For example, competent candidates should normally remember cladding oxidation less than 17%; as this is the way it is normally discussed; but, may not specifically recall in relation to what.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 10CFR50.46 (Attach if not previously provided) 0-TI-394, Rev. 04 Proposed references to be provided to applicants during examination: NONE Learning Objective: _V.B.1_(OPL171.042 / 044 / 045)__ (As available)

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

New Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO G2.1.8 (10CFR 55.41.10) Tier # 3 ------

Ability to coordinate personnel activities outside the control ------

Group # ------

room.

K/A # G2.1.8 Importance Rating 3.4 ------

Proposed Question: # 68 In accordance with 2-OI-68, Reactor Recirculation System, which ONE of the following describes the MINIMUM qualification AND coordination requirements to perform LOCAL VFD Speed Control manipulations for the 2A Reactor Recirc Pump?

A. A Licensed Reactor Operator in communication with the Main Control Room may perform LOCAL VFD Speed Control manipulations.

B. A Licensed Reactor Operator may perform LOCAL VFD Speed Control manipulations with a Senior Reactor Operator supervising locally.

C. A qualified Assistant Unit Operator may perform LOCAL VFD Speed Control manipulations with a Licensed Reactor Operator supervising.

D. A qualified Assistant Unit Operator in communication with the Main Control Room may perform LOCAL VFD Speed Control manipulations.

Proposed Answer: A Explanation A CORRECT: A Licensed Reactor Operator is the minimum qualification, with (Optional): Main Control Room communications established.

B INCORRECT: Plausible in that it would be true if communications were established with the Main Control Room.

C INCORRECT: Plausible in that it would be true if communications were established with the Main Control Room and the AUO were enrolled in a License Training Program.

D INCORRECT: Plausible in that it would be true if AUO were enrolled in a License Training Program and supervised by a Licensed Operator.

Justification: Requires knowledge of MINIMUM qualification AND coordination requirements to perform LOCAL VFD Speed Control manipulations for Reactor Recirc Pumps.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 2-OI-68 Rev. 134 (Attach if not previously provided)

OPDP-1 Rev. 15 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.071V.B.6____ (As available)

Question Source: Duane Arnold 2007 Bank # #66 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Duane Arnold 2007 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO G2.2.37 (10CFR 55.41.7) Tier # 3 ------

Ability to determine operability and/or availability of safety ------

related equipment. Group # ------

K/A # G2.2.37 Importance Rating 3.6 ------

Proposed Question: # 69 Which ONE of the following completes the statement?

In accordance with Unit 2 Tech Spec 3.4.1,Recirculation Loops Operating, Recirculation Loop Jet Pump flow mismatch with BOTH Recirculation Loops in operation must be LESS THAN OR EQUAL TO __(1)__ of rated core flow when operating at LESS THAN 70% rated core __(2)__.

A. (1) 5%

(2) flow.

B. (1) 10%

(2) flow.

C. (1) 5%

(2) power.

D. (1) 10%

(2) power.

Proposed Answer: B Explanation A INCORRECT: Part 1 incorrect - See Explanation C. Part 2 correct - See (Optional): Explanation B.

B CORRECT: Part 1 and 2 correct - In accordance with Unit 2 Tech Spec 3.4.1,Recirculation Loops Operating, SR 3.4.1.1, limit for recirculation loop jet pump flow mismatch with both recirculation loops in operation is 10%

of rated core flow when operating at < 70% of rated core flow.

C INCORRECT: Part 1 incorrect - Plausible in that this is flow mismatch limit for > 70% rated core flow Part 2 incorrect - Plausible in that it is easily confused core flow versus power for mismatch criteria.

D INCORRECT: Part 1 correct - See Explanation B. Part 2 incorrect - See Explanation C.

RO Level Justification: To determine operability of Recirc, candidate must know Jet Pump Flow mismatch criteria.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): U2 TS 3.4.1 Amm 258 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: ___________________ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO G2.2.22 (10CFR 55.41.5) Tier # 3 ------

Knowledge of limiting conditions for operations and safety ------

Group # ------

limits.

K/A # G2.2.22 Importance Rating 4.0 ------

Proposed Question: # 70 Which ONE of the following combinations of Reactor Power AND Reactor Pressure on Unit 1 constitute a Safety Limit violation?

Reactor Reactor Power Pressure A. 15% 750 psig B. 24% 770 psig C. 28% 775 psig D. 32% 810 psig Proposed Answer: C Explanation A INCORRECT: If Reactor Pressure greater than 785 psig, this would be a (Optional): correct answer.

B INCORRECT: If Reactor Pressure greater than 785 psig, this would be a correct answer.

C CORRECT: With the reactor steam dome pressure < 785 psig or core flow< 10% rated core flow, THERMAL POWER shall be 25% RTP.

D INCORRECT: If Reactor Power was less than 25%, this would be a correct answer.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet RO Level Justification: Tests the candidates knowledge of safety limits.

Technical Reference(s): Unit 1 Tech Specs, Sect. 2.0, Am. 267 (Attach if not previously provided)

OPL171.087, Rev. 8 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.087 V.B.14 __ (As available)

Question Source: Bank # FITZ 08 #70 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Fitzpatrick 2008 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.087 Revision 78 Page 4 of 5

a. Section 1.4 Frequency Frequency specifies how often a surveillance Review the requirement (SR) must be performed or met for section 1.4 continued compliance with the LCO. When met examples is specified, the SR need not be performed or current if there is no reason to suspect its acceptance criteria would not be met if it were performed. The examples specify all the special circumstances applied to frequencies and should be reviewed.

1. Section 2.0 SAFETY LIMITS

a. This section contains the requirements for meeting Section 2.0 does the four Safety Limits. The first two requirements not exist in TRM; ensure the Minimum Critical Power Ratio (MCPR) is not exceeded. The third ensures adequate core Obj. V.B.15 cooling. The last ensures the integrity of the vessel and associated piping.

b. For all 3 units

1) Reactor steam dome pressure shall be < 1325 psig.

2) Thermal power shall be < 25% when steam dome pressure is < 785 psig OR core flow is < 10% of rated

3) Reactor water level shall be > Top of Active Fuel (TAF)

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO G2.2.4 (10CFR 55.41.7) Tier # 3 ------

(multi-unit license) Ability to explain the variations in control ------

Group # ------

board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. K/A # G2.2.4 Importance Rating 3.6 ------

Proposed Question: # 71 Which ONE of the following completes the statement?

In accordance with 2/3-OI-3, Reactor Feedwater System, the MAXIMUM speed for Unit 2 Reactor Feed Pump Turbines (RFPTs) is __(1)__ AND the MAXIMUM speed for Unit 3 RFPTs is __(2)__ .

A. (1) 5050 rpm (2) 5050 rpm B. (1) 5050 rpm (2) 5850 rpm C. (1) 5850 rpm (2) 5050 rpm D. (1) 5850 rpm (2) 5850 rpm Proposed Answer: C Explanation A INCORRECT: Part 1 incorrect -The MAXIMUM speed for Unit 2 RFPTs is (Optional): 5850 rpm. Part 2 correct - MAXIMUM speed for Unit 3 RFPT is 5050 rpm.

Combination of both RFPTs having same MAX speed is plausible in that Unit 1 and 2 have the same MAX speed.

B INCORRECT: Part 1 incorrect - The MAXIMUM speed for Unit 2 RFPTs is 5850 rpm. Part 2 incorrect - MAXIMUM speed for Unit 3 RFPTs is 5050 rpm.

C CORRECT: Part 1 correct - The MAXIMUM speed for Unit 2 RFPTs is 5850 rpm. Part 2 correct - MAXIMUM speed for Unit 3 RFPTs is 5050 rpm.

D INCORRECT: Part 1 is correct and Part 2 is incorrect as explained above.

Justification: Candidate must recognize Unit 2/3 differences for RFPT MAXIMUM speeds to correctly answer the question.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 2-OI-3 Rev. 135 (Attach if not previously provided) 3-OI-3 Rev. 81 Proposed references to be provided to applicants during examination: NONE Learning Objective: ___________________ (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO G2.3.14 (10CFR 55.41.12) Tier # 3 ------

Knowledge of radiation or contamination hazards that may ------

Group # ------

arise during normal, abnormal, or emergency conditions or activities. K/A # G2.3.14 Importance Rating 3.4 ------

Proposed Question: # 72 Unit 1 was at 35% Reactor Power when the Hydrogen Injection System was placed in service in Automatic / Power Determined mode in accordance with 1-OI-4, Hydrogen Water Chemistry System.

Power is raised from 35% Reactor Power to 100% Reactor Power

At 100% Reactor Power hydrogen flow rate indicates 20 scfm Which ONE of the following completes the statements?

In accordance with 1-OI-4, hydrogen injection flow rate is __(1)__ the normal 100% Reactor Power flow rate.

Radiation levels in the Condenser Bay will stabilize __(2)__ expected normal full power radiation levels.

A. (1) above (2) at B. (1) below (2) at C. (1) above (2) above D. (1) below (2) below Proposed Answer: C Explanation A INCORRECT: Part 1 correct - See explanation C. Part 2 incorrect -

(Optional): radiation levels are expected to increase to above normal levels. Plausible because flow is higher than normal, but the candidate must understand the effects of H2 injection on Radiation levels.

B INCORRECT: Part 1 incorrect - H2 flow rate is NOT below normal.

Plausible in that this injection flow rate is below the maximum allowed H2 injection rate of 25 scfm. Part 2 is incorrect -radiation levels are expected to increase to above normal levels.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet C CORRECT: Part 1 correct - In the Automatic / Power Determined Mode, the hydrogen injection system is load following. It is normally placed in service above 25% Rx power. As Rx power is increased, the hydrogen flow rate is increased to the maximum amount that the controller is set for.

Normal H2 Injection Rate (100% Reactor Power) is 14 scfm. Due to current EPU spanned software installed on U1 HWC computer, Chemistry has requested Ops to input a 16 scfm H2 injection value in order to receive the required 14 scfm actual H2 injection flow at 100% Power. Part 2 correct -

Operation of HWC with injection rates above normal will cause a significant rise in radiation dose rates in steam affected areas.

D INCORRECT: Part 1 and 2 incorrect as explained above.

Justification: Requires knowledge of radiation hazards associated with changes in HWC System parameters to correctly answer. This question is rated as C/A due to the requirement to assemble, sort, and integrate the parts of the question to predict an outcome. This requires mentally using this knowledge and its meaning to predict the correct outcome.

Technical Reference(s): 1-OI-4 Rev. 9 (Attach if not previously provided)

OPL171.220 Rev. 6 Proposed references to be provided to applicants during examination:

Learning Objective: OPL171.220 V.B.6 / 9_ (As available)

Question Source: Bank # Hatch 2009 # 72 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Hatch 2009 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO G2.3.5 (10CFR 55.41.11) Tier # 3 ------

Ability to use radiation monitoring systems, such as fixed ------

Group # ------

radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. K/A # G2.3.5 Importance Rating 2.9 ------

Proposed Question: # 73 Which ONE of the following completes the statement in accordance with EOI-4 Program Manual?

Per EOI-4, Radioactivity Release Control, __(1)__ Building Ventilation is re-started, if shut down, to __(2)__.

A. (1) Reactor (2) filter the ground level release.

B. (1) Turbine (2) filter the ground level release.

C. (1) Reactor (2) to ensure ability to monitor AND elevate the radioactive release.

D. (1) Turbine (2) to ensure ability to monitor AND elevate the radioactive release.

Proposed Answer: D Explanation A INCORRECT: Plausible in that Reactor Building Ventilation direction to (Optional): restart is provided in EOI-3 under certain conditions and system does provide filtration.

B INCORRECT: Plausible in that where a high potential for contamination exist, Turbine Building Ventilation exhaust fans with HEPA filters are installed to control the spread of contamination. However, this is not the bases for starting Turbine Building Ventilation IAW EOI-4.

C INCORRECT: Plausible in that Reactor Building Ventilation does is discharged through an elevated, monitored release point and direction to restart is provided in EOI-3 under certain condition.

D CORRECT: Per EOI Program Manual, 0-V-F, Operation of the Turbine Building Ventilation System preserves turbine building accessibility, and assures that radioactivity in turbine building areas is discharged through an elevated, monitored release point.

Justification: Ability to use radiation monitoring equipment to monitor Turbine Building Ventilation is tested.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): EOI Program Manual O-V-F Rev. 1 (Attach if not previously provided)

OPL171.204 Rev. 7 Proposed references to be provided to applicants during examination: NONE Learning Objective: OPL171.204 V.B.10___ (As available)

Question Source: Bank #

Modified Bank # DAEC 07 #57 (Note changes or attach parent)

New Question History: Last NRC Exam Duane Arnold 2007 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.204 Revision 7 Page 4 of 52 The wording of the entry condition provides for entry into Obj. V.B 8, 9 EOI-4 when radioactivity release exceeds event Obj. V.C.8,9 classification limits for Unusual Event or any higher classification. Unusual Event limits, coupled with the Any EPIP-1, required duration, are substantially above the limits for Section II-4 normal plant operation and represent inability to control Event Classification radioactivity release. Entry into Emergency Procedures is appropriate at this, or any higher event classification, to ensure procedure guidance is provided when the guidance of normal or abnormal plant procedures has failed to terminate or reverse the trend of increasing release. Refer also to Emergency Plan Implementing Procedure, BFN-EPIP-1, Emergency Plan Classification Logic.

3. Step RR-1 This retainment override step, applies throughout the performance of this procedure. The first override directs the operator to exit all EOI flowcharts and perform actions as directed by the SAM team only when SAMG entry is required and the TSC SAM team has assumed command and control. The second part of the override has the operator restart turbine building ventilation if turbine building ventilation is shutdown.

Operation of the Turbine Building Ventilation System Obj. V.B.10 preserves turbine building accessibility, and assures that Obj. V.C.10 radioactivity in turbine building areas is discharged through an elevated, monitored release point. Continued personnel access to the turbine building may be essential for responding to emergencies or transients which may degrade into emergencies. Since the turbine building is not an air-tight structure, a radioactive release inside the turbine building would not only limit personnel access, but would eventually lead to an unmonitored ground level release.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.067 Revision 16 Page 6 of 10

1. Where a high potential for contamination exist, Shown on Unit 1 exhaust fans with HEPA filters are installed to Turbine Building control the spread of contamination. Vent print

a. Turbine decontamination chamber

b. Outage hot tool room .

c. Total turbine building exhaust capacity is Obj. V.B.2 approximately 269,000 cfm with a Obj. V.C.2 maximum supply of approximately 255,000 cfm, which allows the building to be kept under a slightly negative pressure to prevent leakage of contamination to environment, and provides for an elevated, monitored release.

2. Radiation Monitoring Obj. V.B.2 Obj. V.C.12

a. The turbine building exhaust flow is monitored by RM-90-250 CAM which also monitors the reactor building and refuel floor.

b. The turbine room (roof) exhaust is PROCEDURE monitored by RM-90-249 and RM-90-251 ADHERENCE CAMS which must be in service anytime the fans are in service. Fan/monitor combinations are as follows:

c. Unit 1 & 2 RM 90-251 Fans A,B,C,D,E

d. Unit 1 & 2 RM 90-249 Fans F,G,H,J

e. Unit 3 RM 90-251 Fans A,B,C,D

f. Unit 3 RM 90-249 Fans E,F,G,H,J

3. The following turbine area ventilation fans will trip on loss of air flow:

a. Turbine spaces supply fan

b. Mechanical spaces supply fans

c. Electrical spaces supply fans

d. Mechanical spaces exhaust fan

e. Demineralizer spaces exhaust fans

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OPL171.067 Revision 16 Appendix C Page 7 of 10

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet To Stack Discharge To Stack Discharge Reactor Zone Exhaust Fans Refuel Zone Reactor 100,000 scfmZone

- FAST Exhaust Fans 50,000 scfm - SLOW 50,000 scfm - FAST Exhaust Fans 25,000 scfm - SLOW Refuel Zone 100,000 scfm - FAST Exhaust Fans 50,000 scfm - SLOW 50,000 scfm - FAST 25,000 scfm - SLOW Refueling Room Elevator Stairwell Space EL 664 Space above Drywell Dryer and Normally Ventilated Fuel Separator Storage Storage Refueling Room Pool Pool SBGTS To SBGTS Suction RWCU Filter -

EL 639 Demins EL 664 Space above Drywell Equipment Access Lock Dryer and Normally Ventilated Fuel Separator Drywell Storage EL 621 Pool Storage RWCU RWCU Backwash Backwash Pool RWCU Recirc RWCU Pump Evaporative Coolers Vac Pump HX Tank Room Rooms Room Room Brkr Heating Coils EL 593 Louvres Refuel Zone RWCU Filters Supply Fans Filter -

48,000 scfm - FAST EL 639 Demins Vac Brkr Reactor Main Bld to TIP Steam Torus Drywell System Pipe Access Lock Room Vault Reactor Zone Vac Bkrs EL 565 Supply Fans 98,300 scfm - FAST Core Spray

& RCIC Cooler Room (2)

Suppression Chamber Cooler (2)

Drywell SBGTS HPCI Room RHR Pump SBGTS Core Spray RHR Pump Motor EL 519 EL 621 Pump Motor Motor Vac Brkr EL 593 Refuel Zone Supply Fans 48,000 scfm - FAST Vac Brkr Reactor Zone EL 565 Supply Fans 98,300 scfm - FAST Core Spray

& RCIC Room Suppression Chamber HPCI Room Core Spray

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet TP-1: Reactor Building Ventilation

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO G2.4.20 (10CFR 55.41.10) Tier # 3 ------

Knowledge of the operational implications of EOP warnings, ------

Group # ------

cautions, and notes.

K/A # G2.4.20 Importance Rating 3.8 ------

Proposed Question: # 74 In accordance with 1-EOI-1, RPV Control, NOTE #1, which ONE of the following indications confirms that the Unit 1 reactor will remain subcritical under ALL conditions without boron?

A. ALL control rods are at position 02.

B. ALL control rods full-in EXCEPT 2 at position 30.

C. Reactor Power is on range 7 of the IRMs AND lowering.

D. ALL control rods full-in EXCEPT 1 at position 02 AND 1 at position 48.

Proposed Answer: A Explanation A CORRECT: In accordance with RPV Control, 1-EOI-1 NOTE #1 for Unit (Optional): 1, the reactor will remain subcritical under ALL conditions without boron when all control rods are inserted to or beyond position 02. This is true for Unit 1 only. Unit 2 and 3 require no more than 19 control rods inserted to or beyond position 02 and all other control rods fully inserted which supports the plausibility of the distracters.

B INCORRECT: In accordance with RPV Control, 1-EOI-1 NOTE #1 for Unit 1, the reactor will remain subcritical under ALL conditions without boron when all control rods except one are inserted to or beyond position 00.

C INCORRECT: When used in the EOIs Subcritical is defined as Reactor power on range 7 and lowering of the IRMs with the IRMs inserted.

However, this does not ensure that the reactor will remain subcritical under ass conditions without boron.

D INCORRECT: Does not meet criteria for ensuring the reactor will remain subcritical under ALL conditions without boron. Plausible misconception in that candidate may believe combination of SDM One Rod Out and Maximum Subcritical Bank Withdrawal Position will ensure reactor will remain subcritical under all conditions.

Justification: Requires knowledge of the operational implications of EOP NOTE #1 to successfully answer.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 1-EOI-1 Rev. 0 (Attach if not previously provided)

EOI Program Manual 0-X-B Rev. 19 Proposed references to be provided to applicants during examination: NONE Learning Objective: ___________________ (As available)

Question Source: Bank #

Modified Bank # Oyster Creek 07 #5 (Note changes or attach parent)

New Question History: Last NRC Exam Oyster Creek 2007 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet OYSTER CREEK 2007 OC ILT 07-1 RO NRC Exam KEY Following an automatic scram from rated power, the Operator placed the REACTOR MODE SELECTOR switch in SHUTDOWN.

Which of the following indications, ALONE, allows the Reactor Operator to confirm that the reactor will remain shutdown under all conditions without boron?

A. All APRMs indicate < 2% power B. All control rods indicate position 04.

C. All LPRM amber lights on Panel 4F are LIT.

D. All control rods full-in EXCEPT 2 control rods at position 30.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO G2.4.45 (10CFR 55.41.10) Tier # 3 ------

Ability to prioritize and interpret the significance of each ------

Group # ------

annunciator or alarm.

K/A # G2.4.45 Importance Rating 4.1 ------

Proposed Question: # 75 Which ONE of the following describes the meaning of a WHITE magnetic border being installed on a Main Control Room panel annunciator?

This type of border indicates that the annunciator ______.

A. has ONE OR more alarm inputs disabled.

B. is associated with ongoing testing OR maintenance.

C. is "NOT ABNORMAL" for current plant conditions.

D. is an entry condition for EOI-3, Secondary Containment Control.

Proposed Answer: B Explanation A INCORRECT: In accordance with Annunciator Disablement, OPDP-4, a (Optional): blue magnetic boarder indicates that an alarm is out of service.

B CORRECT: In accordance with Annunciator Disablement, OPDP-4, a white magnetic boarder indicates that an alarm is out of service for TESTING or MAINTENANCE.

C INCORRECT: In accordance with Annunciator System, 0-OI-55, a hot pink boarder indicates that an alarm is "NOT ABNORMAL" for current plant conditions.

D INCORRECT: Entry conditions for Secondary Containment Control, EOI-3 are designated by an orange rectangle on an annunciator window.

Justification: Requires knowledge of Control Room Annunciator designators / boarders to effectively prioritize and interpret significance of alarms.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): OPDP-4 Rev. 4 (Attach if not previously provided) 0-OI-55 Rev. 46 Proposed references to be provided to applicants during examination: NONE Learning Objective: ___________________ (As available)

Question Source: Bank #

Modified Bank # Hatch 07 # 74 (Note changes or attach parent)

New Question History: Last NRC Exam Hatch 2007 (Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

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