ML092400601
| ML092400601 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 08/26/2009 |
| From: | NRC/RGN-II/DRS/OLB |
| To: | Duke Energy Carolinas |
| References | |
| 50-369/09-301, 50-370/09-301 | |
| Download: ML092400601 (228) | |
Text
FACILITY NAME: McGuire Nulear Plant Section'2 Section 2 .
REPORTNUMBER: ____~O~S~OO~O~3~69~~~7~Q~~~O~09~-~30~1~
~O~S~OO~O~3~69~~~7~o~n~O~09~-~30~1~_____
DRAFT RO WRITTEN EXAM CONTE~S:
CONTEr'"S:
ri Draft RO Written Exam (7SQ with ES-401-S ES-401-Slnformation)
Information)
Location of Electronic Files:
~======='~_____
Submitted By: ..r':::::::======::F'=-------- Verified By-l--"--f----"-'-~T-"-~~~~
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X X
Tier Tier# # 1 DRAFT Group # 1 KIA # 007EK1.06 Importance Rating 3.7 4.1 Reactor Trip - Stabilization - Recovery Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION:
Relationship of emergency feedwater flow to S/G and decay heat removal following a reactor trip.
Proposed Question: Common 1 1 Pt Given the following:
- An inadvertent isolation of the containment RN non-essential header has occurred
- A manual reactor trip was initiated and all NC pumps were secured 5 minutes ago
- The crew is performing the actions of ES-0.1 (Reactor Trip Response)
(
- NC System T-Hots are 575°F and slowly rising
- NC System T-Colds are 549°F and slowly lowering
- All S/G levels indicate 8% NR and rising slowly Which ONE (1) of the following describes the action(s) required in accordance with ES-0.1 for this condition?
A. Throttle open steam dumps or raise CA flow until NC system T-Hots are stabilized.
B. Close steam dumps and throttle CA flow to minimize cooldown; maintain total feed flow greater than 450 GPM.
C. Throttle open steam dumps or raise CA flow until NC system T-Ave is stable at or trending to 55rF.
D. Close steam dumps and throttle CA flow as necessary to stabilize NC system T -Colds; no other restrictions apply.
Page 1 of9 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: B Explanation (Optional):
When RCPs are not available (LOOP) then use Tcold as a measure of RCS temperature. With Tcold well below normal for no load conditions the appropriate action (per ES-O.1) is to attempt to limit the cooldown.
A. Incorrect: Thot will not stabilize as natural circulation sets up. The parameter to control is Tcold. Plausible if the candidate misunderstands that natural circulation is still being established and that with NC pumps secured, Tcold is the best indicator of conditions in the NC system (as opposed to Tave or Thot). With Thot increasing the candidate may believe that taking action to reduce Thot may be appropriate. The candidate may not understand that Tcold is well below normal Tcold for no load conditions and that actions should be taken to minimize the cooldown.
B. Correct.
C. Incorrect: Restrictions apply on minimum AFW flow when SG level is less than required (11 %). Plausible if the candidate misunderstands the given indications and believes that action should be taken (increasing
( steam dump or CA flow) to reduce Tave.
D. Incorrect: Closing the steam dumps and throttling CA flow is appropriate as stabilizing Tcold will limit the cooldown. However, the part of the distracter which states that there are no other restrictions is incorrect.
Plausible if the candidate does not recall that there is a minimum CA flow which must be maintained until S/G levels are greater than 11 % to ensure an adequate heat sink.
Technical Reference(s) ES-O.1, Reactor Trip (Attach if not previously Response, Rev.29, page 2-4 provided)
Lesson Plan OP-MC-EP-EO, (Including version or revision Reactor Trip or Safety #)
Injection, Rev. 12,93 -95 Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P_-_M_C_-_E_P_-E_O_O-----"bj'
_O_P-_M_C_-_E_P_-E_O_O-----' ---._6 bj'----. 6
_ ___ (As available)
(
Page 2 of9 Rev Final
ES-401 Sample Written Examination Form ES-40 1-5 Question Worksheet Question Source: Bank# x Modified Mod ified Bank # (Note changes or attach
_ _ _ parent)
New Question History: Last NRC Exam Shearon Harris 2007 NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.10 Content:
55.43 Comments:
Reactor Trip - Stabilization - Recovery Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION:
Relationship of emergency feedwater flow to S/G and decay heat removal following a reactor trip.
KA is matched because the candidate must understand that there is a minimum CA flow which must be maintained after a reactor trip until the minimum S/G levels (11 % % NR) are established to ensure that there is an adequate heat sink for decay heat removal.
This is a higher cognitive level question because the candidate must analyze multiple indications and conditions and determine the correct procedural strategy based on those conditions.
Page 3 of9 Rev Final
ES-401 Sample Written Examination ES-40 1-5 Form E8-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X Tier#
Tier # 1 DRAFT Group # 1 KIA # 011EK3.14 Importance Rating 4.1 4.2 Large Break LOCA Knowledge of the reasons for the following responses as they apply to the Large Break LOCA:
Rep RCP tripping requirement.
Proposed Question: Common 2 1 Pt Given the following conditions on Unit 1:
- "A" and "B" "S" NI pumps are TRIPPED
- "A" and "B" "S" NV pumps are TRIPPED
- NC system pressure is 250 PSIG
- All other equipment is running as designed
(
- Containment pressure is 8 PSIG
- E-O, Reactor Trip or Safety Injection has been implemented Which ONE (1) of the following describes the required action and reason for the action with respect to the NC pumps?
A. Stop all NC pumps to minimize fluid mass loss out of the break.
B.
S. Stop all NC pumps to prevent mechanical damage to the pump and motor.
C. Leave all NC pumps running to provide forced cooling flow of the NC system.
D. Leave all NC pumps running to prevent phase separation of NC system liquid.
Page 1 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: B Explanation (Optional):
A Large Break LOCA inside Containment has occurred. Containment pressure has exceeded 3 PSIG and therefore a Phase B isolation has occurred.
Therefore, cooling to the NC pump motors and thermal barriers is isolated.
Analysis assumes that the NC pumps are secured within 10 minutes of the Phase B signal to preclude overheating of the NC pump seals and motors.
A. Incorrect: See explanation above. Plausible because all NC pumps are stopped during a Small Break LOCA to minimize mass loss out of the break.
B. Correct.
C. Incorrect: See explanation above. Plausible because if this was a Small Break LOCA (and the Phase B had not occurred), the NC pumps would be left running since no NI or NV pumps are running.
D. Incorrect: See explanation above. Plausible because if the NC pumps remain in service during a Small Break LOCA and are subsequently secured, significant phase separation can occur resulting in fuel uncovery.
Consequently, the candidate may determine that it is reasonable to leave the NC pumps running during a Large Break LOCA to leave the NC
(
\
pumps running to prevent phase separation of the NC system fluid.
Technical OP-MC-EP-EO, Rev. 13 (Attach if not previously Reference(
Reference(s)s) -'p"--'page ac.:.sgcce--'337
~~-----------------
- ......7_ _ _ _ _ _ _ provided)
(Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-EP-EO,
_O-=-P: . . . -_M..:. .c:C:. . . -E=P:. . . --=Ec.. : . . 0'-Obj.
~--~-----
6
-'O-=--b:. . Lj.:......6=--_ (As available)
Question Source: Bank# EPEON02 Modified Bank (Note changes or attach parent)
New Question History: Last NRC Exam
(
Page 2 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Large Break LOCA Knowledge of the reasons for the following responses as they apply to the Large Break LOCA:
RCP tripping requirement.
KA is matched because the candidate must diagnose that a Large Break LOCA has occurred, there has been a Phase B Isolation, and that NC pumps have lost cooling water as a result of the Phase B and should be stopped.
This question is comprehension level as the candidate must associate two pieces of information one of which is given (Containment pressure at 8 psig) and one which must be recalled from memory (Phase B isolation which isolates all cooling
( water to the NCPs).
(
Page 3 of4of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X X
Tier # 2 DRAFT Group # 1 KIA #
KJA# 003K1.03 Importance Rating 3.3 3.6 Reactor Coolant Pump Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:
RCP seal system.
Proposed Question: Common 3 1 Pt Given the following conditions:
- Unit 1 is operating at 100% RTP
- AP-008 (Malfunction of NC Pump) has been implemented due to a seal malfunction on 1B NC pump Which ONE (1) of the following indicates that the failure is the 1B NC pump #2 Seal?
( A.. #1 Seal Leak off flow - GOING DOWN
- NC Pump number 2 Seal Standpipe low level alarm - LIT
- NCDT input - STABLE, OR GOING DOWN B.. #1 Seal Leak off flow - GOING DOWN
- NC Pump number 2 Seal Standpipe high level alarm - LIT
- NCDT input - GOING UP C.. #1 Seal Leak off flow - GOING UP
- NC Pump number 2 Seal Standpipe high level alarm - LIT
- NCDT input - GOING UP D.. #1 Seal Leak off flow - GOING UP
- NC Pump number 2 Seal Standpipe low level alarm - LIT
- NCDT input - STABLE, OR GOING DOWN
(
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: B Explanation (Optional):
On an NC pump #2 Seal Failure, the #2 seal passes more flow than normally designed. Since the #2 Seal Leakoff Leakoffflow flow goes to the #2 Seal standpipe, the standpipe level will increase (high level alarm) and overflowing to the NCDT causing NCDT level to increase.
The increased flow through the #2 seal will rob flow from the #1 seal leakoff thereby causing the #1 seal leakoff flow to decrease.
A. Incorrect: See explanation above. Plausible because the #1 seal leakoff flow increases. Standpipe low level alarm is plausible if the candidate does not understand where the standpipe taps of in relation to the #2 seal.
If the candidate believes that a low standpipe is plausible, it also gives plausibility to the NCDT level input being stable or going down.
B. Correct.
C. Incorrect: See explanation above. Plausible if the candidate does not understand where the seals tap off in relation to each other as it may be reasonable to assume that if flow increases through the #2 seal would also increase through the #1 seal (series flow path). Also, the standpipe
( level will increase as well as input to the NCDT.
D. Incorrect: See explanation above. Plausible if the candidate does not understand where the seals tap off in relation to each other as it may be reasonable to assume that if flow increases through the #2 seal would also increase through the #1 seal (series flow path). Standpipe low level alarm is plausible if the candidate does not understand where the standpipe taps of in relation to the #2 seal. If the candidate believes that a low standpipe is plausible, it also gives plausibility to the NCDT level input being stable or going down.
Technical AP-08, Malfunction of NC (Attach if not previously Reference(s)
Reference( s) Pump Background provided)
Document, Rev 1. Page 7 (Including version or
_ _ _ _ _ _ _ _ _ _ revision #)
Proposed references to be provided to applicants during None examination:
( Learning Objective: OP-MC-PS-NCP Obj. 12 (As available)
Page 2 of5 ofS Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank# PSNCPN04 Modified Bank (Note changes or attach
- _ _ _ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.3 Content:
55.43 Comments:
Reactor Coolant Pump Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:
RCP seal system.
( KA is matched because the candidate must understand the locations of the physical connections for the NC pump seal system in relationship to each other to be able to diagnose the effect of the #2 seal failure.
This question is higher cognitive level because the candidate must comprehend the effect of the #2 seal failure on other parameters. The candidate must analyze each individual answer to discern which answer fits the mental model for a #2 seal failure.
(
Page 3 of5 of 5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier # 2 DRAFT Group # 1 KIA #
KJA# 007 K5.02 Importance Rating 3.1 3.4 Pressurizer Relief I Quench Tank Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):
Method of forming a steam bubble in the PZR.
Proposed Question: Common 4 1 Pt Given the following:
- A startup is in progress on Unit 2 following refueling
- NC system is solid with one NC pump in service
- SU-8 (Heatup To 200°F) is in progress
- LTOP is in service
- NC system pressure is 360 PSIG
( Which ONE (1) of the following describes how bulk non-condensable gases are removed from the NC system prior to forming a bubble in the Pressurizer?
A. Cycle Pressurizer PORVs.
B. Vent the Volume Control Tank.
C. Cycle the Reactor Vessel Head vents.
D. Notify Primary Chemistry to add Hydrazine.
Proposed Answer: C
(
Page 1 of8 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Explanation (Optional):
There is no tie between the pressurizer and the PRT when forming a bubble at McGuire.
The Pzr is taken water solid first with non-condensables removed via the PORV's, then heated to saturation while water solid. After SU-8 is entered with the Pzr water solid, non-condensible gasses are removed from the Reactor Coolant System via the Rx Head Vents. Then letdown flow is increased to "draw" the bubble.
A. Incorrect: See explanation above. Plausible because the Pressurizer PORV could be used to vent the Pressurizer Steam Space.
B. Incorrect: See explanation above. Plausible because venting the VCT is the method by which the NC System is degassed in preparation for refueling.
C. Correct.
D. Incorrect: See explanation above. Plausible because adding Hydrazine will remove oxygen in solution from the NC System.
Technical OP/2/A/6100/SU-8, (Attach if not previously Reference( s)
Reference(s) Heatup to 200 degrees F, provided)
Rev. 30, Enclosure 4.2,
(
page 3 Lesson Plan OP-MC-PS- (Including version or NC, Reactor Coolant revision #)
System, Rev. 30, page 19 Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-PS-NC Obj.._4
_O_P-_M_C_-_P_S_-N_C_O_b.L..j 4_ _ (As available)
~-----
Question Source: Bank# 1121 Modified Bank (Note changes or attach
- _ _ _ _ parent)
New Question History: Last NRC Exam McGuire 2005 NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis Page 2 of8 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet 10 CFR Part 55 55.41 41.2 Content: to 41.9 55.43 Comments:
Pressurizer Relief I/ Quench Tank Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):
Method of forming a steam bubble in the PZR.
KA is matched because the candidate is required to know the methodology for removing non-condensable gasses from the NC System prior to bubble formation. Again, at MNS there is no tie between the Pressurizer and PRT with specific regards to drawing a bubble.
(
Page 3 of8 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X
Tier # 2 DRAFT Group # 1 KJA# 012A1.01 Importance Rating 2.9 3.4 Reactor Protection Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:
Trip Setpoint Adjustment Proposed Question: Common 5 1 Pt Given the following:
- Unit 2 is operating at 100% RTP
- Rod control in manual Which ONE (1) of the following will cause the Channel 2 OTilT OTL.\T trip setpoint to decrease?
A. N-42 upper detector fails high.
(
B. Auctioneered high T-ave fails high.
C. NC system wide range pressure channel fails low.
D. Power reduction to 50% with normal pressure and temperature.
(
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):
The N-42 upper detector failing high cause the L11 ~I input to go high which imposes
~ T trip setpoint causing it to be reduced.
a penalty on the OTL1 A. Correct.
B. Incorrect: The T-Ave input to each channel is loop T-Ave dependent and not from Auctioneered high T-Ave. Plausible because a high Loop T-avg will lower the setpoint for the individual OT ~T channel.
OTL1T C. Incorrect: The input to the OTL1 ~ T setpoint calculation is pressurizer pressure and not wide range pressure. Plausible because a lower pressurizer pressure would lower the setpoint.
D. Incorrect: Reducing power increases the OTL1 ~ T setpoint. Plausible if the student mistakenly believes that reducing power reduces the setpoint.
Technical Lesson Plan OP-MC-IC- (Attach if not previously Reference( s) _I_P_E..!-,_R_ev_._2_S--,--,
_I_P_E-,-, _R_ev_._2_8--,---,-,---p--,ag",--e_4_5
_ _ provided)
-,--pa---,9",---e_4_5__
(Including version or revision #)
(
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P_-M_C_-_IC_-_'P_E_O~bJ,---*.
_O_P-_M_C_-_IC_-_' P_E_O~bJ,,-*._1_0_ _ (As available)
Question Source: Bank# 1126 Modified Bank (Note changes or attach
_ _ _ parent)
New Question History: Last NRC Exam McGuire 2005 NRC Exam
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.5 Content:
55.43 Comments:
Reactor Protection Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:
Trip Setpoint Adjustment KA is matched because the candidate is being asked to predict a change in the trip setpoint associated with the Bloop OP L1 ~T reactor trip setpoint based on changes in parameters that affect this circuit. We do not "operate" the RPS system directly but for this particular Reactor Trip we do have a control board meter which indicates the current value of the associated variable setpoint. In order to correctly answer the question the candidate must demonstrate the ability to evaluate changes in the given parameters as to how this indication would respond.
(
This is a higher cognitive level question because the candidate must evaluate multiple inputs to the circuit and predict an outcome. This requires a multi-part mental process and both a knowledge and an understanding of how this circuit works.
(
Page 3 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X X X
Tier# 3 DRAFT Group #
KIA KJA## G2.1.1 Importance Rating 3.8 4.2 Conduct of Operations Knowledge of conduct of operations requirements.
Proposed Question: Common 6 1 Pt Per OMP 2-2 (Conduct of Operations), during NORMAL operations, which ONE (1) of the following would NOT require alerting plant personnel via the page?
A. Opening CF Isolation valves.
B. Starting a Safety Injection pump.
C. Initiation of Steam Generator Blowdown.
(
\
D. Starting a Reactor Makeup Water pump.
(
Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: D Explanation (Optional):
Alert plant personnel via the plant paging system prior to starting large motor/pump loads greater than 600V. NCO shall announce twice on the plant paging system the impending startup of the component by announcing "Attention station personnel, this is the Control Room, Operations will be ... " and giving the component system designator, unit number, train designator, and approximate time to start. Also, warn personnel NOT to stand near 4160 VAC or 6900 VAC busses when starting equipment powered from them.
Example: "Attention station personnel, this is the Control Room. Operations will be starting 1A KC Pump in 2 minutes. Personnel are advised to stand clear of the area and of 1ETA Switchgear."
Repeat announcement.
Exception: During the initial stages of an event that is being addressed by an AP or EP, announcing the impending start of a large motor is NOT required.
( Other plant equipment and evolution's meeting this requirement are:
- Starting Emergency Diesel Generators
- Starting Turbine Driven CA Pumps
- Opening/closing MSIVs
- Opening/closing Pzr PORVs
- Opening/closing CF isolation valves
- Opening/closing Main Steam PORVs and safeties
- Energizing 6900V and 4160V transformers
- Returning Main Buslines to service (closing PCBs)
- Latching and tripping of Main Turbine and CF Pump Turbines
- Initiation of Steam Generator Blowdown
- Evolutions with the potential for the release of high energy
- steam/fluids
- NCO feels an announcement is warranted to ensure personnel Safety Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
A. Incorrect: See above. Plausible because OMP 2-2 states that the NCO will "Alert plant personnel via the plant paging system prior to starting large motor/pump loads greater than 600V." However, other plant equipment and evolutions also meet this requirement. Opening/Closing of CF Valves is one of those evolutions which are specifically listed later in the procedure. If the candidate did not read or recall all of the required evolutions section, he/she could mistakenly conclude that only the starting of large motors/pumps was required to be announced.
B. Incorrect: See above. Plausible because OMP 2-2 specifically states that "During the initial stages of an event that is being addressed by an AP or EP, announcing the impending start of a large motor is NOT required." If the candidate mistakenly assumes that the starting of the SI Pump is during the performance of an EP, he/she could conclude that announcing of the SI Pump start was not required.
C. Incorrect: See above. Plausible because OMP 2-2 states that the NCO will "Alert plant personnel via the plant paging system prior to starting large motor/pump loads greater than 600V." However, other plant equipment and evolutions also meet this requirement. Initiating of Steam Generator Blowdown is one of those evolutions which are specifically listed later in the procedure. If the candidate did not read or recall all of the required evolutions section, he/she could mistakenly conclude that only
( the starting of large motors/pumps was required to be announced.
D. Correct. It is NOT required that the NCO announces starting a Reactor Makeup Water pump as this is a load is not greater than 600V.
Technical OMP 2-2, Rev. 47, page (Attach if not previously Reference(s)
Reference( s) _1_6_a_n_d_1_7_
_1_6=-----an_d=-----1_7 ____ __ __ _ _ provided)
Lesson Plan OP-MC- (Including version or revision ADM-OMP #)
Proposed references to be provided to applicants during None examination:
Learning Objective: Lesson Plan OP-MC- (As available)
ADM-OMP, Obj. 3 Question Source: Bank#
Bank # 1155 Modified Bank (Note changes or attach
- ________ parent)
(
\ New Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Question History: Last NRC Exam McGuire 2005 NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.10 Content:
55.43 Comments:
Conduct of Operations Knowledge of conduct of operations requirements.
KA is matched because the candidate must recall administrative requirements for announcing plant evolutions from OMP 2-2, Conduct of Operations.
(
{
\
Page 4 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 ES-40 1-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X Tier #
Tier# 1 DRAFT Group # 1 KIA # 040AG2.1.3 Importance Rating -4.6 ---
4.6 Steam Line Rupture Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the lineup_
desired plant lineup.
Proposed Question: Common 7 1 Pt Given the following:
- Unit 1 was operating at 100% RTP
- S/G 1B steam line breaks inside Containment
- Containment pressure is currently 4.0 PSIG Which ONE (1) of the following correctly describes CF system indications on the Main Control Board as a result of the above conditions?
(
A. A and B CF Pump Turbine Tripped annunciators - LIT 1CF-2 and 1CF-5 (CF Pump Discharge valves) indicate CLOSE B. A and B CF Pump Turbine Tripped annunciators - LIT 1CF-2 and 1CF-5 (CF Pump Discharge valves) indicate OPEN C. Both FWPT Lovejoy Controller OCS MAN indicators - LIT 1CF-2 and 1CF-5 (CF Pump Discharge valves) indicate CLOSE D. Both FWPT Lovejoy Controller OCS MAN indicators - LIT 1CF-2 and 1CF-5 (CF Pump Discharge valves) indicate OPEN
(
Page 1 of 5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: B 8
Explanation (Optional):
As a result of the Main Steam line break in Containment, an automatic Safety Injection signal and Feedwater Isolation (FWI) have occurred. The Safety Injection signal causes both CF pump turbines to trip. The FWI causes the S/G CF control and bypass valves to close, the S/G CF Containment isolation valves to close, and the CF to CA nozzle isolation valves to close. However, the CF pump discharge valves remain open.
A. Incorrect: See explanation above. Plausible because both FWPTs trip.
The CF pump discharge valves remain open. However, they would close if the Feedwater Isolation was due to a Hi-Hi Doghouse level.
B. Correct.
C. Incorrect: See explanation above. Plausible because the FWPTs go to Manual Speed Control on a Manual Feedwater Isolation and the CF pump discharge valves would close if the Feedwater Isolation was due to a Hi-Hi Doghouse level.
D. Incorrect. See explanation above. Plausible because the FWPTs go to Manual Speed Control on a Manual Feedwater Isolation and the CF Pump
( discharge valves remain open on both a Feedwater Isolation due to a Safety Injection signal or a Manual Feedwater Isolation.
Technical Lesson Plan OP-MC- (Attach if not previously Reference(s) ECC-ISE, Engineered provided)
Safeguards Actuation System, Rev. 31, page 35-37 (Including version or
_ _ _ _ _ _ _ _ _ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-ECC-ISE, Obj. 13 (As available)
Question Source: Bank#
Modified Bank (Note changes or attach
- _ _ _ _ parent)
( New xX Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.10 Content:
55.43 Comments:
Steam Line Rupture Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
KA is matched because the candidate is required to recall which CF system components operate/trip/reposition as a result of a Safety Injection signal caused by a Main Steam line rupture. He must then apply this to given control board indications to determine the components are correctly aligned.
This is a higher cognitive level question because the candidate must analyze
( plant conditions to determine that an automatic Safety Injection signal has been generated. Additionally, the candidate must understand that the automatic Safety Injection signal generates at trip of the CF pump turbines and a FWI signal.
(
Page 3 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier# 1 DRAFT Group # 1 KIA #
KfA# 008AK3.05 Importance Rating - 4.0
_4_._0__
4.5 Pressurizer Vapor Space Accident Knowledge of the reasons for the following responses as they apply to (Pressurizer Vapor Space Accident):
EGGS termination or throttling criteria.
ECCS Proposed Question: Common 8 1 Pt Given the following:
- Unit 1 was operating at 100% RTP
- A Pressurizer Safety valve sticks open
- The operating crew is currently performing the actions of E-1 (Loss of Reactor or Secondary Coolant)
Given and the following conditions at the following times:
Time 1500 1505 1510 1515
( S/G A (NR) [%] 25 9 27 30 S/G B (NR) [%] 24 10 28 29 S/G C (NR) [%] 26 9 30 31 S/G D (NR) [%] 29 10 33 31 CA Flow A S/G [GPM] 0 150 100 100 CA Flow B S/G [GPM] 0 160 105 105 CA Flow C S/G [GPM] 0 150 100 100 CA Flow D S/G [GPM] 0 160 100 100 NC pressure [PSIG] 1765 1750 1740 1775 Subcooling Margin [OF] +3 +2 +1 -1 Pzr Level [%] 15 13 9 14 Cont pressure [PSIG] 0 0 0.5 1.5 What is the earliest time (if any) that the operators can transition to ES-1.1 (Safety Injection Termination)?
A. 1505
(
B. 1510 Page 1 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
C. 1515 D. Not allowed to terminate safety injection, remain in E-1 Proposed Answer: 0D Explanation (Optional):
SI termination cannot be met at time 1505 because S/G NR levels are less than 11 11%% AND NC system pressure is decreasing. At time 1510 SI termination is not met because NC system pressure is still decreasing and PZR level is less than 11%. And, at time 1515 SI termination cannot be met because NC system subcooling is less than OaF. Therefore, SI termination cannot be met at any time given.
A. Incorrect: See explanation above. Plausible because minimum feedwater flow requirements are met, minimum Pressurizer level is met, and minimum subcooling is met. However, NC system pressure is decreasing. Therefore, SI Termination criteria are not met.
B. Incorrect: See explanation above. Plausible because minimum heat sink requirements are met and minimum subcooling is met. Also, the candidate
( may conclude that NC system pressure has turned and has now started to increase because of the pressure increase from time 1510 to time 1515.
However, minimum Pressurizer level is not met. Therefore, SI Termination criteria are not met.
C. Incorrect: See explanation above. Plausible because minimum heat sink requirements are met, minimum pressurizer level is met, and NC system pressure is now increasing. However, minimum subcooling requirements are no longer met. Therefore, SI Termination criteria are not met.
D. Correct.
Technical Reference(s) EP/1/A15000/E-1, EP/1/A/5000/E-1, Loss of (Attach if not previously ReactororSeconda~ provided)
Coolant, Rev. 11, Step 7 Lesson Plan OP-MC-EP-E1 (Including version or revision
- - - - - - - - - - #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P_-M_C_-_E_P_-E_1---,-,_O_b...Lj._2_ _ _ (As available)
_O_P-_M_C_-_E_P_-E_1---,-,_O_b..Lj._2 Page 2 of4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank# EPE1N017 Modified Bank # (Note changes or attach
_ _ _ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.5 Content: 41.10 55.43 Comments:
Pressurizer Vapor Space Accident Knowledge of the reasons for the following responses as they apply to (Pressurizer Vapor Space Accident):
( ECCS termination or throttling criteria.
The reasons (or basis) for SI Termination criteria are the same regardless of the accident. All termination criteria combined indicate that the NC is in a safe state with adequate core cooling and that Sfl S/I flow can be reduced without jeopardizing the safety of the plant. The reasons for the termination criteria are the same regardless of whether they are met during a Vapor Space Accident or a Spurious SI.
The only way to test this KIA is to provide indications that a Pressurizer Vapor Space accident is in progress (i.e. Pressurizer Safety or PORV stuck open) and have the candidate determine if SI Termination criteria is met.
For this question the KIA is matched because the candidate must evaluate each set of conditions and determine whether SI termination criteria is met which means they must know the REASONS why the criteria is met or not met.
This is a higher cognitive level question because the candidate must recall the criteria for terminating Safety Injection and must analyze multiple combinations of plant conditions to determine if SI termination criteria are met.
(
Page 3 of4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X
Tier# 1 DRAFT Group # 1 KIA # 009EK3.21 Importance Rating - 4.2
_4_._2__
4.5 Small break LOCA Knowledge of the reasons for the following responses as they apply to (Small break LOCA):
Actions contained in EOP for small break LOCAIbreak Proposed Question: Common 9 1 Pt Unit 2 is responding to a LOCA and the operators have reached step 28 of ES-1.2 (Post LOCA Cooldown and Depressurization) which requires isolating cold leg accumulators.
Which ONE (1) of the following states the purpose of this step?
A. To prevent CLA injection when the NC system depressurizes, resulting in thermal stress and PTS concerns from the cold water on the reactor vessel.
(
B. To prevent the addition of highly borated CLA water into containment with the potential for Boron crystallization after cooling down, possibly fouling the flow paths in the core.
C. To reserve the CLA water in the event of a re-criticality during the cooldown due to a loss of shutdown margin.
D. To prevent injecting the CLA nitrogen bubble into the reactor and creating a hard bubble in the Pressurizer.
(
Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: 0 D
Explanation (Optional):
In ES-1.2, the Operators are directed to determine if CLA should be isolated.
lAW the basis for this step, the accumulators are isolated to prevent nitrogen injection into the NC system which could result in a hard Pressurizer bubble or nitrogen could collect in high places in the NC system such as the S/G U-tubes.
A. Incorrect. See explanation above. Plausible because the accumulators will inject water into the NC system at a much colder temperature than water that remains in the system or the system piping. It is reasonable to believe that this could result in thermal stresses on the system. However, if the NC system pressure is low enough for the accumulators to inject, there is no PTS concern.
S. Incorrect: See explanation above. Plausible because the accumulators B.
do inject highly borated water into the NC system and it is reasonable to believe that the boron may crystallize out of solution at lower temperatures. However, this is an analyzed condition in that the water in the containment sump will not decrease to a low enough temperature post-accident to allow boron to come out of solution.
C. Incorrect: See explanation above. Plausible because as the system
( cools down, positive reactivity is added which will reduce shutdown margin. However, the addition of highly borated water due to injection via the NV NVand and NNII systems will increase the NC system boron concentration to a high enough level that loss of shutdown margin and a subsequent re-start accident is not a concern.
D. Correct.
Technical OP-MC-EP-E1 rev 18 (Attach if not previously Reference(s) page
-'p_a 134 _ _ _ _ _ _ provided)
......g'--e_1_3_4
~~-----------------
ES-1.2, Post LOCA (Including version or Cooldown and revision #)
Depressurization, rev. 11, page 37 Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-EP-E1 Objective 4 (As available)
(\
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet c
(
Question Source: Bank# EPE1038 Modified Bank (Note changes or attach parent)
New Question History: Last NRC Exam McGuire 2005 NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.5 Content: 41.10 55.43 Comments:
Small break LOCA Knowledge of the reasons for the following responses as they apply to (Small break LOCA):
Actions contained in EOP for small break LOCNbreak LOCAlbreak
(
KA is matched because must recall the basis for isolating Cold Leg Accumulators (CLA) during a Post LOCA Cooldown and Depressurization following a small break LOCA.
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 ES-40 1-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X Tier # 2 DRAFT Group # 1 KIA # 064K4.11 Importance Rating 3.5 4.0 Emergency Diesel Generator Knowledge of (Emergency Diesel Generator) design feature(s) and or interlock(s) which provide for the following:
Automatic load sequencer: safeguards Proposed Question: Common 10 1 Pt Which of the following best describes the Priority Mode of Diesel Sequencer operation?
A. Actuated by a Blackout signal and begins sequencing if bus voltage ONLY is greater than minimum required.
B. Actuated by a Blackout signal and begins sequencing if bus voltage AND frequency are greater than minimum required.
(
C. Actuated by a Safety Injection signal and begins sequencing if bus voltage ON ONLY LY is greater than minimum required.
D. Actuated by a Safety Injection signal and begins sequencing if bus voltage AND frequency are greater than minimum required.
(
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Proposed Answer: C Explanation (Optional):
The Sequencer has basically two modes of operation; The Priority Mode of operation is actuated by a Safety Injection signal from the SSPS. When Safety Injection is actuated, the signal seals in and sequencing begins immediately.
The Secondary Mode of operation is actuated by a 2/3 phase Loss of Voltage (LOV) on the 4160 Volt Essential Bus. Upon actuation, the sequencer starts the diesel and goes through an 8 second test for verification of a Blackout. If a Blackout does not exist, the Sequencer will automatically reset to its initial operating state and the Diesel Generator must be manually shut down. For an actual Blackout, the signal is sealed in, the 4160V bus normal and alternate incoming breaker is tripped, the 4160 Volt Essential Bus is load shed, and the Diesel Generator Breaker is closed provided the Diesel Generating unit has attained 95% speed.
A. Incorrect: See explanation above. Plausible if the candidate confuses the Blackout sequencer operation with the Safety Injection sequencer operation.
B. Incorrect: See explanation above. Plausible if the candidate confuses the
( Blackout sequencer operation with the Safety Injection sequencer operation.
C. Correct.
D. Incorrect: See explanation above. Plausible if the candidate confuses the Blackout sequencer operation with the Safety Injection sequencer operation.
Technical Lesson Plan OP-MC-DG- (Attach if not previously Reference( s)
Reference(s) EQB, Diesel Generator provided)
Load Sequencer, rev. 16, page 13 (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-DG-EQB, Obj. 3 (As available)
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Question Source: Bank# DGEQB006 Modified Bank (Note changes or attach
_ _ _ parent)
New Question History: Last NRC Exam NIA Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Emergency Diesel Generator Knowledge of (Emergency Diesel Generator) design feature(s) and or interlock(s) which provide for the following:
Automatic load sequencer: safeguards
( KIA is matched because the candidate must understand the design features of the different modes of operation of the Diesel Load Sequencer and apply this to a DIG start due to a given ESF signal.
(\
Page 3 of5of 5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X
Tier #
Tier# 1 DRAFT Group # 1 KIA # 054AA1.04 Importance Rating - 4.4
_4_._4
__ 4.5 Loss of Main Feedwater Ability to operate and/or monitor the following as they apply to (Loss of Main Feedwater):
HPI, under total feedwater loss conditions.
Proposed Question: Common 11 1 Pt Given the following conditions:
- The crew has entered FR-H.1 (Response to Loss of Secondary Heat Sink) due to a loss of inventory in the S/Gs and failure of the CA pumps to start Time 1400 1410 1420 1430 S/G 1A WR [%] 43 37 30 26
(
\
S/G 1B WR [%] 41 32 25 20 S/G 1C WR [%] 42 34 29 25 S/G 10 WR [%] 40 33 26 21 Total feed flow [GPM] 0 0 0 0 Cont press [PSIG] 0.75 2.1 3.2 2.8 Which ONE (1) of the following is the EARLIEST time (if any) that the crew would be required to initiate NC system Feed and Bleed based on plant conditions?
A. 1410 B. 1420 C. 1430
- o. Feed and Bleed is not required.
(
Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: B Explanation (Optional):
At time 1410 Feed and Bleed criteria is not met because S/G NR levels are greater than 24%. At time 1420, S/G NR levels are above those required for Feed and Bleed based on normal conditions in Containment. However, Containment pressure has increased above 3 PSIG requiring the use of adverse numbers (36%). Since all S/Gs are less than 36% NR level, initiation of Feed and Bleed is required.
A. Incorrect: See explanation above. Plausible because Feed and Bleed criteria would be met if the candidate determines that Adverse Containment numbers are applicable.
B. Correct.
C. Incorrect: See explanation above. Plausible if candidate does not understand the required number of S/Gs to meet Feed and Bleed criteria or that Adverse Containment numbers already applied in at previous time.
D. Incorrect: See explanation above. Plausible if candidate does not apply Adverse Containment numbers as S/G WR levels do NOT meet the criteria for Feed and Bleed without Adverse conditions.
(
Technical EP/1/A/5000/FR-H.1, Rev. (Attach if not previously Reference( s) _1_2-'
_1_2--'--,--',--'---p_a-"<.g_e_3
-p_a......
g_e_3_ _ _ _ _ _ provided)
Lesson Plan OP-MC-EP- (Including version or
_F_R_H-,-,
_F_R----.:H-'--,_R_e_v_._R-=.e_v_._10--,,-,-p_a--,,9<-e_3_1__
1_0......!,-,-p,-a-><9'-'.e_3,-1_ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: EPFRH003 (As available)
Question Source: Bank#
Modified Bank (Note changes or attach parent)
New x Question History: Last NRC Exam
(
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Loss of Main Feedwater Ability to operate and/or monitor the following as they apply to (Loss of Main Feedwater):
HPI, under total feedwater loss conditions.
KA is matched because candidate is provided with multiple sets of plant conditions (Monitor) and then apply the criteria for feed and bleed iniitialion for a loss of feedwater event. He must also recall the criteria for initiating feed and bleed (Safety Injection) under both normal and adverse conditions.
This is a higher cognitive level question because the candidate must analyze multiple sets of indications and apply adverse Containment condition numbers to determine when Feed and Bleed is required.
(
(
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X X
Tier#
Tier # 1 DRAFT Group # 2 KIA # WE09EK3.2 Importance Rating 3.2 3.6 Natural Circ.
Knowledge of the reasons for the following responses as they apply to (Natural Circ.):
Normal, abnormal, and emergency procedures associated with (Natural Circulation Operations).
Proposed Question: Common 12 1 Pt Given the following plant conditions:
- A reactor trip has occurred on Unit 1 as a result of a Loss of Offsite Power (LOOP)
- 1B EDG has started and loaded normally.
- 1A EDG did not start and attempts to start it have been unsuccessful
- The operating crew has entered ES-O.2 (Natural Circulation Cooldown)
(
- The crew is preparing to start a cooldown and depressurization using natural circulation Based on the conditions above, the required subcooling margin during the cooldown and depressurization is (1) based on (2)
A. (1) 50°F (2) preventing void formation in the reactor vessel head.
B. (1) 50°F (2) providing adequate thermal driving head for natural circulation.
C. (1) 100°F (2) preventing void formation in the reactor vessel head.
D. (1)100°F (1)1 OO°F (2) providing adequate thermal driving head for natural circulation.
(\
Page 1 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
With a Natural Circulation cooldown in progress and less than four VR fans available, ES-0.2 requires that a 100°F subcooling margin be maintained during the cooldown to prevent void formation/growth in the Reactor Vessel head during cooldown and depressurization.
A. Incorrect: See explanation above. Plausible because the candidate must understand that there are two different subcooling margin limits based on the number of CRDM fans in operation. The candidate must also comprehend that because one EDG failed to start, only two of the four CRDM fans are available requiring a higher subcooling margin.
Additionally, the second part of the distracter is plausible because subcooling margin is one of the parameters that is monitored during natural circulation cooldown as a check to determine if natural circulation flow is established. However, the reason for the limit on subcooling margin during cooldown and depressurization is to prevent void growth in the reactor vessel head.
B. Incorrect. See explanation above. Plausible because 50°F is the required subcooling margin limit if all CRDM fans are running. The
( candidate must realize that only two of the four CRDM fans are available.
The basis statement in this distracter is correct.
C. Correct D. Incorrect. See explanation above. Plausible because the subcooling margin limit is correct. However, the basis statement in this distracter is incorrect. The basis statement is plausible because subcooling margin is one of the parameters that is monitored during natural circulation cooldown as a check to determine if natural circulation flow is established.
However, the reason for the limit on subcooling margin during cooldown and depressurization is to prevent void growth in the reactor vessel head.
Technical EP/1/A/5000/ES-0.2, (Attach if not previously Reference( s) Natural Circulation provided)
Cooldown, Rev. 10, page 16 Lesson Plan OP-MC-EP- (Including version or EO, Rev. 12, pages 119- revision #)
121 and 136-140
(
Page 2 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during None examination:
Learning Objective: EPE0005, EPE0006
_E_P_E_0_0_0_5!--,E_P_E_0_0_0_6_ _ _ (As available)
~------------
Question Source: Bank#
Modified Bank (Note changes or attach
- _ _ _ _ parent)
New x Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.5 Content: 41.10 55.43
( Comments:
Natural Circ.
Knowledge of the reasons for the following responses as they apply to (Natural Circ.):
Normal, abnormal, and emergency procedures associated with (Natural Circulation Operations).
KA is matched because the candidate is required to recall the subcooling margin limits required by ES-0.2, Natural Circulation Cooldown and the basis for those limits.
This is a higher cognitive level question because the candidate must understand that the subcooling margin limits are based on the availability of VR fans and must analyze the plant conditions to determine that the number of VR fans available requires a 100°F subcooling margin limit to be applied.
(
Page 3 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier # 1 DRAFT Group # 1 KIA # 058AA1.03 Importance Rating 41.7 Loss of DC Power Ability to operate and/or monitor the following as they apply to (Loss of DC Power):
Vital and battery bus components.
Proposed Question: Common 13 1 Pt Given the following:
- A BLACKOUT has occurred on 1ETA
- DIG 1A failed to start due to an 86N relay actuation
- Annunciator PaneI1AD-11-B4 (Battery EVCA Undervoltage) is in alarm.
Per AP-15 (Loss of Vital or Aux Control Power) which ONE (1) of the following addresses the Battery EVCA undervoltage condition?
(
A. Cross tie EVDA to EVDB.
B. Cross tie EVDA to EVDC.
C. Swap Battery Charger Connection box to 2EMXH.
D. Swap Battery Charger Connection box to 2EMXA.
(
Page 1 of 11 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: 0 Explanation (Optional):
1ETA is de-energized and power cannot be restored due to the failure of 1A EDG. Therefore, EVCA must be swapped to its alternate power source which is 2EMXA on Unit 2.
A. Incorrect: See explanation above. Plausible because EVDA is the bus which is supplied by EVCA and cross-tying EVDA to another 125VDC Vital bus is a reasonable action.
B. Incorrect: See explanation above. Plausible because EVDA is the bus which is supplied by EVCA and cross-tying EVDA to another 125VDC Vital bus is a reasonable action.
C. Incorrect: See explanation above. Plausible because swapping EVCA to an alternate supply is the correct course of action and 2EMXH is an alternate supply for Battery Charger EVCS.
D. Correct.
( Technical Lesson Plan OP-MC-EL- (Attach if not previously Reference(s) _E_L_P_,!-R_e..:....v_.
_E_L_P-",-R_e_v_._ __ __ _ __ _____ provided)
OP/1/A/61 00101 00/01 0 L, (Including version or Annunciator Response for revision #)
PaneI1AD-11, Rev. 66, page 23 OP/1/A/5500/15, Loss of Vital or Aux Control Power, Rev. 20, Enclosure 1 page 4, step 4 and Enclosure 34 Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-EL-EPL Obj. 2 (As available)
Question Source: Bank #
Bank# ELEPLN04 Modified Bank (Note changes or attach
_ _ _ parent)
New Page 2 of 11 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Loss of DC Power Ability to operate and/or monitor the following as they apply to (Loss of DC Power):
Vital and battery bus components.
KA is matched because candidate must understand the normal lineup of the Vital I&C System (120 VAC EPG) system and how the system is aligned/operated under abnormal conditions.
This is a higher cognitive level question because the candidate must analyze the condition and determine that with the Blackout on 1ETA and the failure of the 1A
( EDG, EVCA must be energized from an alternate source. Then the candidate must also recall that the alternate source for supplying EVCA is 2EMXA on Unit 2.
{
Page 3 of 11 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier # 2 DRAFT Group # 1 KJA# 004K5.50 Importance Rating 2.6 Chemical and Volume Control System:
Knowledge of the operational implications of the following concepts as they apply to the NV system:
Design basis letdown system temperatures: resin integrity Proposed Question: Common 14 1 Pt Given the following on Unit 1:
- LD HX outlet temperature is 115°F and increasing If LD Hx outlet temperature reaches (1) 1NV-127A (LD Hx Outlet 3-Way Temp Cntrl) will AUTO divert letdown flow to the (2)
(
A. (1) 138°F (2) VCT to protect the demineralizer resin B. (1) 138°F (2) RHT to protect the VCT from over temperature C. (1) 120°F (2) VCT to protect the demineralizer resin D. (1) 120°F (2) RHT to protect the VCT from over temperature
(
Page 1 of 5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):
As letdown temperature increases to 138°F 1NV-127A will divert letdown flow to the VCT to protect the demineralizer resin.
A. Correct.
B. Incorrect: See explanation above. Plausible because there is a diversion flow path to the RHT. However, that diversion of letdown flow is on VCT high level.
C. Incorrect: See explanation above. Plausible because 1NV-127A does divert to the VCT on high temperature. Also, the Letdown Heat Exchanger Outlet Hi Temperature annunciator alarms at 120°F.
D. Incorrect: See explanation above. Plausible because there is a diversion flow path to the RHT. However, that diversion ot'letdown flow is on VCT high level. Also, the Letdown Heat Exchanger Outlet Hi Temperature annunciator alarms at 120°F.
Technical LP OP-MC-PS-NV (Rev (Attach if not previously
( Reference(s) 55) Pg 35 of 153 Section provided) 2.14 OP/11A161 OP/1/A/61 001010 00/010 H (Including version or (Annunciator Response for revision #)
Panel 1AD-7) Pg 37 of 52
( Rev 57)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-PS-NV Obj 10
_O_P-_M_C_-_P_S_-N_V_O_b'----j
~-----
1_0_ _ (As available)
Question Source: Bank#
Modified Bank (Note changes or attach
_ _ _ _ parent)
New x Question History: Last NRC Exam
(
Page 2 of5 ofS Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.5 Content:
55.43 Comments:
Chemical and Volume Control System:
Knowledge of the operational implications of the following concepts as they apply to the NV system:
Design basis letdown system temperatures: resin integrity KA is matched because the candidate must be familiar with the letdown design basis maximum temperature. He/she must also know the operational implication (letdown auto divert to the VCT) should that temperature be reached.
(
(
Page 3 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X X
Tier # 2 DRAFT Group # 1 KIA # 008K3.03 Importance Rating _4_._1 4.1 _ _ 4.2 Component Cooling Water Knowledge of the effect that a loss or malfunction of the (Component Cooling Water System) will have on the following:
Rep RCP ,
Proposed Question: Common 15 1 Pt Given the following conditions on Unit 1:
- A small break LOCA occurred in Containment
- SI has actuated on both trains
- 1B NV pump tripped on overcurrent
- Containment pressure is 3.5 PSIG Based on the above conditions ALL cooling would be lost to the ...
(
A NC pump seals ONLY.
A.
B. NC pump motor bearings ONLY.
C. NC pump seals AND pump lower bearings.
D. NC pump motor bearings AND pump lower bearings.
(
Page 1 of6 of 6 Rev Final
ES-401 Sample Written Examination ES-40 1-5 Form ES-401-5 Question Worksheet Proposed Answer: 8 B
Explanation (Optional):
Due to the LOCA, pressure inside Containment has increased such that a Safety Injection signal and a Phase B isolation signal have been generated. The Phase B signal has resulted in Component Cooling Water (KC) being isolated to Containment. The KC isolation results in a loss cooling to the NC pump motor bearing coolers and to the NC pump thermal barrier. However, NC pump seal injection is maintained because 1A NV pump remains in service. NC pump lower bearing temperatures will increase slightly due to the loss of cooling to the NC pump thermal barriers. However, ALL cooling to the lower pump bearings has NOT been lost because seal injection flow is maintained.
A. Incorrect: See explanation above. Plausible if student believes that NC pump seal injection has been lost because of the Phase B B isolation or the 1B B
NV pump trip.
B. Correct.
C. Incorrect: See explanation above. Plausible if student believes that NC pump seal injection has been lost because of the Phase B isolation or the 1B
( NV pump trip. Also, while there is a slight increase in lower bearing temperatures due to the loss of KC to the thermal barrier, the primary cooling for the lower bearing which is seal injection has not been lost.
D. Incorrect: See explanation above. Plausible if student believes that NC pump seal injection has been lost because of the Phase B B isolation or the 1B B
NV pump trip and KC has been lost. Seal injection is maintained because the 1A NV pump is .still still running. Therefore, only KC has been lost. Cooling to the NC pump motor bearings and thermal barrier has been lost. The loss of KC to the thermal barrier will cause a slight increase in lower bearing temperatures.
However, all cooling has not been lost since seal injection is still maintained.
Technical OP-MC-PSS-KC, rev. 24, (Attach if not previously Reference(s) --'pp'-a-"g<-e_1_3_a_n_d_3_5
..... _a--"'g'----e_1_3_a_n_d_3_5_ _ _ _ provided)
(Including version or
_ _ _ _ _ _ _ _ _ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P-_M_C_-_P_S_S_-K_C---,,_O_b--,--j
_O_P-_M_C_-_PS_S_-_K_C-,-,O----"bj,--.._4_ _ (As available) 4_
(
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank# PSNCPN020 Modified Bank (Note changes or attach
_ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Component Cooling Water Knowledge of the effect that a loss or malfunction of the (Component Cooling Water System) will have on the following:
RCP KA is matched because the candidate must understand how the KC system is
( affected on a Phase B Signal (i.e. KC cooling lost to NCPs) and resulting effects on NC system components.
This is a higher cognitive level question because the candidate must analyze given plant condition to determine that KC cooling to the NC pumps has been isolated as a result of the Phase B isolation and that NC pump seal injection is still in service.
(
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: XX X X
Tier# 2 DRAFT Group # 1 KfA# 010A4.01 Importance Rating 3.7 3.5 Pressurizer Pressure Control Ability to manually operate and/or monitor in the Control Room:
PZR Spray Valve Proposed Question: Common 16 1 Pt Given the following initial conditions:
- Unit 2 is operating at 100% RTP
- PZR Channel Select is in 1-2 position
- NC system pressure is 2235 PSIG The following occurs:
- The OATC notices that 2NC-27 (Pressurizer Spray Control) is full
( open
- 2NC-29C (Pressurizer Spray Control) is closed
- NC system pressure is decreasing
- Attempts to close 2NC-27 using its controller have been unsuccessful Which ONE (1) of the following describes the actions required (if any) to stop the NC system pressure decrease?
A. The operating crew must manually trip the Reactor and stop 2A NC pump.
B. No action required as the Pressurizer Spray valves will be automatically blocked at 2185 PSIG.
C. The operating crew must manually place the Pressurizer Spray Emergency Close switch to the close position.
D. No action required since the Pressurizer Backup heaters will energize at 2210 PSIG and stop the pressure decrease.
(
Page 1 of 14 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
At a pressure of 2235 PSIG, 2NC-27 should not be open and manual action must be taken to stop the pressure decrease. The operator must use the Pressurizer Spray Emergency close switch to cause 2NC-27 to go closed.
A. Incorrect: See explanation above. Plausible because is AP-11 requires the NC pump to be stopped but, only if the reactor is tripped, the spray valve is still open, and pressure is decreasing.
B. Incorrect: See explanation above. Plausible because the PZR PORVs are automatically blocked at 2185 psig.
C. Correct.
D. Incorrect: See explanation above. Plausible because backup heaters do energize at 2210 psig. However, they do not have sufficient capacity to stop the pressure decrease with a spray valve fully open.
Technical Reference(s) OP-MC-PS-IPE, Rev. 27, (Attach if not previously
-'p_a-"9<-e_2_7_a_n_d_6_8
-'p'--'a......9!....:.e_2-'-7_a-'-n-'-d_6-'_ -8"----___ _ _ provided)
AP/2/A/5500/11 , Pressurizer AP/2/A/5500/11, (Including version or revision
( Pressure Anomalies, Rev. #)
10, page 2-4 Proposed references to be provided to applicants during None examination:
Learning Objective: _O-=--=--P----=--M:."-.C~-...:....P__=_S-'-I_'_P=E-'---,
OP-MC-PS-IPE, 0--=---.
~~~------
Obj.
.: . lb.jL-.5
.:. . 5_ _ _ (As available)
Question Source: Bank#
Modified Bank (Note changes or attach
- -_- __ -_ - parent)
New x Question History: Last NRC Exam
(
Page 2 of14 of 14 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Pressurizer Pressure Control Ability to manually operate and/or monitor in the Control Room:
PZR Spray Valve KA is matched because the operator is required to determine that the spray valve has failed open and determine the appropriate manual action to stop the pressure decrease.
This is a higher cognitive level question because the candidate must analyze a set of conditions and determine a correct course of action.
(
Page 3 of 14 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X X
Tier Tier# # 1 DRAFT Group # 1 KIA # 062AG2.2.40 Importance Rating 3.4 Loss of Nuclear Service Water Generic: (Ability to apply technical specifications for a system)
Proposed Question: Common 17 1 Pt Given the following:
- Unit 1 is shutdown
- NC system temperature is 140°F
- 'A' Train components are in operation
- 1B EDG is tagged for maintenance
- The NC system WR level is 55 inches Given the following events occur:
(
- The 1A RN pump trips on overcurrent
- The operating crew has completed the actions of AP-20 Case 1 (Loss of Operating RN Train)
What actions are required (if any) per Tech Spec 3.7.7 (Nuclear Service Water system)?
SeNice A. RN is not required to be Operable in Mode 5:
No action is required per this LCO.
B. Only ONE train of RN is required to be Operable:
No action is required per this LCO.
C. BOTH trains of RN are required to be Operable:
Enter the applicable action statement of TS 3.7.7.
D. Only ONE train of RN is required to be Operable but must have Emergency Power available:
Enter the applicable Action Statement of TS 3.7.7.
(
Page 1 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):
SeNice Water System is applicable in Technical Specification 3.7.7, Nuclear Service Modes 1-4. It is given that the Unit is in Mode 5. Therefore, TS 3.7.7 is not applicable.
A. Correct.
B. Incorrect: See explanation above. Plausible because many of our LCO's require only one train in Mode 4 or 5.
C. Incorrect: See explanation above. Plausible because the candidate may think this T.S. is applicable in Mode 5 and/or SLC 16.5.2 requires both trains to be available but not operable.
D. Incorrect: See explanation above. Plausible because SLC 16.5.2 requires both trains of RN to be available with the RCS at reduced inventory.
Technical T.S. 3.7.7, Nuclear (Attach if not previously Reference(s)
Reference(s) SeNice Water System Service provided)
(
SLC 16.5.2, Power (Including version or Systems and Decay Heat revision #)
Removal - Reduced Inventory Operation Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-PSS-RN Obj. 17 (As available)
Question Source: Bank #
Bank#
Modified Bank (Note changes or attach
- _ _ _ _ parent)
New x Question History: Last NRC Exam
(
Page 2 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.10 Content:
55.43 Comments:
Loss of Nuclear Service Water Generic: (Ability to apply technical specifications for a system)
KA is matched because the candidate is being asked to determine the applicability of TS 3.7.7 LCO to a Loss of RN scenario with the plant shutdown on RHR cooling.
This is a higher cognitive level question because the candidate must analyze plant conditions and determine that TS 3.7.7, Nuclear SeNice Service Water System is not applicable in the current mode.
(
(
Page 3 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X X
Tier# 1 DRAFT Group # 1 KIA # WE11EK1.2 Importance Rating 3.6 4.1 Loss of Emergency Coolant Recirc Knowledge of the operational implications of the following concepts as they apply to the Loss of Emergency Coolant Recirc:
Normal, abnormal, and emergency procedures associated with (Loss of Emergency Coolant Recirc.)
Proposed Question: Common 18 1 Pt Given the following conditions:
- A LOCA has occurred on Unit 1
- All ECCS pumps are taking suction from the FWST
- FWST level is 100 100 inches
- Containment sump level is 1.5 feet
(
Which ONE ON E (1) of the following describes the operational implications of implementing ECA 1.1?
A. Attempts are made to locate and isolate the cause of the loss of inventory from containment and makeup is initiated to the FWST. NC system is cooled down and depressurized to allow the CLA's to inject.
B. Attempts are made to locate and isolate the cause of the loss of inventory from containment and makeup is initiated to the FWST. NC System is cooled down, depressurized and placed on RHR cooling.
C. Containment spray and Injection flow are minimized, makeup is initiated to the FWST, NC System conditions are maintained stable until FWST and containment sump inventories are recovered or ECR capability is restored.
D. Containment spray and Injection flow are minimized, attempts are made restore ECR, makeup is initiated to the FWST, and the NC System is cooled down, depressurized and placed on RHR cooling.
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: D Explanation (Optional):
A. Incorrect: The first part of this answer is the right strategy wrong procedure; these actions are performed in ECA 1.2 (LOCA Outside Containment). Plausible Because the given information in the stem do not indicate that actions in ECA 1.2 have been performed and this would be a reasonable course of action for the given situation. The second part of this answer is correct though not complete.
S.
B. Incorrect: See explanation above. Plausible: As described above and the second part of the answer is correct and more complete.
C. Incorrect: Maintain plant conditions stable is not part of the strategy in ECA 1.1, if ECR capability is not recovered, a plant cooldown and depressurization is performed and the core is placed on RHR cooling.
Plausible The majority of this answer is correct, only the end point of the procedure is incorrect.
D. Correct.
( Technical Lesson Plan OP-MC-EP- (Attach if not previously Reference(s)
Reference( s) E1, rev. 18, page 194 & provided) 196 (Including version or
_ _ _ _ _ _ _ _ _ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P-_M_C_-_E_P_-E_1....!..,_O_b___
j._3
_O_P-_M_C_-_E_P_-E_1---,-,_O_b..Lj ._3_ _ (As available)
Question Source: Bank#
Modified Bank (Note changes or attach
- _ _ _ _ parent)
New x Question History: Last NRC Exam
(
Page 2 of5 ofS Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.8 Content: to 41.10 55.43 Comments:
Loss of Emergency Coolant Recirc Knowledge of the operational implications of the following concepts as they apply to the Loss of Emergency Coolant Recirc: Normal, abnormal, and emergency procedures associated with (Loss of Emergency Coolant Recirc.)
KA is matched because is given a scenario where a loss of ECR has occurred and ECA 1.1 is being implemented. He is then required to recall what operational strategies are directed by this procedure in order to mitigate this condition.
(
(
Page 3 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet i
\
Examination Outline Cross- Level RO SRO reference: X X Tier # T2 DRAFT Group # G1 KIA #
KfA# 073K3.01 Importance Rating 3.6 Process Radiation Monitoring:
Knowledge of the effect that a loss or malfunction of the (System) will have on the following:
Radioactive effluent releases.
Proposed Question: Common 19 1 Pt Given the following:
- Unit 1 is shutdown in Mode 5
- A purge of the Containment atmosphere is in progress
- Personnel are preparing for refueling operations Which ONE (1) of the following is a list of the automatic action(s) that will occur if 1EMF-38(L) (Containment Particulate Low Range) experiences a loss of power?
(
A. VQ secured ONLY.
B. VQ and VP secured ONLY.
C. VQ secured, VP secured, Containment Sump pumps 1A1, 1A2, 1B1, 1B2 and Incore Sump pump secured ONLY.
D. VQ secured, VP secured, Containment Sump pumps 1A1, 1A2, 1B1, 1B2 and Incore Sump pump secured, Containment evacuation alarm sounded.
(
Page 1 of5of 5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Proposed Answer: C Explanation (Optional):
VQ and VP are secured. Also, Containment Sump pumps (1A (1A1, 1, 1A2, 1B1, 1B2) and Incore Sump pump are secured.
A. Incorrect: See explanation above. Plausible because upon a loss of power to a process monitor EMF, the associated RP-86 modual will "fail safe". This would result in a "Trip 2 Condition and any control functions associated with that EMF would ocurr. While a Trip 2 of EMF-38 (L) would result in a VQ isolation the question asked for a complete list of auto actions.
B. Incorrect: See explanation above. Plausible because both of the actions stated in this distracter would occur but once again, it is not a complete list.
C. Correct.
D. Incorrect: See explanation above. Plausible because these are all actions which would occur if power was lost to 1EMF-39(L) under the given plant conditions. Additional plausibility is added by the fact that 1EMF-39(L) is contained within the same detector package as 1EMF-( 38(L).
Technical Lesson Plan OP-MC-WE- (Attach if not previously Reference(s) EMF, Rev 29 Pg 25 & 59 provided)
(Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P_-_M_C_-W_E_-E_M_F_O----"bj'--.
_O__P_-M_C_-_W_E_-_E_M_F_O_b-Lj_.3 _ _ (As available)
Question Source: Bank# Ques 46E Modified Bank (Note changes or attach
- _________ parent)
New Question History: Last NRC Exam McGuire 1999 NRC Exam
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination ES-401-5 Form ES-40 1-5 Question Worksheet
( Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Process Radiation Monitoring:
Knowledge of the effect that a loss or malfunction of the (System) will have on the following:
Radioactive effluent releases.
KA is matched because the question requires the candidate to understand the effect of a loss of power (malfunction) to 1EMF-38(L) (Process radiation monitor) on Containment Purge (VP) (A radioactive effluent release).
(
Page 3 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X Tier #
Tier# 1 DRAFT Group # 1 KJA#
KfA# 022AK1.03 Importance Rating 3.0 Loss of Rx Coolant Makeup Knowledge of the operational implications of the following concepts as they apply to the (Loss of Rx Coolant Makeup) :
Relationship between charging flow and PZR level.
Proposed Question: Common 20 1 Pt Given the following:
- 1NV-241 (Seal Water Injection Flow Control) failed closed and cannot be reopened.
- Normal UD LID has been isolated
- Excess UD LID has been placed in service at a flow rate of 26 GPM
- Seal Injection is presently 7 GPM per NC pump
(
- Total NC pump seal leak off flow is 12 GPM
- PZR level is 44%
Assuming no further operator action is taken, how long will it take for the PZR Heater feeder breakers to trip open?
REFERENCE PROVIDED A. 164 Minutes B. 180 Minutes C. 360 Minutes D. 520 Minutes Page 1 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
In this question the failure of 1NV-241 has resulted in the loss of normal charging but the seal injection flow path remains available. Placing excess LID in service at 26 GPM and adjusting Seal Injection flow to 7 GPM per NCP has established a flow imbalance between make up to, and LID from the Reactor Coolant System of 10 GPM.
- 26 GPM (Excess LID)
- 16 GPM (28 GPM Seal Injection minus 12 Seal Leak Off) 10 GPM (Total Makeup to the NC System) 44% PZR level represents a volume of 6400 Gallons 10% PZR level represents a volume of 2800 Gallons This represent a difference of 3600 Gallons With no further operator actions, at a net loss of 10 GPM exists and at this rate of inventory loss, it would talk approximately 360 minutes for the PZR level to drop from 44% to 17%.
(' A. Incorrect: See explanation above. 90 Minutes is plausible if the
\
candidate miscalculates the total loss from the NC system by counting the seal leak off flow as letdown (38 GPM Out) and 16 GPM total makeup (28 GPM Seal Injection minus 12 GPM seal leak off). This would yield a difference of 22 GPM and if true, it would take 164 minutes for PZR level to reach 17%
B. Incorrect: See explanation above. 100 Minutes is plausible if the candidate believes that all of the seal injection (28 GPM) - 12 (GPM) out yielding 16 can be considered NC system makeup, and uses the Excess LID flow rate (26 GPM) plus the seal leak (12) off as the volume out. (38 GPM)(Correct) This would yield a difference of 20 GPM resulting in a time of 100 minutes to reach 17%
C. Correct. As stated in the explanation above, 360 minutes is correct D. Incorrect: See explanation above. This answer is plausible if the candidate believes that the PZR heaters trip at 4% vs. 17%. The 4% is the level at which the charging pump suction auto aligns to the FWST.
There is plausibility with this level because auto actions do occur but not the PZR heater trip. If the correct flow balance numbers are used, (net loss of 10 GPM) and a volume of 1200 yielding a net change of 5200 Gal, the resulting time would be 520 minutes.
(
Page 2 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical OP/11A161 OP/1/A/61 00/22 Curve (Attach if not previously Reference(s)
Reference( s) ----'7c.....:...3-=-8~R-=-ev_=_4_=_3_=_4_=_________
7.38 Rev 434 provided)
Lesson Plan PS-NV Pg 5, (Including version or 37 revision #)
Proposed references to be provided to applicants during OP/11A161 OP/1/A/61 00/22 examination: Curve 7.38 Rev 434 Learning Objective: PS-NV-#4 (As available)
PS-ILE #9 Question Source: Bank#
Modified Bank X (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Fu ndamental Knowledge
( Level:
Comprehension or Analysis X X
10 CFR Part 55 55.41 41.8 Content:
55.43 Comments:
Loss of Rx Coolant Makeup Knowledge of the operational implications of the following concepts as they apply to the (Loss of Rx Coolant Makeup) :
Relationship between charging flow and PZR level.
KA is matched because the Unit has experienced a Loss of Normal Rx Coolant M/U capability due to the failure of 1NV-241, when closed isolates the charging flow path downstream of the split between the seal injection and the piping to the Regenerative HX and ultimately the Rx coolant system. The only makeup flowpath remaining is via seal injection. The candidate must then evaluate the relationship between a much reduced make up flow rate and an existing let down flow rate and then determine the effect over time on the PZR level.
This is a higher cognitive level question because the candidate must analyze
( plant conditions, determine the net loss from the NC system and then using the
\
reference provided, calculate the time for Pressurizer level to decrease to 17%.
Page 3 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Examination Outline Cross- Level RO SRO reference: X X X X
Tier Tier# # 2 DRAFT Group # 2 KJA# 015K5.02 Importance Rating 2.7 2.9 Nuclear Instrumentation Knowledge of the operational implications of the following concepts as they apply to the (Nuclear Instrumentation SYSTEM):
Discriminator/compensation operation.
Proposed Question: Common 21 1 Pt Which ONE ON E (1) of the following describes the effect of an UNDER-COMPENSATED Intermediate Range Channel following a Reactor Trip?
A. Channel will indicate high, Source Ranges will correctly energize due 1/2 logic.
B. Channel will indicate low, prematurely energizing the Source
( Ranges due to 1/2 logic.
C. Channel will indicate low, Source Ranges will not energize until P-6 is met from other Channel due to 2/2 logic.
D. Channel will indicate high, preventing P-6 from automatically energizing the Source Ranges as designed due to not satisfying 2/2 logic.
Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Proposed Answer: D Explanation (Optional):
An under-compensated IR channel will indicate neutron flux and gamma flux causing the indication to be higher than normal. This will cause the effected IR 10 channel to remain above the P-6 setpoint (10- 10 amps). Since P-6 is a 2/2 logic the permissive will not be met which will prevent the Source Ranges instruments from automatically energizing.
A.
A Incorrect: See explanation above. Plausible if the candidate confuses how the P-6 permissive functions to enable manual blocking and automatic unblocking of the Source Range channels.
B. Incorrect: See explanation above. Plausible if the candidate confuses how gamma compensation affects the IR indication and confuses how the P-6 permissive functions to enable manual blocking and automatic unblocking of the Source Range channels.
C. Incorrect: See explanation above. Plausible if the candidate confuses how gamma compensation affects the IR indication.
D. Correct.
(
Technical OP-MC-IC-ENB, rev. 27, (Attach if not previously Reference(s)
Reference( s) pages 22 and 244_ _ _ _ provided)
'p:....c:a--"'9c..:..e...:....s_2_2-=-a_n...:....d_2__
~~----------------
(Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O __ P-_M_C_-_IC_-_E_N_B..!...,_O~bJL-'.
_O_P-_M_C_-_IC_-_E_N_B...!-, _O~bJL-*._7___
_ _ (As available)
Question Source: Bank# ICENB018 Modified Bank (Note changes or attach
- _ _ _ _ _ parent)
New Question History: Last NRC Exam
(
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.5 Content:
55.43 Comments:
Nuclear Instrumentation Knowledge of the operational implications of the following concepts as they apply to the (Nuclear Instrumentation SYSTEM):
Discriminator/compensation operation.
KA is matched because the candidate is required to understand the operation of gamma compensation on the IR Excore Nuclear Instrument detectors and the P-6 permissive logic for the SR channels.
This is a higher cognitive level question because the candidate must associate multiple data points both given and recalled from memory. The given data point is that one of the IR channels is under-compensated. The candidate must then
( recall from memory how gamma compensation affects the IR channel indication and recall how the P-6 permissive logic works to deduce the correct answer.
(
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X Tier # 2 DRAFT Group # 1 KIA # 039G2.2.38 Importance Rating _3-=-.3.6
- c. .: .6_ _ 4.5 Main and Reheat Steam Knowledge of the conditions and limitations in the facility license.
Proposed Question: Common 22 1 Pt lAW Tech Spec 3.7.1 (Main Steam Safety Valves), the FIRST safety valve is set to open at (1) PSIG and the LAST safety valve is set to open at (2) PSIG.
A. (1) 1125 (2) 1205 B. (1) 1170 (2) 1220
( C. (1) 1170 (2) 1225 D. (1) 1190 (2) 1225
(
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
Opening setpoints from TS 3.7.1:
SM PORV - 1125 PSIG st MSSV -1170 1st - 1170 PSIG nd 2 nd MSSV - 1190 PSIG 3 rd rd MSSV - 1205 PSIG 4th MSSV - 1220 PSIG 5th th MSSV -1225
- 1225 PSIG A. Incorrect: See setpoints listed above. Plausible because 1125 psig is the opening setpoint for the Main Steam PORVand PORV and 1205 psig is the opening rd setpoint for the 3rd MSSV.
B. Incorrect: See setpoints listed above. Plausible because 1170 psig is the opening setpoint for the first MSSV. However, 1220 psig is the opening setpoint for the 4th MSSV.
C. Correct.
D. Incorrect: See setpoints listed above. Plausible because 1190 psig is the nd
( opening setpoint for the 2 nd MSSV and 1225 is the opening setpoint for the last MSSV.
Technical TS 3.7.1 (Main Steam (Attach if not previously Reference(s)
Reference(s) _S-,--a,--f_et.cLy_V-,a_lv-,e_sL-)
_S_a_f....:....et-LY--,V_a_lv--,e_sL-)_ _ _ _ provided)
OP-MC-STM-SM, rev. 25, (Including version or
-'--pa-'g"-e_23
---'p'-a-"g<-e_2_3_ __ __ __ ____ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-STM-SM, Obj. 7 (As available)
Question Source: Bank# STMSM020 Modified Bank (Note changes or attach
- _ _ _ _ _ parent)
New Question History: Last NRC Exam Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content: 41.10 55.43 Comments:
Main and Reheat Steam Knowledge of the conditions and limitations in the facility license.
KA is matched because the candidate is required to recall the Main Steam relief setpoints associated LCO 3.7.1. (Main Steam Safety Valves). Knowledge of these values represents knowledge of the limiting condition of operation for these components as stated in tech specs which are part of the facility license.
(
Page 3 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Examination Outline Cross- Level RO SRO reference: X Tier # 2 DRAFT Group # 1 KIA # 026G2.1.32 Importance Rating 3.8 Containment Spray (NS):
Generic: Ability and explain and apply all system limits and precautions.
Proposed Question: Common 23 1 Pt Which ONE (1) of the following is the basis for the minimum temperature of the FWST as it relates to a Containment Spray actuation?
A. Prevent soluble boron from coming out of solution which could result in clogging of the NS spray nozzles and reduced spray flow.
B. Prevent an excessive reduction in containment pressure, which could decrease the rate at which steam can be vented out the
( break and increases peak clad temperature.
C. Prevent exceeding the maximum external pressure load on the containment shell due to an internal vacuum caused by overcooling of the Post-Accident Containment atmosphere.
D. Prevent thermal shock of NS system piping specifically the NS spray nozzles which could be exposed to adverse containment conditions following a High Energy Line Break inside Containment.
(
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: B 8
Explanation (Optional):
In the ECCS analysis, the containment spray temperature is assumed to be equal to the FWST lower temperature of 70°F. The lower temperature limit is based on the following: If the lower temperature limit is violated, the containment spray further reduces the containment pressure which decreases the saturated steam specific volume. This means that each pound of steam generated during core reflood tends to occupy a larger volume which decreases the rate at which steam can be vented out the break and increase the peak clad temperature.
A. Incorrect: See explanation above. Plausible because the solubility of boron is a concern associated with the FWST minimum temperature, this is not discussed associated with the containment spray system.
B. Correct: As discussed above which is also as stated in the Limits and Precautions section of the Containment Spray lesson plan.
C. Incorrect: See explanation above. Plausible because a vacuum being established in containment is a concern with FWST temperature but this is a concern during normal operation. In a post accident environment, CPCS will secure the NS system preventing excessive containment
( negative pressure.
D. Incorrect: See explanation above. Plausible because in a post HELBIC atmosphere, the temperature would be significantly elevated. It is reasonable that the introduction of the relatively cold water through the spray nozzles could result in a thermal shock concern to the nozzles themselves.
Technical Lesson Plan ECC-NS (Attach if not previously Reference(s)
Reference( s) _(>-R_e_v_2_9.!-)_P"...g_3_1_ _ _ _ provided)
--'('--R_ev_29-<)_P--"9<-3_1____
(Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-ECC-NS Obj. 11 (As available)
Page 2 ofS of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank#
Modified Bank (Note changes or attach
- _ _ _ _ parent)
New x Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.10 Content:
55.43 Comments:
Containment Spray (NS):
Generic: Ability and explain and apply all system limits and precautions.
(
KA is matched because this question tests the candidates knowledge of a significant temperature limit associated with the containment spray system. This limit is clearly associated with the system as discussed in the lesson plan as well as supported by one of the stated objectives. The limits and precautions associated with this system do not lend themselves to an application type question so we were only able to address the "ability to explain" element of this generic KIA statement.
(
Page 3 ofof55 Rev Final
ES-401 Sample Written Examination ES-40 1-5 Form ES-401-S Question Worksheet Examination Outline Cross- Level RO SRO reference: XX X X
Tier#
Tier # 2 DRAFT Group # 1 KJA#
KIA # 062G2.2.39 Importance Rating 3.9 4.5 4.S AC Electrical Distribution Knowledge of less than one hour technical specification action statements for systems.
Proposed Question: Common 24 1 Pt Given the following:
- Unit 1 is operating at 100% RTP.
- The 1A EDG has just been declared inoperable due to an oil leak on the Woodward governor.
Which ONE (1) of the following describes ALL checks which must be
(, performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to ensure compliance with TS 3.8.1 (AC Sources - Operating)?
A. Flowpaths through which 1ETA AND 1ETB are being supplied by offsite power.
B. Flowpath through which 1ETA is being supplied by offsite power AND determine that 1ETA is being supplied independently from 1 ETB.
C. Flowpath through which 1 ETB is being supplied by offsite power AND determine that 1ETB is being supplied independently from 1 ETA.
D. Flowpaths through which 1ETA AND 1ETB are being supplied by offsite power AND determine that 1ETA and 1 ETB are being supplied independently.
( Page 1 of20 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: 0 Explanation (Optional):
Tech Spec SR 3.8.1.1. requires verification of the flowpath through which ETA and ETB are being supplied by offsite power AND that the busses are being supplied independently.
A. Incorrect: See explanation above. Plausible if candidate believes that only the flowpath to the affected Safety Bus needs to be checked.
B. Incorrect: See explanation above. Plausible if candidate believes that, from the standpoint of redundancy, only the flowpath to the unaffected Safety Bus needs to be checked.
C. Incorrect: See explanation above. Plausible if the candidate does not understand that not only does the flowpath to each Safety Bus need to be checked but train separation also needs to be ensured.
D. Correct.
( Technical Reference(s) TS 3.8.1. AC Sources - (Attach if not previously Operating
_O---'--pe_r_a_ti_n""-g_ _ _ _ _ _ _
--~--~--------------
provided)
PT/1/A/43501025, PT/1/A/4350/025, Essential (Including version or revision Auxiliary Power System #)
Power Source Verification, rev. 19 page 5 Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-EL-EP, Obj. 39 (As available)
~--~-------
~-~----
Question Source: Bank#
Modified Bank # (Note changes or attach
_ _ _ _ _ parent)
New -
X -----
Question History: Last NRC Exam
(
Page 2 of20 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
((
Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content: 41.10 55.43 Comments:
AC Electrical Distribution Knowledge of less than one hour technical specification action statements for systems.
KA is matched because the candidate must understand the requirements for the surveillance which must be performed within one hour when an Emergency sUNeiliance Diesel Generator is lost.
(
(
Page 3 of20 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Examination Outline Cross- Level RO SRO reference: X X Tier#
Tier # 1 DRAFT Group # 2 KfA# 051AG2.4.11 Importance Rating 4.0 Loss of Condenser Vacuum:
(Generic): Knowledge of abnormal condition procedures Proposed Question: Common 25 1 Pt Given the following conditions on Unit 1:
- Reactor power is 40%
- 1CM-843 (1A Main Condenser Vacuum Breaker) has failed in the intermediate position. Maintenance is attempting to close this valve.
- EXH HOOD TEMP HI alarm is lit
- Condenser vacuum is 26 inches Hg and DEGRADING slowly
( * (1ZJP5000) CSAE steam pressure is reading 100 PSIG Which ONE (1) of the following actions is directed by AP-23 (Loss of Condenser Vacuum) and will be the MOST effective in mitigating this event?
A. Reduce turbine load.
B. Start additional RC pumps.
C. Dispatch operator to restore CSAE steam pressure.
D. Trip the turbine AND open the Exhaust Hood Spray valves.
(
Page 1 of6 of 6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Proposed Answer: C Explanation (Optional):
The stem sets up a scenario where a failure of one of the main condenser vacuum breaker valves has failed intermediate, The effect of this is excessive air in leakage and a resulting degradation of main condenser vacuum. AP/23 (Loss of Condenser Vacuum) would be implemented to provide mitigating strategies in the situation.
A. Incorrect: See explanation above. Plausible because this action is directed in Step 5 of AP-23 but would ineffective for the scenario described. This is explained by the note prior to this step.
B. Incorrect: Same as above.
C. Correct: Minimum pressure for proper CSAE operation is 140 PSIG and if below this Step 8 of AP/23 directs the operator to dispatch an operator to take actions to restore this pressure to 145 PSIG.
D. Incorrect: See explanation above. Alignment of Exhaust Hood spray is correct and directed by AP-23 but a Turbine trip is not required.
Plausibility for this actions is that a trip of the turbine is directed for a Hi Hi alarm but not for a Hi as stated in the stem
(
Technical AP-23 Background Doc. (Attach if not previously Reference(s) ---,(,-R_e_v_3L-)
'('----R_e_v_3L-)_Pg""---5
_P9"'-----5_ _ _ _ _ provided)
AP/1/A/5500/23 (Rev 7) (Including version or Pages 3 & &5 revision #)
--~--~-------------
--~-----------------
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-AP-23 Obj.2
~-----
~-----
(As available)
Question Source: Bank#
Modified Bank (Note changes or attach
- _ _ _ _ parent)
New xx Question History: Last NRC Exam
(
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.10 Content:
55.43 Comments:
Loss of Condenser Vacuum:
(Generic): Knowledge of abnormal condition procedures KA is matched because the plant condition given is a loss of condenser vacuum and the question requires the candidate to evaluate the plant conditions and choose the correct actions which would be required by the appropriate abnormal procedure AP-23.
The Analysis Cog level is justified because the question requires the candidate to evaluate the loss of condenser vacuum is attributed air in leakage not loss of cooling and apply that to a particular strategy in the AP. This requires the understanding of the basis for the procedure actions.
(
(
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Examination Outline Cross- Gross- Level RO SRO reference: X X X Tier # 2 DRAFT Group # 2 KJA# 086K4.02 Importance Rating 3.0 3.4 Fire Protection Knowledge of (Fire Protection system) design feature(s) and or interlock(s) which provide for the following:
Maintenance of fire header pressure.
Proposed Question: Common 26 Gommon 1 Pt In the event of a fire which activates the fire protection system, which ONE (1) of the following sequence of events is the normal starting sequence for the fire pumps?
A. The "A" Jockey Pump starts at 43" level in the pressurizer tank The "B" "8" Jockey Pump starts at 41" level in the pressurizer tank The "A" Fire Pump starts at 83 psig system pressure The "8" "B" Fire Pump starts at 78 psig system pressure The "c" "G" Fire Pump starts at 73 psig system pressure
(
- 8. The "A" Jockey Pump starts at 51" level in the pressurizer tank B.
The "8" "B" Jockey Pump starts at 45" level in the pressurizer tank The "A" Fire Pump starts at 81 psig system pressure The "8" "B" Fire Pump starts at 76 psig system pressure The "c" "G" Fire Pump starts at 71 psig system pressure C.
G. The "A" Jockey Pump starts at 43" level in the pressurizer tank The "8" "B" Jockey Pump starts at 41" level in the pressurizer tank The "A" Fire Pump starts at 81 psig system pressure The "8" "B" Fire Pump starts at 76 psig system pressure The "c" "G" Fire Pump starts at 71 psig system pressure D. The "A" Jockey Pump starts at 51" level in the pressurizer tank The "8" "B" Jockey Pump starts at 45" level in the pressurizer tank The "A" Fire Pump starts at 83 psig system pressure The "8""B" Fire Pump starts at 78 psig system pressure The "c""G" Fire Pump starts at 73 psig system pressure
(
Page 1 of of55 Rev Final
ES-401 Sample Written Examination Form ES-401-S ES-401-5 Question Worksheet
( Proposed Answer: A Explanation (Optional):
Both Jockey Pumps are normally aligned for AUTO start. If the pressurizer tank level decreases to 43", the lead jockey pump will start. The lead jockey pumps alternate with each start of the pumps. If the pressurizer tank level decreases to 41 ", the standby jockey pump will start.
The "A" Fire Pump starts when system pressure decreases to 83 psig, the "B" Fire Pump when pressure decreases to 78 psig, and the "c" "C" Fire Pump when pressure decreases to 73 psig.
A. Correct.
B. Incorrect: See explanation above. Plausible because the starting pressures for the Fire Pumps are close to the actual start pressures. The Jockey Pump starts are plausible because the normal level in the Pressurizer Tank is 45-51 4S-S1". ".
C. Incorrect: See explanation above. Plausible because the starting levels for the Jockey Pumps are correct and the Fire Pump starts are close to the actual starting pressures.
( D. Incorrect: See explanation above. Plausible because the starting setpoints for all three Fire Pumps are correct. The Jockey Pump starts are plausible because the normal level in the Pressurizer Tank is 45-51 4S-S1 ".
Technical OP-MC-SS-RFY, rev. 26, (Attach if not previously Reference(s)
Reference( s) -'p'-a-"g<-e_2_3_a_n_d_2_S
-'p_a--"g'-e_2_3_a_n_d_2_5_ _ _ _ provided)
(Including version or
_ __ __ __ ___ _________ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-SS-RFY, Obj. S 5 (As available)
OP-MC-SS-RFY, Obj. 4
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
/
( # SSRFYN07 Question Source: Bank Bank#
Modified Bank (Note changes or attach
- _ _ _ _ _ parent)
New Question History: Last NRC Exam -------------------------------
Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Fire Protection Knowledge of (Fire Protection system) design feature(s) and or interlock(s) which provide for the following:
Maintenance of fire header pressure.
( KA is matched because the candidate must be familiar with the setpoints for starting the Fire Water Jockey pumps and the Fire Water pumps to maintain system pressure.
\
Page 3 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Examination Outline Cross- Level RO SRO reference: X X Tier #
Tier# 2 DRAFT Group # 1 KIA # 063K2.01 Importance Rating 2.9 3.1 DC Electrical Distribution Knowledge of the electrical power supplies to the following:
Major DC loads Proposed Question: Common 27 1 Pt Given the following conditions:
- Unit 1 has experienced a Loss of Offsite Power (LOOP).
The Unit 1 Turbine Backup Vapor Extractor is being supplied by electrical bus (1) which is designed to supply all of its rated loads for a period of (2)
Which ONE (1) of the following correctly completes the statement
( above?
A. (1)1DP (1) 1DP (2)1 (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. (1) CXA (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. (1) 1DP (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D. (1) CXA (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Page 1 of8 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Proposed Answer: C Explanation (Optional):
For this question in addition to knowing the power supply for the Backup Vapor Extractor (1 DP), the time rating (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) for the electrical bus was added to raise the difficulty of the question.
A. Incorrect: See explanation above. Plausible because 1DP is the correct bus and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is the time rating for another Auxiliary Power DC bus (CXA).
B. Incorrect: See explanation above. Plausible because CXA is another Auxiliary Power DC bus (1 DP is an Auxiliary Power DC bus) which is designed to supply its rated loads for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
C. Correct.
D. Incorrect: See explanation above. Plausible CXA is another Auxiliary Power DC bus and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is the time rating for 1DP.
Technical OP-MC-EL-EPJ rev. 12, (Attach if not previously Reference( s)
Reference(s) -'p_a ......g<-e_1_1
--'p_a---"9' -e_1_1_____ __ __ _ _ provided)
( OP-MC-EL-EPK, rev. 24, (Including version or
---'pc:....a::..:..>giL:e'--2_5-=----______
---'pL-a---'9"---e_2_5_ _ _ _ _ _ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _ _ _ _ _ _ _ _ _ _ _ (As available)
Question Source: Bank#
Modified Bank (Note changes or attach
_ _ _ parent)
New x Question History: Last NRC Exam
(
Page 2 of8 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
DC Electrical Distribution Knowledge of the electrical power supplies to the following:
Major DC loads KA is matched because the candidate must know the electrical bus which supplies the Turbine Backup (DC) Vapor Extractor.
(
(
Page 3 of8 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X XX Tier# 1 DRAFT Group # 1 KIA # 029EA2.04 Importance Rating 3.2 3.3 ATWS Ability to determine or interpret the following as they apply to a ATWS:
CVCS centrifugal charging pump operating indication Proposed Question: Common 28 1 Pt Given the following conditions on Unit 1 1::
- A major steam line break occurs inside Containment
- Containment pressure increases to 5.5 PSIG
- The reactor fails to trip automatically
- FR-S.1 (Response to Nuclear Power Generation/A TWS) has been Generation/ATWS) implemented
( To prevent runout of the NV pumps, flow rates must be kept less than 1 GPM by manually closing the NV pump recirculation valves when NC system pressure is less than 2 PSIG.
Which ONE (1) of the following correctly completes the statement above?
A. (1) 325 (2) 1500 B. (1) 325 (2) 2000 C. (1) 560 (2) 1500 D. (1) 560 (2) 2000
(
Page 1 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
The NV pump runout flow limit is 560 GPM. The Foldout criteria of FR-S.1 directs the NV pump recirculation valves to be closed if NC system pressure is less than 1500 PSIG and directs them to be opened if NC system pressure is greater than 2000 PSIG.
A. Incorrect: See explanation above. Plausible because 325 GPM is the minimum flow to the NC system that is maintained assuming one injection line ruptures with the mini-flow recirc valves open. Also. Also 1500 psig is the NC system pressure at which the valves should be closed.
B. Incorrect: See explanation above. Plausible because 325 GPM is the minimum flow to the NC system that is maintained assuming one injection line ruptures with the mini-flow recirc valves open. Also 2000 psig is the NC system pressure at which the recirc valves should be opened.
C. Correct D. Incorrect: See explanation above. Plausible because 560 GPM is the correct runout flow for two NV pumps. Also 2000 psig is the NC system pressure at which the recirc valves should be opened.
(
Technical Reference(s) Lesson Plan OP-MC-PS-NV (Attach if not previously (Chemical and Volume provided)
Control), rev. 56, page 33 (Including version or revision
- - - - - - - - - - #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P_-M_C_-_P_S_-N_V--','-,'O_b....Lj_.
_O_P_-M_C_-_P_S_-N_V----' --O_b-Lj_.5_ _ _ (As available)
Question Source: Bank#
Modified Bank # (Note changes or attach
_ _ _ _ _ parent)
New --
X- - --
Question History: Last NRC Exam
(
Page 2 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge X
( Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.5 Content:
55.43 Comments:
ATWS Ability to determine or interpret the following as they apply to a ATWS:
CVCS centrifugal charging pump operating indication KA is matched because the candidate must be able to monitor plant conditions and determine when actions must be taken to protect the NV pumps from runout.
(
(
Page 3 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X Tier # 1 DRAFT Group # 2 KIA #
KJA# 028AA1.07 Importance Rating 3.3 3.3 Pressurizer Level Malfunction Ability to operate and/or monitor the following as they apply to (Pressurizer Level Malfunction):
Charging pumps maintenance of PZR level (including manual backup)
Proposed Question: Common 29 1 Pt Unit 2 is currently operating at 60% power with a load increase in progress. Given the following events and conditions:
- Pressurizer level control is in the "1-2" position (normal control)
- Pressurizer level is at program level and in "automatic"
- Pressurizer level Channel 1 fails at its current level If the channel failure remains undiscovered, which ONE (1) of the following describes the system response as plant load is increased?
(
A. Charging flow decreases Letdown isolates Pressurizer heaters turn off B. Charging flow increases Letdown isolates Pressurizer backup heaters energize C. Charging flow increases Pzr Low Level Control annunciator alarms Pressurizer level increases to the trip setpoint D. Charging flow decreases Pzr Low Level Control annunciator alarms Pressurizer level decreases until the pressurizer is empty
(,
Page 1 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
As unit load is increased, Pressurizer program level will also increase. However, with Pressurizer Level Channel 1 failed at its current level, the master level controller will receive a level deviation signal from the summing unit telling it that Pressurizer level is less than program level. The master level controller will compare 2NV238 position to actual charging flow and will open 2NV238 in an attempt to increase Pressurizer level to program level. However, since Channel 1 is failed "as is" the level deviation signal will remain.
With 2NV238 opening, charging flow and ACTUAL Pressurizer level will increase, the Lo Level control annunciator alarms, and level increases to the high level trip setpoint.
A. Incorrect: See explanation above. Plausible if the candidate misinterprets the direction of the level deviation.
B. Incorrect: See explanation above. Plausible if candidate does not correctly apply the affect of the channel failure along with the change in plant conditions and the function of the other level channel.
C. Correct.
( D. Incorrect: See explanation above. Plausible if the candidate misinterprets the direction of the level deviation.
Technical Lesson Plan OP-MC-PS- (Attach if not previously Reference(
Reference(s) s) ILE, rev. 17, page 15 and provided) 37 (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-PS-ILE,
_O-' Obj. ._12
---P_-_M_C_-P_S-'----_IL_E....!....,-,-O--,-,bJL-'
~~-----
12_ _ (As available)
Page 2 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Question Source: Bank#
Modified Bank PSILEN02 (Note changes or attach
- _____ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Pressurizer Level Malfunction
( Ability to operate and/or monitor the following as they apply to (Pressurizer Level Malfunction):
Charging pumps maintenance of PZR level (including manual backup)
KA is matched because in order to effectively monitor the operation of the system, the candidate must understand how charging flow and actual pressurizer level respond when a pressurizer level instrument fails.
This is a higher cognitive level question because the candidate must understand the operation of the Pressurizer Level Control system and analyze given conditions to determine how the system will respond to a malfunction of the level control system.
(
Page 3 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X Tier # 1 DRAFT Group # 2 KIA # WE03EA1.3 Importance 3.7 4.1 Rating LOCA Cooldown / Depress.
Ability to operate and/or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):
Desired operating results during abnormal and emergency situations.
Proposed Question: Common 30 1 Pt Given the following:
- A LOCA has occurred on Unit 1
- ES-1.2 (Post LOCA Cooldown and Depressurization) has been implemented Which ONE (1) of the following actions are part of the mitigating strategy in ES-1.2?
(
A. (1) Establish a 100°F/hr 1OO°F/hr cooldown rate (2) Sequentially stop all but one NV pump B. (1) Cooldown and depressurize at maximum rate to minimize break flow (2) Sequentially stop all but one NV pump C. (1) Establish a 100°F/hr 1OO°F/hr cooldown rate (2) Secure all NC pumps to minimize break flow D. (1) Cooldown and depressurize at maximum rate to minimize break flow (2) Secure all NC pumps to minimize break flow
(
Page 1 of of55 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):
The following actions are part of the mitigating strategy in ES-1.2:
a establishing a 1OO°F/hr cooldown rate a restoring PRZR level using one PORV a restarting an RCP a sequentially stopping all SI pumps (except the last charging/SI pump) a depressurizing the RCS with normal spray to restore PRZR level a aligning the last charging/SI pump to normal charging a adjusting normal charging flow to control PRZR level a depressurizing the RCS to minimize break flow A. Correct.
B. Incorrect: See mitigating strategy above. Plausible because depressurizing the NC system to minimize break flow is part of the mitigating strategy in ES-1.2. While cooling down and depressurizing at the MAXIMUM rate is part of the mitigating strategy in E-3, it is not part of the mitigating strategy in ES-1.2. Also, sequentially stopping all but one NV pump is part of the mitigating strategy in ES-1.2.
( C. Incorrect: See mitigating strategy above. Plausible because establishing a 1OO°F/hr cooldown rate is part of the mitigating strategy in ES-1.2. Also, securing NC pumps to minimize break flow is part of the mitigating strategy in E-1 (if subcooling is lost and at least one NI or on NV pump is running). However, securing NC pumps is not part of the mitigating strategy in ES-1.2.
D. Incorrect: See mitigating strategy above. Plausible because depressurizing the NC system to minimize break flow is part of the mitigating strategy in ES-1.2. While cooling down and depressurizing at the MAXIMUM rate is part of the mitigating strategy in E-3, it is not part of the mitigating strategy in ES-1.2. Also, securing NC pumps to minimize break flow is part of the mitigating strategy in E-1 (if subcooling is lost and at least one NI or on NV pump is running). However, securing NC pumps is not part of the mitigating strategy in ES-1.2.
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Technical Lesson Plan OP-MC-EP- (Attach if not previously Reference(s) E 1, Loss of Reactor or E1, provided)
Secondary Coolant, rev.
18 page 102 Background Document for (Including version or ES-1 .2 (Post LOCA revision #)
Cooldown and Depressurization), rev. 2, page 7 Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-EP-E1, Obj. 3_ _ (As available)
_O_P-_M_C_-_E_P_-E_1---,-,_O_b..L.j._3
~--~-----
Question Source: Bank#
Modified Bank (Note changes or attach
- __ - parent)
New x
( Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X X
Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
LOCA Cooldown / Depress.
Ability to operate and/or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):
Desired operating results during abnormal and emergency situations.
KA is matched because the candidate must understand the overall mitigating strategy of ES-1.2 (Post LOCA Cooldown and Depressurization) to effectively monitor the status of the plant and take appropriate actions to meet the mitigating strategy.
(
Page 3 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier# 2 DRAFT Group # 1 KIA # 022K1.04 Importance Rating 2.9 2.9 Containment Cooling Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:
Chilled water Proposed Question: Common 31 1 Pt Given the following:
- Unit 2 is operating at 100% RTP
- A Loss of Offsite Power occurs on both Units 1 and 2 Which ONE (1) of the following provides the assured source of cooling water to maintain containment temperatures within Tech Spec limits?
A. RV pumps B. '2A' RN pump only C. '2B' RN pump only D. Both '2A' AND '2B' RN pump
(
Page 1 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Proposed Answer: B Explanation (Optional):
On a Blackout, RV system pumps lose power so they will be unavailable to supply cooling to the Upper and Lower Containment AHUs. However, RN-42A remains open which allows 'A' RN pump to supply the Containment AHUs.
A. Incorrect: See explanation above. Plausible because RV pump C could be considered the supply since it will try to start on loss of cooling water pressure.
B. Correct.
C. Incorrect: See explanation above. Plausible if the candidate believes that the supply comes from the B RN train.
D. Incorrect:: See explanation above. Plausible if the candidate does not realize one train of valves close on the blackout.
Technical Lesson Plan OP-MC- (Attach if not previously Reference( s)
Reference(s) CNT -RV, rev 19, page 27 CNT-RV, provided)
( (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-CNT-RV, Obj. 13 (As available)
Question Source: Bank# CNTRVN02 Modified Bank (Note changes or attach parent)
New Question History: Last NRC Exam
(
Page 2 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(' Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.2 Content: to 41.9 55.43 Comments:
Containment Cooling Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:
Chilled water KA is matched because candidate must have knowledge of how the RV System (Containment Ventilation Cooling Water System) is supplied during a loss-of-offsite power. This requires both knowledge of the physical connections and the effects of a station Blackout on both the RN and RV systems, both of which are McGuire Nuclear Station's equivalent of a containment chilled water system.
This is a higher cognitive level question because the candidate must analyze the
( given plant conditions, determine that cooling water is unavailable from the RV system and that cooling water is still available from the RN system via RN-42A but only from the 'A' Train of RN due to the train separation caused by the Blackout.
Page 3 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Examination Outline Cross- Level RO SRO reference: X X X Tier # 2 DRAFT Group # 2 KIA # 027K2.01 Importance Rating - 3.1
_3_._1
__ 3.4 Containment Iodine Removal Knowledge of the electrical power supplies to the following:
Fans Proposed Question: Common 32 1 Pt Unit 1 was operating at 100% when the following sequence of events occurred:
- A Loss-of-Offsite Power resulted in a Reactor Trip
- When the 1A DIG attempted to load 1ETA, a fault on the bus resulted in an 87G (Generator Differential) relay actuation
- Containment pressure is 2.3 PSIG and increasing
(
Which ONE (1) of the following describes the status of the VE (Annulus Ventilation) fans if a Containment Phase 'B' '8' signal is received?
A. Only 1 18 B VE fan will start coincident with the Phase 'B' '8' signal.
- 8. 1A and 1 B. 18B VE fans will start coincident with the Phase 'B' '8' signal.
C. Only 1 18B VE fan will start 10 minutes after receipt of the Phase 'B' '8' signal.
D. 1A and 1 18B VE fans will start 10 minutes after receipt of the Phase
'8' signal.
'B'signal.
{
\
Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Proposed Answer: A Explanation (Optional):
Power is unavailable to 1A VE fan due to the lockout of bus 1ETA. However, power is available to 18 1B VE fan. Containment pressure is current below 3.0 PSIG. The 181B VE fan would start if Containment pressure increase to the Phase 8 setpoint (3.0 PSIG).
B A. Correct.
- 8. Incorrect: See explanation above. Plausible if the candidate does not B.
understand that the 87G relay will lockout the 1EDG and therefore no power will be available to 1ETA and consequently no power is available to 1EMXC which supplies the 1A VE fan.
C. Incorrect: See explanation above. Plausible because only 18 1B VE fan will start. However, the candidate must understand that the VE fans start immediately upon receipt of a Phase '8' 'B' signal where most other Phase 'B8' equipment actuations have a 10 minute time delay.
D. Incorrect: See explanation above. Plausible if the candidate does not understand that the 87G relay will lockout the 1EDG and therefore no power will be available to 1ETA and consequently no power is available to 1EMXC which supplies the 1A VE fan. Also the candidate must understand that the VE fans start immediately upon receipt of a Phase '8' 'B' signal where most other Phase '8'
'B' equipment actuations have a 10 minute time delay.
Technical Lesson Plan OP-MC- (Attach if not previously Reference( s)
Reference(s) CNT-VE, rev. 25 page 13 provided)
Attached electrical (Including version or
_d-'-.i-'-.ag>Lr_a_m_f_ro_m_S,-P_D_S
_d_i-.-:ag!Lr_a_m_f_ro_m_S_P_D_S _ _ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: None
_N_o_ne _ _ _ _ _ _ _ _ _ (As available)
(
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank#
Modified Bank (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
Content 55.43 Comments:
Containment Iodine Removal Knowledge of the electrical power supplies to the following:
Fans
( KA is matched because the VE system performs the function of iodine removal.
In the event of an accident, containment is vented to the annulus area and the annulus area is vented to atmosphere using the VE fans through charcoal filters for iodine removal. The VE fans are powered from essential power via ETA and ETB. For these types of loads, it is difficult to create a discriminating question based on just identifying a particular bus. By providing just a relay actuation associated with the "A" train bus, the candidate must evaluate the effect on whether or not power would still be available to this component. Many of the relays associated with this bus would not affect the loading in a BIO mode but the one given would trip the associated DIG. This constitutes knowledge of the electrical power supply over and above just picking out a particular bus.
This is a higher cognitive level question because the candidate must comprehend that due to the relay actuation power is unavailable to 1ETA and consequently to 1A VE fan. The candidate must also comprehend that the 1B VE fan has power available and will start immediately if a Phase B signal is received.
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Examination Outline Cross- Level RO SRO reference: X X
Tier # 1 DRAFT Group # 1 KIA # 077AK2.07 Importance Rating 3.6 Generator Voltage and Electrical Grid Disturbances Knowledge of the interrelations between (Generator Voltage and Electric Grid Disturbances) and the following:
Turbine! Generator Control Proposed Question: Common 33 1 Pt Unit 1 & 2 are operating at 100% RTP:
- The TCC has notified the Control Room of impending grid frequency disturbances
- Both Unit 1 & 2 have been operating with frequency less than 59.5 Hz for greater than 20 Minutes Why must the operator ensure Turbine First Stage Impulse pressure is less than 340 PSIG prior to opening the Switchyard
( PCB's?
A. Opening the Switchyard PCB's prior to Turbine First Stage Impulse pressure decreasing below 340 PSIG will result in a Turbine Trip.
B. Turbine First Stage Impulse pressure <340 PSIG ensures that a Turbine Trip will occur once separated from the Grid but that a Reactor Trip will not occur.
C. Opening the Switch yard PCB's above 340 PSIG Turbine First Stage Impulse pressure will initiate a Complete Loss of Load transient and the Main Generator load will reduce to In-House loads.
D. Turbine First Stage Impulse pressure <340 PSIG ensures that the AMSAC circuit will not trip the Main Turbine during the resulting feedwater transient as the Turbine runs back to In-House loads.
Page 1 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):
Per AP/05 Enc 2 (Abnormal Generator Voltage or Grid Frequency) Step 4 directs the Operators to monitor Accumulated time that frequency is less that that indicted in the table provided in this step. Per this table, if Freq is < 59.5 Hz for 20 min, the procedure direct actions to separate the unit from the Grid. The procedure either verifies that Turbine Impulse pressure is < 340 PSIG or directs a load reduction to reduce load and then open the Switchyard PCB's which will result in the Main Turbine running back to In House Loads. If the PCB's are opened above this turbine load, a Turbine Trip will occur.
A. Correct.
B. Incorrect: See explanation above. Plausible because 340# represents approx. 47.2 % Reactor power which is below P-8 and therefore it would be possible to have a Main Turbine Trip and not have a Reactor Trip.
C. Incorrect: See explanation above. If the PCB's are opened above 340#, a turbine trip will result. It is plausible that candidate could believe that a complete loss of load may be desirable in order to keep the unit on line. The original design at MNS was to be able to handle a complete loss of load from 100% but this was changed and a turbine trip added if impulse is greater than 340#.
( D. Incorrect: See explanation above. Plausible because this setpoint is near the AMSAC reset setpoint of 290 psig and this would result in a severe feedwater transient which could conceivably challenge AMSAC. If AMSAC were to actuate, a turbine trip would result.
Technical Lesson Plan OP-MC-GEN- (Attach if not previously Reference(s) _E_H_C~R....:....ev----,--35~P--",gc......:8c....::.3
_E_H_C_R_e_v_3_5_P",-g_8_3_ _ _ _ provided)
AP-5, Generator Voltage (Including version or revision and Electric Grid #)
Disturbances, rev 6, page 17 Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-GEN-EHC Obj # 13 (As available)
. Page 2 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank# MNS AP05027 Modified Bank # (Note changes or attach
_____ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Generator Voltage and Electrical Grid Disturbances Knowledge of the interrelations between (Generator Voltage and Electric Grid Disturbances) and the following:
Turbine! Generator Control
(
KA is matched because a situation where the Grid Frequency has deteriorated to the point of having the separate the station from the grid. This requires the Operators to adjust turbine load to less that 340# Impulse pressure to prevent a turbine trip and ensures the LOA (Load Drop Anticipatory) will actuate to prevent a trip on overspeed due to transferring from load control to speed control. This question is testing the candidate's knowledge of this aspect of the turbine generator control system which is unique to a Grid disturbance scenario. This meets the "interrelation" element of this KIA because this consideration during T/G control is both unique for this type of event and uniquely impacts when we would open the switchyard breakers to induce a runback to in house loads.
(
Page 3 of6 Rev
ES-401 Sample Written Examination Form ES-401-S ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X Tier # 1 DRAFT Group # 1 KIA # 01SAA2.11 015AA2.11 Importance Rating 3.4_ _
_3-,-._4 3.8 RCP Malfunctions Ability to determine and interpret the following as they apply to (RCP Malfunctions):
Proposed Question: Common 34 1 Pt Given the following conditions:
- Unit 1 is responding to a LOCA
- All sources of feedwater have been lost, S/G NR levels are 17%
and decreasing
- NC pumps are secured
- FR-C.1 (Response to Inadequate Core Cooling) has been implemented
- NI and NV pumps are unavailable
(
- Peak Containment pressure reached 2.S 2.5 PSIG
- S/G depressurization has failed to restore adequate core cooling
- Core Exit Thermocouples are currently indicating 1210°F 121 OaF
- NC pump support requirements can NOT be met What is the major action(s) required by FR-C.1 under these conditions?
A. Do NOT restart NC pumps, open all PZR PORVs and head vents to depressurize the NC system.
B. Restart all NC pumps and restore secondary heat sink in FR-H.1 before proceeding in FR-C.1.
C. Restart NC pumps one at a time until CETs are less than 1200°F to force two phase flow through the core for core cooling.
D. Do NOT restart NC pumps, initiate feed and bleed of the NC system to restore core cooling. Feed and bleed is time critical to prevent a core melt.
(
Page 1 of8 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Proposed Answer: C Explanation (Optional):
The question stem establishes a scenario where the crew has implemented FR C-1 and has proceeded through the procedure to the point where a RCP start is required. The stem also provides the information that first two major strategies of reestablishing SI Sl flow and SIG S/G depressurization have not been successful exemplified by CET current indicating >1200 deg. In this scenario, heat sink is verified and the NCP's are started one at a time with or without normal required support for pump operations.
A. Incorrect: See explanation above. Plausible if a pump was not available to be started or there was no heat sink available.
B. Incorrect: See explanation above. NC pumps are started one at a time and not all at once. Plausibility for restoring secondary heat sink is the information in the stem that "All sources of feedwater have been lost" and current SIG S/G are low but still high enough to provide a heat sink.
C. Correct: As explained above, this situation would require the actions stated per Step 22 of FR C-1.
D. Incorrect: See explanation above. As explained above, restarting the NCP's is correct and the plausibility for the alternate strategy suggested would be correct in FR H-1 if SIG S/G WR levels were to degrade to <24% WR level and a complete
( loss of FW has occurred in this scenario.
Technical Lesson Plan OP-MC-EP- (Attach if not previously Reference(s) FRC, Core Cooling provided)
Functional Restoration Procedures Rev 10 Pg 43 FR-C-1 Rev 6 Pg 18-20 (Including version or revision
-- -- -- -- - -- ------- #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _E_P_-_F_RC_O_bL-j#_4_
_E_P_-_F_R_C_O_b---Lj_#_4 _______ _ (As available)
Question Source: Bank#
Modified Bank # EPFRC019 (Note changes or attach
_ _ _ _ _ parent)
New Question History: Last NRC Exam
(
Page 2 of8 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.10 Content:
55.43 Comments:
RCP Malfunctions Ability to determine and interpret the following as they apply to (RCP Malfunctions):
KA is matched because NCP normal support requirements cannot be met and under normal circumstances, this would be a malfunction that would require the affected pumps to be secured. Because this a CSF challenge, FR C-1 directs that the pumps be run one at a time even if it results in pump damage. The question also requires the candidate to recognize that the situation described in the stem would be a time to "jog RCP's during ICC".
This Question meets the criteria of analysis because the candidate must evaluate
( a given set of plant conditions and then apply this information to choose the required strategy in FR-C-1 and know that a pump run is required even though pump damage may result.
(
Page 3 of8 Rev
ES-401 Sample Written Examination Form ES-401-S ES-401-5 Question Worksheet
/ Examination Outline Cross- Level RO SRO
\
reference: X X X X
Tier # 1 DRAFT Group # 1 KIA #
KJA# 00SK6.03 005K6.03 Importance Rating _2-=..:.--,-S 2.5_ _ 2.6 Residual Heat Removal Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):
RHR heat exchanger Proposed Question: Common 35 3S 1 Pt Unit 1 is shutdown with the following conditions:
- 1A and 1B ND NO trains are in service seNice providing shutdown cooling lAW SO-9 (ND (NO System Parallel Heat Exchanger Operation)
- The flow rate on each ND NO train is currently 1S00 1500 GPM
- NC system temperature is being maintained at 170°F
- The air line for 1 ND-34 (1A & 1 B ND NO Hx Byp Isol) breaks off
( Which ONE (1) of the following describes the indications that will be observed obseNed by the Operators in the Main Control Room over the next 1S 15 minutes?
1A NDNO Train Total 1B ND NO HX Inlet Flowrate Tem~erature Teml2erature A. Increase Increase B. Increase Decrease C. Decrease Increase D. Decrease Decrease Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 ES-40 1-5 Question Worksheet
( Proposed Answer: A Explanation (Optional):
The instrument air line breaking off of 1NO-34 causes the valve to fail open. This bypasses a portion of the flow that would normally pass through the NO Heat Exchangers. The reduction in total resistance to flow causes the total flow rate on each NO Train to increase. However, since there is less flow through the heat exchangers, NC System temperature will increase.
A. Correct.
B. Incorrect: See explanation above. Plausible because the total system flow rate does increase. The candidate may incorrectly conclude that the increase in system flow rate results in increased cooling of the NC System and a reduction in NC system temperature.
C. Incorrect: See explanation above. Plausible if the candidate concludes that the flow bypassing the heat exchangers no longer contributes to the total flow rate for each train resulting in a reduction in flow rate. The candidate would then conclude that the reduction in flow rate would reduce the flow through the heat exchangers causing NC System temperature to increase.
O. Incorrect: See explanation above. Plausible if the candidate concludes
( that the air line break causes 1NO-34 to fail closed. This would reduce the total system flow rate on each train. However, it would also force more flow through the NO Heat Exchangers causing NC system temperature to decrease.
Technical Lesson Plan OP-MC-PS- (Attach if not previously Reference(
Reference(s)s) NO, Residual Heat provided)
Removal System, rev 37, pages 27 and 69 (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-PS-NO, Obj. 8
~~------
(As available)
~~-----
(
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Question Source: Bank#
Bank #
Modified Bank EB1113*
EB 1113* (Note changes or attach
- _ _ _ _ parent)
New
- From Comanche Peak exam bank.
Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Residual Heat Removal Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):
( RHR heat exchanger KA is matched because the candidate must understand how flow is controlled through the ND NO System Heat Exchangers during shutdown cooling mode and how failures associated with the flow/temperature control valves will effect overall system parameters.
This is a higher cognitive level question because the candidate must analyze the effect of the 1NO-34ND-34 air line breaking off and once the candidate determines that the valve fails open determine (based on the system flowpath) how the valve failing open will affect the flows and temperatures in the system.
(
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Examination Outline Cross- Level RO SRO reference: X X X
Tier # 1 DRAFT Group # 1 KIA #
KJA# 055EA1.06 Importance Rating _4_._1 4.1 _ _ 4.5 Station Blackout Ability to operate and monitor the following as they apply to a Station Blackout.
Restoration of power with one ED/G Proposed Question: Common 36 1 Pt Unit 2 is responding to a large LOCA when a loss of Off Site Power occurs. Given the following events and conditions:
- A reactor trip and safety injection has occurred and 2B O/G DIG failed to start.
- S SII was reset
- Sequencers were reset Which ONE (1) of the following statements correctly describes the
( restoration process for the Train A NV, NI, NO, and CA pumps?
A. 2A NO and 2A CA pumps automatically restart NV and 2A NI pumps must be restarted by operator action 2A NVand NV and 2A NI pumps automatically restart B. 2A NVand 2A NO and 2A CA pumps must be restarted by operator action C. 2A NV and 2A CA pumps automatically restart 2A NI and 2A NO pumps must be restarted by operator action O. 2A NI and 2A NO pumps automatically restart 2A NV and 2A CA pumps must be restarted by operator action
(
Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Proposed Answer: C Explanation (Optional):
Both the ECCS and blackout sequencers control NV NVand and CA pumps. The ECCS sequencer controls NI and NO pumps only. Therefore, the 'A' Train NVand NV and CA pumps will automatically sequence on but the 'A' Train NI and NO pumps must be manually restarted.
A. Incorrect: See explanation above. Plausible if the candidate misunderstands the SI and SBO functions of the components. NI pumps must be restarted and the CA pumps will automatically restart.
B. Incorrect: See explanation above. Plausible if the candidate misunderstands the SI and SBO functions of the components. NO pumps must be restarted and the NV pumps will automatically restart.
C. Correct.
O. Incorrect: See explanation above. Plausible because starting the NO and NI pumps automatically would be a desired state for a large LOCA.
Technical OP-MC-OG-EQB, rev 16 (Attach if not previously
( Reference(s) ......9<-e_s_1_6-'-,2_7---',_2_9____
---,p_a---",9,---e_s_1_6-,---,
--'p_a 2_7---'-,_2_9_ _ _ _ provided)
(Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-OG-EQB, Obj. 8 (As available)
Question Source: Bank #
Bank# DGEQBN01 Modified Bank (Note changes or attach
_ _ parent)
New Question History: Last NRC Exam Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Station Blackout Ability to operate and monitor the following as they apply to a Station Blackout.
ED/G Restoration of power with one EO/G KA is matched because candidate must know how what happens both automatically and what must be performed manually to restore operating equipment to service with one ED/G operating following a station blackout.
In the scenario provided, a station blackout has occurred, a single remaining EDG is sequencing onto the bus restoring power and the candidate is being asked what indications will be changing (Monitor) and what actions will have to be taken manually. (Operate)
( This is a higher cognitive level question because the candidate must analyze a sequence of events and determine how that sequence of events affects the realignment of the 'A' Train ECCS components. With a different set of initial conditions the automatic operation of the sequencerlDIG would be different therefore an element of analysis is present and the candidate is predicting an outcome.
((
\
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X Tier # 1 DRAFT Group # 2 KIA # 003AK3.10 Importance Rating _3_._2 3.2 _ _ 4.2 Dropped Control Rod:
Knowledge of the reasons for the following responses as they apply to (Dropped Control Rod):
PDIL (Power Dependent Insertion Limits)
RIL and POlL Proposed Question: Common 37 1 Pt Given the following conditions on Unit 1:
- Rod M-4 has dropped due to a blown fuse
- AP-14 (Rod Control Malfunction) has been implemented
- The fuse has been replaced and the dropped rod has been realigned with the rest of the rods in Control Bank D Due to a miscommunication with I&E, the Pulse-to-Analog Converter was not reset to the correct bank step position.
(
The "Control Bank Lo-Lo Limit" annunciator will:
A. alarm SOONER than required because the RIL function of the OAC is calculating CB-D rods to be higher than actual.
B. alarm LATER than required because the RIL function of the OAC is calculating CB-D rods to be higher than actual.
C. alarm SOONER than required because the RIL function of the OAC is calculating CB-D rods to be lower than actual.
D. alarm LATER than required because the RIL function of the OAC is calculating CB-D rods to be lower than actual.
(
Page 1 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: B 8
Explanation (Optional):
Per direction in AP/14, the dropped rod is retrieved by opening the lift coil disconnects on the unaffected rods in the associated bank and then the misaligned rod is pulled out and realigned. During this evolution, the PIA converter continues to "count pulses". The Rod Insertion Limit computer utilizes this pulse count from the PIA converter to determine the "Actual" rod height. If the converter is not reset to reflect the actual bank position after the retrieval of the dropped rod, the RIL computer will see the control banks further out than they actually are. The "Control Bank Lo-Lo Limit" Annunciator alarms based on a comparison of actual rod position (PIA Converter) and Reactor Power (Auctioneered High Delta T) required Rod Insertion Limit rod Position. This error would result in this Annunciator alarms LATER than required.
A. Incorrect: See explanation above. This answer is plausible because in order to correctly answer this question it is required to have an in-depth understanding of both the function of the PIA converter and the function of the RIL computer. It would be understandable to reverse these effects.
B. Correct.
( C. Incorrect: See explanation above. Plausible because in order to correctly answer this question it is required to have an in-depth understanding of both the function of the PIA converter and the function of the RIL computer. It would be understandable to reverse these effects.
D. Incorrect: See explanation above. Plausible if the candidate believes that the RIL computer now has an input indicating that the rods are approximately 200 steps lower that actual. This would be the magnitude of the error present if the effect of not resetting the PIA converter was reversed.
Technical AP-14, Rod Control (Attach if not previously Reference(s) Malfunction Bkgrd Doc provided)
(Rev 6) Pg 15 Lesson Plan OP-MC-IC- (Including version or revision IRE, Rod Control Sytem #)
(Rev 19) Pg 17 & 19 Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P_-M_C_-_A_P_-1_4_0_b-,-j
._4_ _ _ (As available)
_O_P-_M_C_-_A_P_-1_4_0_bL-j._4
(
Page 2 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Question Source: Bank#
Modified Bank # EB670 (Note changes or attach
_____ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.5 Content:
55.43 Comments:
Dropped Control Rod:
Knowledge of the reasons for the following responses as they apply to (Dropped Control Rod):
RIL and PDIL (Power Dependent Insertion Limits)
( KA is matched because the question is testing the understanding the effects of the recovery of a dropped rod on indications associated with Power Dependent Insertion Limit Annunciator which would alert the operator if the Rod Insertion Limits were being exceeded. The candidate must understand the impact of a misaligned P to A converter on this calculated limit. In the scenario described the effect would be severely non- conservative and could impact reactor safety.
This is a higher cognitive level question because the candidate process two separate pieces of information to come to a correct conclusion. The first piece of information is that the PIA Converter was not reset which means that the TOTAL number of steps counted will be higher than normal. Using that piece of information the candidate must comprehend that the rod position input to the RIL Computer will be higher than actual. From that, the candidate should correctly conclude that the RIL alarms will occur at a bank position that is higher than actual (i.e. LATER during a rod insertion).
(
Page 3 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X Tier#
Tier # 2 DRAFT Group # 1 KIA KJA# # 006A3.06 Importance Rating 3.9 4.2 Emergency Core Cooling Ability to monitor the automatic operations of the (SYSTEM) including:
Valve lineups Proposed Question: Common 38 1Pt Given the following sequence of events:
- A Large Break LOCA occurs on Unit 1
- All ECCS systems are injecting from the FWST
- Safety Injection is reset
- FWST level is currently 200 inches An Operator depresses the 'SS-RESET' pushbuttons on the 'CNTRL
( PERMISSIVE FOR RECIRC MODE 1NI-185A 1 / 184B' switches.
Concerning the following valves:
- 1ND-19A 1 ND-19A (A NO Pump Suction from FWST or NC)
- 1ND-4B (B NO Pump Suction from FWST or NC)
Which ONE (1) of the following describes what the Operator observes with regards to the automatic operation of the ECCS valves listed above after the SS-RESET push buttons are depressed?
pushbuttons A. Immediately after depressing the SS-RESET pushbuttons, 1NI-185A1184B, OPEN AND 1ND-19A14B CLOSE.
B. Immediately after depressing the SS-RESET pushbuttons, 1 NI-185A1184B OPEN AND 1 1NI-185A1184B ND-19A14B REMAIN OPEN.
1ND-19A14B C. When 2/3 FWST Lo Level Bistables are received, 1NI-185A1184B OPEN AND 1ND-19A14B CLOSE.
(
Page 1 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D. When 2/3 FWST Lo Level Bistables are received, 1NI-185A1184B REMAIN CLOSED AND 1ND-19A14B REMAIN OPEN.
Proposed Answer: D Explanation (Optional):
NI-184B and NI-185A automatically open on FWST low level (180 inches),
following a safety injection signal, to swap the NO pump suction from the FWST to the containment sump. Each valve has an S-Iatch control circuit which ensures that the valves will not swap to the containment sump unless certain conditions exist. The S latch is activated by the train related safety injection signal and has two train related indication/switches on MC11. When the Ss signal is actuated, the S LATCHED indication will illuminate and remain lit until the SS RESET pushbutton is depressed. The S LATCH seals in the Ss SIGNAL, therefore the automatic swap will be enabled even if the Ss signal is reset. The S-Iatch allows the automatic opening of NI-184B and/or NI-185A on 2 of 3 FWST LO level bistables provided the FWST level instruments are not in test.
A. Incorrect: See explanation above. Plausible if the candidate does not
( understand how the S Latch circuit works and does not remember the setpoint for the FWST low level swap over to the containment sump.
B. Incorrect: See explanation above. Plausible if the candidate does not understand the S Latch circuit or confuses the operation of the SS-RESET pushbutton with the operation of the BYPASS pushbutton. The BYPASS pushbutton allows NI-185A1184B to be opened while ND-19A14B are open.
C. Incorrect: See explanation above. Plausible if the candidate does not understand how the S Latch circuit works. The actions in the distracter would occur as described if the SS-RESET pushbutton had not been depressed.
D. Correct.
Technical OP-MC-PS-ND, rev. 37 (Attach if not previously Reference(s)
Reference( s) -,-p:pages 29 and
- . . .: a-'S!g'-.: . e-=-s-=2-=-9-=-a:
~~-----------------
31
.:. .:n-=-d-=-3-=-1____ provided)
(Including version or revision
- - - - - - - - - #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-PS-ND, Obj. 7 (As available)
~~------
Page 2 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank#
Bank # PSND035 Modified Bank # (Note changes or attach parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Emergency Core Cooling Ability to monitor the automatic operations of the (SYSTEM) including:
Valve lineups KA is matched because the question tests the candidate's ability to recognize
( ECCS system automatic actions which should occur either immediately when an action is taken or long-term when plant conditions change. Additionally, the candidate must be able to recognize automatic actions that should have occurred and do not because changing conditions have affected the normal automatic operation of the ECCS system.
This is a higher cognitive level question because the candidate must process several pieces of information (i.e. (Le. Safety Injection has occurred, SI has been reset, and FWST level is >180 inches) to correctly determine the effect of depressing the SS-RESET pushbuttons with that combination of conditions present.
Page 3 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X Tier # 1 DRAFT Group # 2 KIA # 068AK2.02 Importance Rating 3.7 3.9 Control Room Evacuation:
Knowledge of the interrelations between (Control Room Evacuation) and the following:
Reactor Trip System Proposed Question: Common 39 1 Pt AP-17 (Loss of Control Room) contains a caution which reads:
" The operator at the Reactor Trip Breakers SHALL NOT TRIP the Reactor until directed to do so by the SRO at the ASP."
Which ONE (1) of the following describes the basis for this operational concern, during the response to Loss of Control Room?
A. Ensures control is established at the Auxiliary Shutdown Panel
( before placing the plant in a transient.
B. A "fire" may have caused the Control Room evacuation and a coordinated effort is required for the SRO to isolate controls from the normal power source(s).
C. Emergency Boration must be initiated prior to tripping the Reactor and because the control room indications are no longer available, action has to be verified by the SRO at the ASP.
D. In accordance with 10CFR50, reactivity manipulations must be performed or directed by an NRC Licensed Operator; and since the operator at the Reactor Trip breakers may not be an NRC Licensed Operator this effort must be directed by the SRO at the ASP.
Page 1 of4 of 4 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):
The caution referenced in the stem of this question is contained in Step 5 of AP-17 (Loss of Control Room). The purpose if the step and caution is pre-stage operators at key locations and align ASP controls to ensure effective control of the plant is established immediately on the initiation of the plant transient when the reactor is tripped. There is a discussion in the background document that when this scenario was first tested, an SI resulted due to excessive cooldown which was a direct result of operators not being pre-staged and control established prior to initiating a trip of the reactor.
A. Correct.
S. Incorrect: AP-17 is not used in a Fire scenario (AP-24). Plausible because B.
the candidate may confuse actions directed in AP-24 with those in AP-17 which also deals with a C/R evacuation.
C. Incorrect: Emergency boration is only required if two or more rods are not fully inserted or rod position cannot be determined. Plausible because emergency boration is required by this AP as described above but not in the situation given and the indications to verify this action are located in the Aux
( bldg and would be verified by the SRO at the ASP.
D. Incorrect: There are many actions directed in abnormal and emergency procedures which could be considered reactivity manipulations but are performed by non-licensed operators. Plausible because under "normal" conditions, this would be a true statement but the evacuation of the control room would be a situation where this would not be a overriding consideration.
Technical AP-17, Loss of Control (Attach if not previously Reference(s) Room Bkgd Doc (Rev 3) provided)
(Pg 5)
(Including version or revision
- - - - - - - - - #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-AP-17 Obj #
_O_P-_M_C_-_A_P_-1_7_0_b,,-j 2 _ _ (As available)
- _2
~------
Page 2 of4 of 4 Rev
ES-401 Sample Written Examination Form ES-401-5 ES-40 1-5 Question Worksheet Question Source: Bank# NMS
- 1325 Modified Bank # (Note changes or attach
_____ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Control Room Evacuation:
Knowledge of the interrelations between (Control Room Evacuation) and the following:
Reactor Trip System
(
KA is matched because the question is testing the candidates knowledge of criteria for actuation of the reactor trip system during a control room evacuation scenario. The note stated in the stem of the question cautions the operator not to trip the reactor prior to the SRO at the ASP being ready. While this would not be a problem if the operator would simply follow the procedure as written, a licensed operator has the authority to trip the reactor if he feels that this actions is warranted. (Normal operation of the reactor trip system). This note is placed to remind the operator that this is an abnormal situation and that premature tripping of the Rx could significantly degrade the situation. Understanding of the basis of this note examines the candidates understanding of how being in AP-17 relates to when it would be appropriate to operate the reactor trip system which normally puts the plant is a safer state but in this case would not.
(
Page 3 of4 of 4 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X Tier# 2 DRAFT Group # 1 KIA # 078K3.02 Importance Rating 3.4 3.6 Instrument Air Knowledge of the effect that a loss or malfunction of the (SYTEM) will have on the following:
Systems having pneumatic valves and controls Proposed Question: Common 40 1 Pt Given the following:
- Unit 1 is operating at 100% RTP
- Instrument Air (VI) is inadvertently lost to containment Which ONE (1) of the following Main Control Board indications will provide verification that VI has been lost to containment?
A. 1NV-24B (NC Loop To Excess Letdown Heat Exchanger
( Isolation) in the CLOSE position B. 1NV-35A (Variable Letdown Orifice Outlet Flow Control Isolation) in the CLOSE position C. 1NV-459 (Variable Letdown Orifice Outlet Flow Control) in the OPEN position D. 1NV-1A (NC Letdown Isolation Valve) in the OPEN position Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: B Explanation (Optional):
1NV-35A is in containment and is normally open. It fails closed on a loss of VI and therefore provides positive verification that VI has been lost to containment.
A. Incorrect: 1NV-24B is normally closed and therefore would not provide verification that VI had been lost to containment. Plausible because 1NV-24B is inside containment and does fail closed on a loss of VI.
B. Correct.
C. Incorrect: 1NV-459 fails closed on a loss of VI, not open. Plausible because 1NV-459 is inside containment and because it is normally in service (in some intermediate position) and would change position on a loss of VI.
D. Incorrect: 1NV-1A is normally open so the valve failing to the open position does not provide verification that VI has been lost to containment. Plausible because 1NV-1A is in containment and does fail open on a loss of VI.
Technical Lesson Plan OP-MC-PS- (Attach if not previously
( Reference(
Reference(s) s) NV, rev. 55 pages 55 and provided) 59 McGuire Drawing MCFD- (Including version or
_1_5_5_4_-0_1_.0_2_
_15_5_4_-0_1_._02 __ __ __ _ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O~P-....:.cM'-'--C=--...:....P_'=_S--'-N....:.cV_"__','_O=_b:.Lj OP-MC-PS-NV, Obj ....:.c7__
~~~---
7 available)
(As avai lab Ie)
Question Source: Bank#
Modified Bank (Note changes or attach parent)
New x Question History: Last NRC Exam
(
\
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Instrument Air Knowledge of the effect that a loss or malfunction of the (SYTEM) will have on the following:
Systems having pneumatic valves and controls KA is matched because the repositioning of valves is an observable effect on a system due to a loss of VI. The NV system inside containment does contain pneumatic valves and the question is examining knowledge of the effect on these valves of a loss of instrument air to containment. The candidate must have knowledge of both where the given valves are located, what their normal position is with the unit at 100% power, if they are pneumatically operated and in what position they would fail if VI were to be lost.
This is a higher cognitive level because it requires the candidate to know two
( pieces of information and apply those pieces of information to each answer to determine which one is correct.
The candidate must first know how each of the valves provided in the answers fails on a loss if VI. Second, the candidate must know the normal position of each of those valves. Finally, the candidate must apply those two pieces of information to determine if the valve changing position provides positive verification that VI has been lost to Containment.
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X Tier #
Tier# 2 DRAFT Group # 2 KIA # 011A3.03 3.2-Importance Rating - - - - 3.3 Pressurizer Level Control Ability to monitor automatic operations of the (SYSTEM) including:
Charging and letdown Proposed Question: Common 41 1 Pt Unit 1 is operating at 100% power with the PZR level control system in a 1-2 lineup.
The following events occur in the order listed.
- 1) Letdown isolates and all pressurizer heaters de-energize
- 2) Pressurizer level increases
- 3) Charging flow decreases
( What is the cause of these indications?
A. Auctioneered Hi-Tave input to the Pzr Control circuit fails low B. Pressurizer Level Master Controller output has failed low C. Pressurizer level channel channellI fails high D. Pressurizer level channel II fails low
(
Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: D Explanation (Optional):
channell!II failing low would cause letdown to isolate and Pressurizer level channel pressurizer heaters to de-energize. When letdown isolates, pressurizer level increases resulting in a level deviation between Level Channel I and program level. This will cause the output from the Pressurizer Level Master Controller to decrease to a minimum value causing 1NV-238 to close thereby decreasing charging flow.
A. Incorrect: See explanation above. Plausible if the candidate misinterprets the sequence of events. The T-ave input to the level deviation summing unit failing low would cause program level to go to no load level resulting in a level deviation. The level deviation would cause charging flow to decrease to minimum. Pressurizer level would initially decrease until letdown isolates and Pressurizer heaters de-energize. After letdown isolates Pressurizer level would then start to increase. So, the same events occur as in the correct answer only in a different sequence.
B. Incorrect: See explanation above. Plausible if the candidate misinterprets the sequence of events. The charging flow would go to some
( minimum value causing Pressurizer level to decrease resulting in a letdown isolation and heaters de-energizing. Once the letdown isolation occurred pressurizer level would then increase. So, the same events occur as in the correct answer only in a different sequence.
C. Incorrect: See explanation above. Plausible if the candidate misinterprets the sequence of events. If Pressurizer Level Channel ChannellI fails high charging flow would decrease to minimum and Pressurizer level would initially decrease until letdown isolates Pressurizer heaters de-energize. After letdown isolates Pressurizer level would increase. So, the same events occur as in the correct answer only in a different sequence.
D. Correct.
Technical Lesson Plan OP-MC-PS- (Attach if not previously Reference(s)
Reference( s) ILE, rev. 17, page 15 and provided) 37 (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: _O~P~--=..:.M.:....::C~-P~S.::.....-..::..::I OP-MC-PS-ILE,
~~~-----
Obj.
L=E,-,---,--=-0. 12
.: :. obj.L-....:...::12=----_ (As available)
Question Source: Bank# PSILEN09 Modified Bank (Note changes or attach
- _ _ _ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Pressurizer Level Control Ability to monitor automatic operations of the (SYSTEM) including:
Charging and letdown
(
KA is matched because, while monitoring the automatic operation of the system, the candidate must interpret the symptoms of a failure (charging and letdown changing) and determine what has caused the automatic operation of the Pressurizer Level Control system to be affected.
This is a higher cognitive level question because the candidate must interpret multiple symptoms of a failure, in the sequence that those symptoms present themselves to determine what has failed to affect the automatic operation of the system.
(
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier # 1 DRAFT Group # 1 KIA KJA# # 056AG.2.4.35 Importance Rating 3.8 4.0 Loss of Off-site Power!6 Power/6 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects.
Proposed Question: Common 42 1 Pt During recovery form a Loss of all AC power, operators are performing actions in ECA-O.O (Loss of All AC Power)
Which ONE (1) of the following describes the importance of locally isolating the KC supply to the NC pump thermal barriers prior to restarting a KC pump?
A. To prevent damage to the NC pump thermal barriers due to thermal shock.
( B. To prevent potential mechanical failure of the NC pump thermal barriers due to water hammer.
C. To prevent steam from forming and circulating in the KC system and ensures the KC system is available to cool equipment necessary for recovery.
D. To ensure elevated heat loads as a result of the loss of all AC power are within the design cooling capacity of the KC system prior to starting a KC pump.
(
Page 1 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-S ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
During the performance of ECA-O.O, local operator actions are directed to close 1KC-42SA KC-425A (NC Pumps Ret Hdr Cont Outside Isol) and 1KC-338B (NC Pump Sup Hdr Cont Outside Isol) and place stickers next to the Main Control Board switches which state: "Do not reopen due to steam voiding in NCP thermal barriers".
A. Incorrect: See explanation above. Plausible because isolating the cooling water to the thermal barriers will cause the thermal barrier to heat up and thermal shock is potentially a concern. However, the primary concern is the potential introduction of this steam into the main portion of the CCW system upon CCW pump start. This keeps the main portion of the CCW system available for cooling equipment necessary for recovering the plant when ac power is restored.
B. Incorrect: See explanation above. Plausible because isolating the cooling water to the thermal barriers will cause the thermal barrier to heat up and water hammer is a concern due to the resultant voiding. However, the primary concern is the potential introduction of this steam into the main portion of the CCW system upon CCW pump start. This keeps the main
( portion of the CCW system available for cooling equipment necessary for recovering the plant when ac power is restored.
C. Correct.
D. Incorrect: See explanation above. Plausible because after a loss of KC and subsequent restoration the total heat load on the system will be higher than prior to the loss of KC cooling. However, this is not the primary concern.
Technical EP/1/A/5000/ECA-O.O, Loss (Attach if not previously Reference(s) of All AC Power, rev. 25, provided) page 12 Background Document for (Including version or ECA-O.O, Loss of All AC revision #)
Power, rev. page 109 and 110.
Proposed references to be provided to applicants during None examination:
Page 2 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: OP-MC-EP-ECA-O.O,Obj.
OP-MC-EP-ECA-O.O, Obj. (As available) 4 Question Source: Bank# EPECA0018 Modified Bank (Note changes or attach
- _ _ _ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.10 Content:
55.43 Comments:
( Loss of Off-site Power/6 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects.
KA is matched because the candidate is required to understand the operational effects of the given local auxiliary operator tasks associated with ECA 0.0. This generic KIA solicits knowledge of both the task and the operational effects but in this application of the KIA, meeting the first part would require having the RO candidate recall individual procedure steps which require local plant manipulations. This level of procedure memorization is not reasonable.
(
Page 3 of7 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
/
( Examination Outline Cross-reference:
Level RO SRO X X Tier # 1 DRAFT Group # 2 KIA KJA# # WE07EK1.3 Importance Rating 3.2 3.6 Saturated Core Cooling Knowledge of the operational implications of the following concepts as they apply to the (Saturated Core Cooling).
Annunciators and conditions indicating signals, and remedial actions associated with the Saturated Core Cooling.
Proposed Question: Common 43 1 Pt Given the following conditions on Unit 1:
- ES-1.2 (Post LOCA Cooldown and Depressurization) is being performed due to a LOCA inside Containment.
- 1A NV pump and 1A NI pump are running
- Containment pressure is 4 PSIG
- Pressurizer level is 33%
- BOTH subcooling monitors are INOPERABLE
- NC system CETs indicate 500°F
(
- NC system WR pressure indicates 750 PSIG Which ONE (1) of the following describes the condition of the fluid in the NC system and the required actions (if any) based on these indications?
REFERENCE PROVIDED A. Saturated; No additional actions required.
B. Subcooled; No additional actions required.
C. Saturated; Start 1B NI and 1B NV pumps.
D. Subcooled; Start 1B NI and 1B NV pumps.
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Proposed Answer: C Explanation (Optional):
For the given conditions, the candidate must use the provided reference (Enclosure 4.3, Curve 1.1 OB) to determine that the NC system is in a saturated condition.
With the candidates in ES-1.2 (Post LOCA Cooldown and Depressurization) when they identify that saturated conditions exist (i.e. subcooling has been lost) or Pressurizer level is not being maintained, Foldout page criteria in the procedure requires the Operator to "Start additional NVand NI pumps".
A. Incorrect: See explanation above. Plausible because the NC system is in a saturated condition. However, if the candidate does not recall the Foldout criteria, it is reasonable to believe that the procedural steps in ES-1.2 will address the condition or that the procedure is written assuming that saturated conditions may exist in the NC system and as a result no additional actions outside of continuing on in the procedure are required.
B. Incorrect: See explanation above. Plausible if the candidate uses the Steam Tables to determine subcooling instead of using the provided
( reference. If the candidate uses the Steam Tables, they will determine that the NC system is subcooled and also determine that no additional actions are required. The candidate must understand that under post accident conditions, the Steam Tables should not be used to determine subcooling.
C. Correct.
D. Incorrect: See explanation above. Plausible if the candidate uses the Steam Tables to determine subcooling instead of using the provided reference. If the candidate uses the Steam Tables, they will determine that the NC system is subcooled. The candidate must understand that under post accident conditions, the Steam Tables should not be used to determine subcooling. If the candidate does not understand the Pressurizer level requirements for Adverse Containment conditions, they may believe that Pressurizer level is in adequate, apply the Foldout page criteria for SI re-initiation and start the 1B NI and 1B NV pumps.
Technical Reference(s) EP/1/A/5500/F-0, Critical (Attach if not previously Safety Function Status provided)
Trees, rev. 4, page 4 (Including version or revision
- - - - - - - - - - #)
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-EP-FRC Obj. _2
_O_P-_M_C_-_E_P_-F_R_C_O_b,,---j.
~-------
2_ _ _ (As available)
Question Source: Bank#
Modified Bank # (Note changes or attach parent)
New X- - - -
X Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis X X
10 CFR Part 55 55.41 41.9 Content:
55.43
( Comments:
Saturated Core Cooling Knowledge of the operational implications of the following concepts as they apply to the (Saturated Core Cooling).
Annunciators and conditions indicating signals, and remedial actions associated with the Saturated Core Cooling.
KA is matched because the candidate use the indications provided to determine that the NC system is in a saturated condition and determine the remedial actions (start additional NVand NV and NI pumps) required for those conditions.
This question is higher cognitive level because the candidate is required to use the reference provided to analyze plant conditions to determine that the NC system is in a saturated condition. Additionally, the candidate must comprehend that using the Steam Tables post-accident to determine subcooling is not correct.
If the candidate uses the Steam Tables instead of the reference provided they will determine that the NC system is subcooled instead of saturated.
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: XX Tier # 1 DRAFT Group # 2 KJA#
KIA # WE08EK2.1 Importance Rating _3.:...c.,--,4 3.4_ _ 3.7 RCS Overcooling- PTS:
Knowledge of the interrelations between (RCS Overcooling-PTS) and the following:
Components and functions of control and safety systems, including instrumentation, signals, failure modes and automatic and manual features.
Proposed Question: Common 44 1 Pt A SGTR has occurred on Unit 1 and the crew has initiated a cooldown at maximum rate per E-3 (SGTR):
Given the following information:
- NC system pressure is 1850 PSIG
- The Steam Dump Interlock Bypass switches were placed in the "Byp Intlk" position after P-12 was energized
(
- The Steam Dump Mode Selector is in the "Steam Pressure" position.
- The valve positioner for Condenser Dump #1 (SB-3) fails "OPEN" In order to prevent challenging NC system PTS (Pressurized Thermal Shock) limits, which one of the following will halt the resultant NC system cooldown?
A. NC system T-ave decreasing to 553°F.
B. S/G pressures decreasing to 780 PSIG.
C. Placing the Steam Dump Mode Selector to the "T-ave "T-ave Mode" D. Placing the "Steam Dump Interlock Bypass Switches" "A" and "B" to the "OFF" position
(
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: D Explanation (Optional):
The stem of this question sets up a situation where the crew has initiated a cooldown during a SGTR. Once P-12 (553°F) is reached the switch is required "Byp Intk" to allow the cooldown to continue. One of the Steam to be placed in "8yp dumps then fails open due to a local positioner failure. The correct response is to place the Steam Dump Intk Byp 8yp Switches to the "OFF" position. This action repositions a local positioner 3-way valve in the air supply to both block the air supply and vent the supply thereby allowing the steam dumps to fail closed.
A. Incorrect: T-ave decreasing to 553°F with a P-4 signal present results in a feedwater isolation not a main steam isolation. Plausible because this is a valid temperature for actuation of a safety function which is related to preventing a uncontrolled cooldown under different circumstances.
- 8. Incorrect: 780 PSIG is above the low steam line pressure Main Steam B.
Line Isolation setpoint of 775 PSIG. Plausible if the candidate misunderstands the MSI setpoint and believes that a MSI isolation has occurred and halted the cooldown.
( C. Incorrect: Placing the steam dump mode selector in "T-ave" mode only affects the output of the controller located on the control board. The failure described in the stem is a failure of the individual valve positioner.
Plausible as this action would result in the output of the steam dump controller going to "0" and if this was the cause of the cooldown, would be effective.
D. Correct.
Technical OP-MC-STM-IDE, Steam (Attach if not previously Reference(
Reference(s)s) Dump Control System provided)
(Rev 29) Pg 41 of 79 (Including version or
_ _ _ _ _ _ _ _ _ _ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-STM-IDE Obj.4 (As available)
(
Page 2 of5 ofS Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank#
Modified Bank ASTMIDER06 (Note changes or attach
- _ _ _ _ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis xx 10 CFR Part 55 55.41 41.07 Content:
55.43 Comments:
RCS Overcooling- PTS:
Knowledge of the interrelations between (RCS Overcooling-PTS) and the following:
( Components and functions of control and safety systems, including instrumentation, signals, failure modes and automatic and manual features.
KiA KIA is matched because the situation/failure described has put the plant in a condition that, if left unchecked would result in a PTS challenge. The student must apply knowledge of the failure modes of a steam dump and the interlock associated with the steam dump control system that would have to actuated in order to rectify the situation.
Analysis level because the candidate must understand first, what has procedurally transpired prior to the situation given i.e. Low Steam Pressure MSI has been blocked. The candidate must then apply knowledge of the steam dump control system and the failure mode of the steam dump valves to correctly answer the question.
(
Page 3 of5of 5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X
Tier # 3 DRAFT Group #
KIA # G2.4.45 Importance Rating 4.1 Emergency Procedures/Plans:
Generic : Ability to prioritize and interpret the significance of each Annunciator or alarm Proposed Question: Common 72 1 Pt Unit 1 is being returned to full power following a refueling outage when the following annunciators are received in the Control Room:
- The Safety Breaker and Feeder for 1A NC pump both indicated CLOSED
- No other alarms are received. Reactor power is 45% and
( increasing.
Which ONE (1) of the following would be the correct action for the OATC?
A. Manually trip the reactor.
B. Manually feed the affected S/G.
C. Stop the power increase and investigate.
D. Reduce reactor power to less than 48% and trip the 1A NC pump.
(
Page 1 of 4 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
((
Proposed Answer: C Explanation (Optional):
Impulse Channell failing low will actuate rod stop C-5 (1/1 Impulse Pressure channels < 15%) which will stop automatic rod withdrawal but will NOT stop manual rod withdrawal.
A. Incorrect: See explanation above. Plausible because 1 PR channel failing high (>103%) will stop automatic rod withdrawal (C-2). However, this is also a manual rod withdrawal block.
B. Incorrect. See explanation above. Plausible because Loop 1l L1T within 2% of the OP or OT L1T setpoint will stop automatic rod withdrawal (C-3 &
OTllT & C-4).
However, it requires 2/4 channels to be within 2% of the setpoint and it stops both automatic and manual rod withdrawal.
C. Correct:
D. Incorrect: See explanation above. Plausible because Impulse pressure channel failing low is the correct answer. However, Impulse Pressure Channel I is the channel which provides the rod stop.
(
Technical OP-MC-IC-IPE, rev. 28, (Attach if not previously Reference( s)
Reference(s) --'-pp_a--""9'
_a---"9'---e_4_9_ _ _ _ _ _ _ provided)
(Including version or
_ _ _ _ _ _ _ _ _ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-IC-IPE, Obj. 12 (As available)
~--~-----
~-~---
Question Source: Bank# ICIPE042 Modified Bank (Note changes or attach parent)
New Question History: Last NRC Exam Page 2 of4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Reactor Protection Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:
eRDS CROS KA is matched because the candidate must understand the reactor protection signals associated with interlocks which will prevent control rod motion.
This question is higher cognitive level because lAW NUREG-1 021, Appendix A it has "at least two data points which must be associated" and these data points "have to be recalled from memory by the examinee". In this case the data points which must be recalled from memory are the 5 RPS rod stops (C1 thru C5), their
. setpoints, coincidence, monitored parameters, and whether the rod stop affects
( manual rod withdrawal, automatic rod withdrawal, or both (a total of 20 pieces of data to be recalled). The examinee must then compare those data pieces to the symptoms provided and determine which answer matches the symptoms provided.
(
Page 3 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X Tier #
Tier# 2 DRAFT Group # 2 KIA # 033G2.4.31 Importance Rating 4.2 4.1 Spent Fuel Pool Cooling Knowledge of annunciators alarms, indications or response procedures Proposed Question: Common 46 1 Pt Given the following conditions on Unit 2:
- The core has been off-loaded to the Spent Fuel Pool
- 2A KF Pump is running
- 2B KF Pump is off
- A Loss of Off-Site Power occurs
- 2A and 2B EDGs start and load normally
- 30 minutes after the loss of power, a Spent Fuel Pool Hi Temperature alarm is received Which ONE (1) of the following is the cause of this condition?
A. The 2A or 2B KF pump was not manually restarted (sequencer reset required).
B. The 2A or 2B KF pump was not manually restarted (sequencer reset NOT required).
C. The 2A KF pump ONLY did not automatically load on the Blackout sequence as designed.
D. The 2A and 2B KF pumps did not automatically load during the Blackout sequence as designed.
Page 1 of5 Rev Final
ES-401 Sample Written Examination ES-401-5 Form ES-40 1-5 Question Worksheet
(
Proposed Answer: B Explanation (Optional):
On a Blackout signal, the KF pumps will receive a start permissive signal when 2ETA and 2ETB are re-energized by their respective EDGs and Load Group 9 is sequenced onto the busses. However, they will not automatically start and must be manually started by the Operators in the Main Control Room.
A. Incorrect: See explanation above. Plausible because one of the KF Pumps must be started manually. However, the Blackout sequencer does not have to be reset prior to starting the pump.
B. Correct.
C. Incorrect: See explanation above. Plausible because most important loads on ETA and ETB are sequenced on the bus automatically. The candidate may conclude that the KF pump which was running prior to the loss of power should automatically start during the Blackout sequence (since only one pump is normally running).
D. Incorrect: See explanation above. Plausible because most important loads on ETA and ETB are sequenced on the bus automatically. The candidate may conclude that both KF pumps should have been started by their
( respective Blackout sequencers.
Technical Lesson Plan OP-MC-FH- (Attach if not previously Reference(s) _K_F---,,_r_ev_._2_9-,-,-,---pa---,g",--e_2_7___
_K_F---,-,_r_ev_._2_9-,---,-'----pa---'g"-e_2_7___ provided)
(Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-FH-KF, Obj. 12 (As available)
'---~-----
~--~-----
Question Source: Bank#
Modified Bank (Note changes or attach parent)
New x Question History: Last NRC Exam
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.10 Content:
55.43 Comments:
Spent Fuel Pool Cooling alarms, indications or response procedures Knowledge of annunciators alanns, KA is matched because the candidate must understand how the KF System functions to analyze and determine the cause of the Spent Fuel Pool Hi Temperature alarm.
This is a higher cognitive level question because the candidate must associate two data points, one given and one recalled from memory. The given data point is that a Blackout load sequence has occurred (although not given directly) and the data which must be recalled from memory is that the KF pumps do not automatically load on a Blackout and therefore the KF pumps should have been
( restarted manually.
(
Page 3 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier# 3 DRAFT Group #
KIA # G2.2.40 Importance Rating 3.4 3.7 Equipment Control Ability to apply technical specifications for a system.
Proposed Question: Common 47 1 Pt Given the following conditions on Unit 1:
- NC system temperature is 250°F
- 2 NC pumps are in operation Which ONE (1) of the following lists the Tech Spec 3.5.3 (ECCS - Shutdown) operability requirements based on the above conditions?
A. BOTH RHR subsystems must be OPERABLE Charging is not
( required.
B. BOTH Charging and BOTH RHR subsystems must be OPERABLE.
C. ONE Charging subsystem and ONE RHR subsystem must be OPERABLE.
D. BOTH RHR subsystems and ONE Charging subsystem must be OPERABLE.
Page 1 of9 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Proposed Answer: C Explanation (Optional):
Tech Spec 3.5.3 requires that "one ECCS train shall be OPERABLE" in Mode 4.
This means that one Charging subsystem and one RHR subsystem must be OPERABLE.
A. Incorrect: See explanation above. Plausible if candidate confuses the applicable specification (3.5.3) with the RHR and Coolant Circulation - Low Water Level Tech Spec (TS 3.9.6) or the SLC for Power Systems and Decay Heat Removal- Reduced Inventory (SLC 16.5.2)
B. Incorrect: See explanation above. Plausible if the candidate confuses the applicable specification (3.5.3) with the spec for ECCS - Operating (3.5.2) which is applicable in Modes 1, 2, and 3.
C. Correct.
D. Incorrect: See explanation above. Plausible if the candidate mistakenly determines that one charging subsystem should be OPERABLE by TS 3.5.3. and that two RHR subsystem should be operable by SLC 16.5.2 (requiring more than the normal single RHR train required by TS 3.5.3).
(
Technical Reference(s) TS 3.5.3, ECCS - Shutdown (Attach if not previously
_ _ _ _ _ _ _ _ _ _ _ provided)
TS 3.5.2 ECCS - Operating (Including version or revision
- )
SLC 16.5.2, Power Systems and Decay Heat Removal- Reduced Inventory Operation Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-PS-ND, Obj. 11 (As available)
Question Source: Bank# ADMTS023 Modified Bank (Note changes or attach
- parent)
New
(
Page 2 of9 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.10 Content:
55.43 Comments:
Equipment Control Ability to apply technical specifications for a system.
KA is matched because the candidate must apply Technical Specifications for the ECCS system based on given plant conditions. In order to correctly answer the question they must demonstrate an understanding of how the ECCS system requirements change during shut down. Between SLC and TS this requirement is dependent on plant mode, condition of the NC system, water level in the refueling canal.
( This question has been deemed to be a higher cognitive level question because the candidate must first recall the range of temperatures for different plant modes and use that information to determine that the plant is in Mode 4. The candidate must then recall all tech specs which are applicable to the ECCS systems in Mode 4, must recall the specification itself, and determine which of the answers is correct (or which distracters can be eliminated). In order to eliminate the incorrect answers they will have to mentally isolate this specific TS from other SLC requirements which if considered would make the distracters correct.
(
Page 3 of9 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X
Tier# 1 DRAFT Group # 2 KIA KJA# # WE16EA2.1 Importance Rating 2.9 3.3 High Containment Radiation:
Ability to determine and interpret the following as they apply to (High Containment Radiation):
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Proposed Question: Common 48 1 Pt Unit 2 refueling is in progress. Given the following plant alarms:
- 2EMF-3 (Containment Refueling Bridge) Trip 2 alarm
- 2EMF-39 (Containment Gas) Trip 2 alarm
- 2EMF-40 (Containment Iodine) Trip 2 alarm Which ONE (1) of the following procedures should be implemented?
( A. AP-25 (Spent Fuel Damage)
B. AP-40 (Loss of Refueling Canal Level)
C. AP-18 (High Activity in Reactor Coolant)
D. FR-Z.3 (Response to High Containment Radiation Level)
(
Page 1 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):
Per the Entry conditions of AP-25, indications given are consistent with a dropped and damaged fuel assembly and resultant release of fission gasses.
A. Correct.
B. Incorrect: Unless accompanied with failed fuel, gas/iodine monitors should not be in alarm. Plausible for lowering cavity level, 2EMF-3 would be in alarm and is an entry criteria for AP-40 but with the additional indications provided this would not be the correct procedure to implement.
C. Incorrect: AP-18 entry criteria symptoms include reactor coolant filter high rad indications along with EMF-48 Reactor Coolant high rad.
Plausible because with the system opened for refueling, it would be reasonable to assume that activity contained in the reactor coolant system could become airborne and show up on the containment atmosphere radiation monitors. Additionally, when an NC high activity malfunction is inserted on the simulator plant modeling, readings on EMF 39 and 40 will increase and eventually reach alarm status even with the Reactor Coolant System intact.
( D. Incorrect: FR-Z-3 would be implemented only of 1EMF-51 A or B were indicating> 35 R Plausible since the stem of the question establishes a condition of High Radiation in containment.
Technical AP-25, Spent Fuel (Attach if not previously Reference( s)
Reference(s) _D_a.:....m_a.....
-,D"-.a_m_a."' ge_re_v_._8-'-,
-ge_re_v_._8--,--,-'--,---p_a.>.Lge_2
-p_a.....
ge_2__ provided)
(Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O-,,-P,---..:...cM_C_-A_P_-_2_5 _O,--b:...Lj._1
_O--'-----P-_M_C_-_A_P_-2_5_0-'-bL-j. _ _ (As available)
-,-1__
Page 2 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank# MNS
- 358 Modified Bank (Note changes or attach
- _ _ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.10 Content:
55.43 Comments:
High Containment Radiation:
Ability to determine and interpret the following as they apply to (High Containment Radiation):
( Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
KIA is matched because the stem establishes a scenario where fuel damage during refueling operations has resulted in indications of abnormal containment radiation. Utilizing these given indications, the candidate must select the appropriate procedure mitigate.
This question is higher cognitive level because the candidate is expected to evaluate the given indications and select the appropriate abnormal procedure based on those indications. The indications provided are shared between the procedures given as distracters which requires the candidate to evaluate indications taken together instead of simply recognizing one or more is contained in a given AP entry criteria.
(
Page 3 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier # 2 DRAFT Group # 2 KIA # 071A1.06 Importance Rating 2.5 2.8 Waste Gas Disposal Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:
Ventilation system Proposed Question: Common 49 1 Pt Given the following:
- Unit 1 is operating at 100% RTP
- Unit 2 is refueling
- Unit 1 is releasing a minimally decayed Waste Gas Decay Tank
- A significant packing leak starts on isolation valve 1WG-160, ryvG 0fVG Decay Tank Outlet to Unit Vent Control).
( Which ONE (1) of the following correctly describes the automatic actions which will ensure that the leak is contained and filtered?
A. OEMF-50 (Waste Gas Disch Hi Rad) automatically closes 1WG-160 AND 1EMF-41 1EMF-41 (Aux Bldg Vent Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans.
B. 1EMF-41 (Aux Bldg Vent Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans AND 1EMF-36 (Unit Vent Hi Rad) automatically closes 1WG-160.
C. 1EMF-36 automatically closes 1WG-160 AND 1EMF-35 (Unit Vent Part Hi Rad) automatically aligns the Auxiliary Building ventilation filter trains.
D. 1EMF-35 (Unit Vent Part Hi Rad) automatically stops the Auxiliary Building ventilation unfiltered exhaust fans AND 1EMF-41 (Aux Bldg Vent Hi Rad) automatically aligns the Auxiliary Building ventilation filter trains.
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: D Explanation (Optional):
The release of radioactive gas into the Auxiliary Building will be picked up by the Auxiliary Building Ventilation System which discharges to the plant vent. The Unit 1 Low Range Particulate Vent Monitor (EMF 35) should alarm which will automatically stop the Auxiliary Building Unfiltered Exhaust Fans. The Auxiliary Building Ventilation Monitor (EMF 41) should also alarm which will place the Auxiliary Building Ventilation Filter system in service.
A. Incorrect: EMF 50 will not get to Trip 2 because it is set for the activity being released, and EMF 41 does not automatically stop these fans. Plausible as these are automatic actions for the EMF monitors.
B. Incorrect: EMF 41 does not automatically stop these fans. Plausible if the candidates do not recognize that this is not an automatic action for EMF 41 but for EMF 35/37.
C. Incorrect: EMF 35 does not realign ventilation filters. Plausible if the candidate does not recognize that EMF 35 does not realign ventilation filters.
Also, EMF 36 can close 1WG-160. But, since it's setpoint is high enough to allow the release to occur, EMF 36 will not alarm.
( D. Correct.
Technical OP-MC-WE-EMF, rev. (Attach if not previously Reference(s) _2_9-' -,-'--'-p_a
_2_9---,--, .....
ge_2_9
---p_a""-ge_29
_ _____ __ ___ provided)
(Including version or
_ _ _ _ _ _ _ _ _ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-WE-EMF, Obj. 3 (As available)
Question Source: Bank# NRC 771 Modified Bank (Note changes or attach
- _ _ _ _ parent)
New Question History: Last NRC Exam Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.5 Content:
55.43 Comments:
Waste Gas Disposal Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:
Ventilation system KA is matched because the candidate must determine the specific location where effects of the release will be seen to predict the effects on the ventilation system based on which EMF monitor should alarm.
This is a higher cognitive level because the candidate must comprehend the physical location of the leak and based on that location analyze the given answers to determine which automatic actions will mitigate the consequences of the leak.
(
Page 3 of5of 5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X XX Tier# 3 DRAFT Group #
KIA KfA# # G2.1.37 Importance Rating 4.3 4.6 Conduct of Operations Knowledge of procedures, guidelines or limitations, associated with reactivity management.
Proposed Question: Common 50 1 Pt Which ONE (1) of the following lists ALL of the conditions that must be satisfied per OMP 2-2 to allow non-licensed personnel to manipulate facility controls which directly affect reactivity or power level of the reactor?
A. Non-licensed individuals must have completed the ISS Course and be under the direction and in the presence of a licensed operator.
( B. Non-licensed individuals who have been selected for license training are allowed to manipulate controls under 10 CFR 55, as part of training to qualify for an operator license.
C. Non-licensed individuals must have completed all NLO Training and Qualification Guides, under direction and in the presence of a licensed operator, and be performing these manipulations as part of his/her training.
D. Non-licensed individuals must have completed GFES and must be under the direction and in the presence of a licensed operator and be performing these manipulations as part of his/her training to qualify for an operating license.
Page 1 of4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: 0 D
Explanation (Optional):
Per OMP 2-2:
PerOMP Non-licensed individuals who have been selected for license training are allowed to manipulate controls under 10 CFR 55, as part of training to qualify for an operator license. These operations shall be under the direction and in the presence of an NCO.
Controls which affect core reactivity shall NOT be manipulated by non-licensed trainees until successful completion of the NRC GFES exam.
GFESexam.
A. Incorrect: See explanation above. Plausible: both requirements are true but it is not a complete list.
B. Incorrect: See explanation above. Plausible This distracter represents a true statement but not contain all of the requirements.
C. Incorrect. See explanation above. Plausible: both requirements are true but it is not a complete list.
D. Correct: See explanation above. Plausible if the candidate misunderstands that, while ECPs and ECBs must be performed independently by two
( individuals, one of the persons performing the calculation must be a Qualified Reactor Engineer.
Technical OMP 2-2 Conduct of (Attach if not previously Reference(s)
Reference(s) Operations (Rev 2-2) provided)
Pg 20 of 37 (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-ADM-RM, Obj. 10 (As available)
Question Source: Bank# ADMOMP019 Modified Bank (Note changes or attach
- _ _ _ _ _ _ parent)
New Question History: Last NRC Exam Page 2 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.1 Content:
55.43 Comments:
Conduct of Operations Knowledge of procedures, guidelines or limitations, associated with reactivity management KA is matched because the candidate must be able to recall the guidelines concerning reactivity manipulations by non licensed operators as prescribed by the Conduct of Ops OMP.
(
(
Page 3 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X X
Tier#
Tier # 3 DRAFT Group #
KIA KJA# # G2.1.27 Importance Rating 3.9 4.0 Conduct of Operations Knowledge of system purpose and or function.
Proposed Question: Common 51 1 Pt Which ONE (1) of the following describes the design features/components of the NO system which function to protect the system from overpressure?
A. Suction relief - 400 PSIG Discharge relief - 650 PSIG ND-1 Band ND-2A,C opening interlock - < 365 PSIG B. Suction relief - 450 PSIG Discharge relief - 600 PSIG
( ND-1 ND-1B Band and ND-2A,C opening interlock - < 385 PSIG C. Suction relief - 400 PSIG Discharge relief - 650 PSIG ND-1 Band ND-2A,C opening interlock - < 385 PSIG D. Suction relief - 450 PSIG Discharge relief - 600 PSIG ND-1 Band ND-2A,C opening interlock - < 365 PSIG
(
\.
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: B Explanation (Optional):
The overpressure protection for the NO system is provided by a combination of features. The first protective feature is the interlock with NO-1 Band NO-2AC such that the valves will not open when NC system pressure is greater than 385 psig.
This pressure combined with the shutoff head of the NO pump (200 psi) would maintain NO system pressure less than the pump discharge relief valve setpoint.
The second protective feature is the suction and discharge relief valves which lift at 450 and 600 psi respectively.
A. Incorrect: See explanation above. Plausible if the candidate confuses the relief valve setpoints (which appear similar) and the NO-1 B I/ NO-2AC interlock setpoint (365 psig is close to the actual setpoint of 385 psig).
B. Correct.
C. Incorrect: See explanation above. Plausible if the candidate confuses the relief valve setpoints (which appear similar).
O. Incorrect: See explanation above. Plausible if the candidate confuses the NO-1 B I/ NO-2AC interlock setpoint (365 psig is close to the actual setpoint of
( 385 psig).
Technical Lesson Plan OP-MC-PS- (Attach if not previously Reference(
Reference(s) s) NO, rev. 37, page 19 and provided) 21 (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-PS-NO, Obj. 5 (As available)
OP-MC-PS-NO, Obj. 6
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank# PSN0016 PSND016 Modified Bank (Note changes or attach
- _____ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Conduct of Operations Knowledge of system purpose and or function.
KA is matched because the candidate must understand how system design
( features and components function to provide overpressure protection for the ND NO system.
(
Page 3 of5 ofS Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier #
Tier# 2 DRAFT Group # 2 KIA # 079A4.01 Importance Rating 2.7 2.7 Station Air Ability to operate and/or monitor in the control room:
Cross-tie valves with lAS Proposed Question: Common 52 1 Pt Given the following:
- Unit 1 is shutdown in a refueling outage.
- A VI header rupture occurs causing the VI system to completely depressurize.
Which ONE (1) of the following describes how the VS system is prevented from depressurizing due to the break on the VI system?
( A. A valve will automatically close to separate the VI and VS headers. And, the VS air compressor will start automatically to maintain VS header pressure.
B. A valve will automatically close to separate the VI and VS headers. However, the VS air compressor must be manually started to maintain VS header pressure.
C. The VI and VS headers are separated using a manual isolation valve. And, the VS air compressor must be manually started to maintain VS header pressure.
D. The VI and VS headers are separated using a manual isolation valve. However, VS air compressor will start automatically to maintain VS header pressure.
Page 1 of5 ofS Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: 8 B
Explanation (Optional):
The Low Pressure VS System is normally supplied from the VI System via cross-connect valve VI-820 which automatically closes when VI header pressure decreases to 90 psig. The VS system has an air compressor which has an auto-start feature. However, the compressor is normally "OFF" and would therefore have to be manually started to restore VS System pressure.
A. Incorrect: See explanation above. Plausible because VI-820 automatically closes to separate the headers and there is an auto-start feature on the VS air compressor. However, as stated above, the VS compressor is not normally aligned for automatic operation.
B. Correct.
C. Incorrect: See explanation above. Plausible because the VS system is not safety-related and it is therefore reasonable to believe that an automatic isolation valve would be used to prevent the VS from depressurizing.
However, the automatic function is not really to protect the VS system but the VI system which is safety-related. Also, the second part of the question about having to start VS compressor manually is correct.
( D. Incorrect: See explanation above. Plausible because the VS system is not
\
safety-related and it is therefore reasonable to believe that an automatic isolation valve would be used to prevent the VS from depressurizing.
However, the automatic function is not really to protect the VS system but the VI system which is safety-related. Also, there is an auto-start feature on the VS air compressor. However, as stated above, the VS compressor is not normally aligned for automatic operation.
Technical Lesson Plan OP-MC-SS- (Attach if not previously Reference(s)
Reference(s) VI, rev. 32 page 71 and provided) 105 (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P-_M_C_-_S_S_-V_I-,-, _O~bJ,--*7
_O_P_-_M_C_-S_S_-_V-,-I,_O_b-L-j __
_ _ _ (As available)
(
\
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank# NRC 451 Modified Bank (Note changes or attach
- _ _ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Station Air Ability to operate and/or monitor in the control room:
Cross-tie valves with lAS
( KA is matched because the candidate must understand how the cross-tie between VI and VS operates to monitor the system for proper operation when the VI header depressurizes and to be able to operate the VS compressor to re-pressurize the VS system.
(
Page 3 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X X X
Tier # 2 DRAFT Group # 2 KIA KJA# # 034K1.02 Importance Rating 2.5 3.2 Fuel Handling Equipment Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:
RHRS Proposed Question: Common 53 1 Pt Given the following conditions:
- Refueling is in progress on Unit 1.
- Reactor vessel head is removed and the refueling cavity is full.
Which ONE (1) of the following states the requirements for NO Loop operability in accordance with Tech Spec 3.9.5 (Residual Heat Removal (RHR) and Coolant Circulation - High Water Level)
(
\ for the conditions above?
A. ONE NO Loop must be OPERABLE and in operation. An NO Loop consists of one NO pump, one heat exchanger, and a flow path from an NC system COLD leg to an NC system HOT leg.
B. ONE NO Loop must be OPERABLE and in operation. An NO Loop consists of one NO pump, one heat exchanger, and a flow path from an NC system HOT leg to an NC system COLD leg.
C. TWO NO Loops must be OPERABLE with one NO Loop in operation. An NO Loop consists of one NO pump, one heat exchanger, and a flow path from an NC system COLD leg to an NC system HOT leg.
O. TWO NO Loops must be OPERABLE with one NO Loop in operation. An NO Loop consists of one NO pump, one heat exchanger, and a flow path from an NC system HOT leg to an NC system COLD leg.
Page 1 of 10 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: B 8
Explanation (Optional):
Technical Specification 3.9.5 requires that one Residual Heat Removal Loop be "OPERABLE and in operation" during fuel movement (specifically Mode 6 with the water level ~ 23ft above the top of the reactor vessel flange).
level;::
As defined by the Basis Document for TS 3.9.5, an RHR Loop consists of "an RHR pump, a heat exchanger, valves, piping, instruments, and controls to ensure an OPERABLE flow path and to determine the low end temperature. The flow path starts in one of the RCS hot legs and is returned to the RCS cold legs."
This part of the Basis Document is expected RO knowledge by OP-MC-PS-ND Objective 11:
Concerning the Technical Specifications related to the ND NO System:
- Given the LCO title, state the LCO including the composition of an RHR loop listed in the LCO section of Bases ( including any COLR values) and applicability.
A. Incorrect: The assumed flow path is from the hot leg to the cold leg.
Plausible if the candidate confuses the normal flow path for the ND NO system during refueling operations. The requirement for one loop operable and in operation is correct.
B. Correct.
C. Incorrect: Only one RHR loop is required to be operable and the required flow path is from the hot leg to the cold leg. Plausible if the candidate confuses the refueling technical specification with the RCS Loop operability TS for Mode 4 which (with no NC Loops operable) would require both RHR loops to be operable with one loop in operation. The candidate might also confuse the normal RHR loop flow path for refueling operations.
D. Incorrect: Only one RHR loop is required to be operable. The rest of the answer is correct. Plausible if the candidate confuses the refueling technical specification with the RCS Loop operability TS for Mode 4 which (with no NC Loops operable) would require both RHR loops to be operable with one loop in operation.
(
Page 2 of of10 10 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s) TS 3.9.5, Residual Heat (Attach if not previously Removal (RHR) and Coolant provided)
Circulation-High Circulation - High Water Level Oocument TS 3.9.5, Basis Document (Including version or revision Residual Heat Removal #)
(RHR) and Coolant Circulation - High Water Level Lesson Plan OP-MC-PS-NO, OP-MC-PS-ND, rev. 37, page 45 Proposed references to be provided to applicants during None examination:
Learning Objective: _O-'-P_-_M-'
_O-,,---P -C_-P_S_-_N_D_O'
-_M_C-' ----b:...Lj._1_1
--_P_S_-N-=O"---".O......:.b"-j _ _ _ (As available)
.-,-1_1___ ava ilab Ie)
Question Source: Bank #
Bank# ADMTS024 Modified Bank # (Note changes or attach
_ _ _ _ _ parent)
( -----
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X X
Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.2 Content: to 41.9 55.43 Page 3 of10 of 10 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier#
Tier # 2 DRAFT Group # 2 KIA # 028K3.01 Importance Rating _3_._3 3.3_ _ 4.0 Hydrogen Recombiner and Purge Control Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:
Hydrogen Concentration in containment Proposed Question: Common 54 1 Pt Given the following conditions on Unit 1 1::
- A small break LOCA has occurred inside Containment
- E-1 (Loss of Reactor or Secondary Coolant) has been implemented
- Bus 1ETA is de-energized
- The 1B NI pump has failed
- The 1B Hydrogen Recombiner is out of service
- Containment hydrogen concentration is 7%
(
- The TSC has recommended purging containment to reduce hydrogen concentration to 3.5% before energizing the igniters Which ONE (1) of the following statements correctly describes the method for performing this evolution to control the off-site dose?
A. Containment air is exhausted through the Containment Air Release system where it is filtered prior to release to the unit vent stack.
B. Containment air is exhausted through the Incore Instrument Ventilation system where it is filtered prior to release to the unit vent stack.
C. Containment air is exhausted to the Auxiliary Building where it is filtered prior to release to the unit vent stack.
D. Containment air is exhausted to the Annulus where it is filtered prior to release to the unit vent stack.
Page 1 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Proposed Answer: D Explanation (Optional):
Post-LOCA the annulus ventilation system can be used to maintain Containment H2 concentration < 4% by venting the Containment atmosphere to the annulus where it is passed through a filtration system which reduces both the H2 concentration and the iodine concentration prior to discharging to the plant vent.
A. Incorrect: See explanation above. Plausible if the candidate confuses the VQ System (Containment Air Release and Addition) with the VE System (Annulus Ventilation).
B. Incorrect: See explanation above. Plausible if the candidate does not remember that VE releases to the stack to maintain negative pressure in the annulus area.
C. Incorrect: See explanation above. Plausible as this could be a way to filter the release if the air was vented to the auxiliary building.
D. Correct.
Technical Lesson Plan OP-MC- (Attach if not previously Reference(
Reference(s)s) CNT-VE, rev. 25, page 19 provided)
( (Including version or
_ _ _ _ _ _ _ _ _ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-CNT-VE Obj. _1_1_
_O_P-_M_C_-_C_N_T_-V_E_O_bL-j. 11 (As available)
Question Source: Bank #
Bank# NRC 767.1 Modified Bank (Note changes or attach
- _ _ _ _ parent)
New Question History: Last NRC Exam Page 2 of4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Hydrogen Recombiner and Purge Control Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:
Hydrogen Concentration in containment KA is matched because the candidate must understand how Post-LOCA hydrogen concentration can be reduced if both hydrogen recombiners are not available.
(
(
Page 3 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet f
\,
Examination Outline Cross- Level RO SRO reference: X X X
Tier # 2 DRAFT Group # 1 KIA # 007A2.05 Importance Rating 3.2 3.6 Pressurizer Relief / Quench Tank Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
Exceeding PRT high-pressure limits Proposed Question: Common 55 1 Pt Given the following:
- Unit 2 is operating at 90% RTP after a start-up from a refueling outage
- A Pressurizer PORV is found to be leaking
- The leaking PORV's block valve has been shut The PRT has been cooled down to the following current conditions:
(
- PRT level - 65 %
- PRT temperature -100°F - 100°F
- Lower Containment temperature - 118°F What actions are required to restore and maintain normal operating conditions in the PRT for the long term?
A. Vent the PRT to containment.
B. Vent the PRT to the waste gas system.
C. Cool the PRT by initiating spray flow through the sparger line from the FWST.
D. Cool the PRT by pressurizing with nitrogen and initiating spray flow from the NCDT.
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: 8 B
Explanation (Optional):
With PRT pressure> 8 psig and temperature < containment temp, cooling the PRT will only result in the PRT heating back up again and repressurizing due to the temperature increase. The PRT must be vented to the waste gas system to restore pressure to normal and maintain pressure in the normal band.
A. Incorrect: Cannot be performed at power as the vent valve is inside containment and is inaccessible at power. Plausible as venting to containment would accomplish the required action.
B. Correct.
C. Incorrect: Cannot cool the PRT through the sparger line. Plausible since the PRT can be cooled by recircing through the RWST - must pressurize with N2 and recirculate RWST water through the spray and drain connections.
D. Incorrect: Lower Containment temp is 118°F. Cooling the tank further would only delay the time when it would heat back up again and require further cooling. The PRT can be cooled by pressurizing the PRT with nitrogen - but then spray flow must be initiated from the RMWST not the
( NCDT. Plausible as cooling will reduce pressure temporarily but will not allow the PRT to reheat to its normal limit of 114°F without getting a high-pressure condition (containment temp is 118°F). In addition, recirculating through the NCDT using the NCDT pumps cools the PRT and pressure would be reduced - temporarily.
Technical Lesson Plan OP-MC-PS- (Attach if not previously Reference(
Reference(s) s) NC, rev. 30 pages 39 and provided) 41 (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P-_M_C_-_P_S_-N_C_,,---O_b--,-j_.1_9__
_O_P_-_M_C_-P_S_-_N_C-,-,_O--,bjL-'_19
_ _ (As available)
{
Page 2 ofS of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank# PSNCN03 Modified Bank (Note changes or attach
_ _ _ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.5 Content:
55.43 Comments:
Pressurizer Relief I Quench Tank Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
(
Exceeding PRT high-pressure limits KA is matched because the candidate must analyze the given conditions and determine the appropriate actions to restore PRT conditions to normal after a PORV discharge into the tank.
This question is analysis level as the candidate must compare the indications in the PRT and the conditions in Containment to determine that the only appropriate action is to vent the PRT to the Waste Gas system.
Page 3 of5 ofS Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X X X
Tier Tier## 2 DRAFT Group # 1 KIA # 013K2.01 Importance Rating 3.6 3.8 Engineered Safety Features Actuation Knowledge of electrical power supplies to the following:
ESFAS I safeguards equipment control Proposed Question: Common 56 1 Pt Given the following initial conditions on Unit 2:
- A unit shutdown and cooldown was in progress
- All actions associated with NC system pressure going below P-11 were completed
- 'B' Train components are in service The following sequence of events occurs:
( 1. 120VAC Vital Panelboard EKVD de-energizes due to an electrical fault
- 2. 'A' Main Steam line ruptures
- 3. Pressurizer pressure is 1840 PSIG and going down
- 4. Containment pressure is 1.2 PSIG and going up What is the status of the Unit 2 Emergency Core Cooling System (ECCS) equipment? (Assume no operator actions have occurred.)
A. All ECCS equipment is operating.
B. None of the ECCS equipment is operating.
C. Only 'A' Train ECCS equipment is operating.
D. Only 'B' Train ECCS equipment is operating.
Page 1 of9 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
For this accident, the Safety Injection Signal from Pressurizer Low Pressure has already been blocked (actions for NC system pressure below P-11). However, the Safety Injection signal for Hi Containment Pressure is still function and has been actuated due to Containment pressure at 1.2 psig.
The Train 'A' ECCS Train has actuated normally. However, Train '8' 'B' ECCS Train will NOT automatically actuate due to the loss of power to EKVD (Solid State Protection Train '8'
'B' Output Cabinet).
A. Incorrect: Only Train 'A' of ECCS starts due to the loss of power to SSPS Train '8'
'B' Output Cabinet. Plausible if candidate does not understand that the loss of EKVD effects SSPS Train '8' 'B' or believes that an signal from either train of SSPS will actuate both trains of ECCS equipment.
- 8. Incorrect: Train A of ECCS starts due to the Hi Containment Pressure B.
signal. Plausible if the candidate believes that below P-11 all automatic SI signals can be blocked or believes that the loss of EKVD effects both trains ofSSPS.
of SSPS.
( C. Correct: Train A of ECCS starts due to the Hi Containment Pressure signal.
D. Incorrect: Only Train 'A' of ECCS starts due to the loss of power to SSPS Train '8'
'B' Output Cabinet. Plausible if the candidate does not understand from which bus each train of SSPS is powered and believes that Train 'A' of SSPS is affected instead of Train '8'.
'B'.
Technical Lesson Plan OP-MC- (Attach if not previously Reference(
Reference(s) s) ECC-ISE, Engineered provided)
Safeguards Actuation System, rev. 31, pages 17,21,and Lesson Plan OP-MC-EP- (Including version or EPL, 125VDC and revision #)
120VAC Vitall&C Power rev.22, page 19 Proposed references to be provided to applicants during None examination:
( Learning Objective: OP-MC-ECC-ISE Obj. 7 (As available)
~---
\
Page 2 of9 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Question Source: 8ank#
Bank#
Modified Bank 8ank ECCISEN011 (Note changes or attach
- _ _ _ _ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Engineered Safety Features Actuation Knowledge of electrical power supplies to the following:
ESFAS I/ safeguards equipment control
( KA is matched because the candidate must understand where each train of SSPS is powered from and that an automatic Safety Injection has occurred where only one train of ECCS has started due to a loss of control power to the other train.
This question is analysis level because the candidate must analyze the conditions given and determine that a Safety Injection signal has been generated. The candidate must also know that the loss of EKVD de-energizes
'B' Train SSPS Output Cabinet which will prevent the SI Train '8' the '8' 'B' Sequencer from functioning.
(
Page 3 of9 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier Tier# # 2 DRAFT Group # 1 KJA# 025K5.01 Importance Rating 3.0 3.4 Ice Condenser Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):
Relationships between temperature and pressure.
Proposed Question: Common 57 1 Pt Given the following:
- Unit 2 is operating at 100% RTP
- It has been determined that eight (8) Ice Condenser doors will not open due to floor buckling Which ONE (1) of the following statements describes the
( Containment design pressure AND how peak Containment pressure during a Design Basis Accident is affected by the condition above?
A. Containment design pressure is 3 psig. Peak pressure will be reached LATER than normal.
B. Containment design pressure is 3 psig. Peak pressure will be reached SOONER than normal.
C. Containment design pressure is 15 psig. Peak pressure will be reached LATER than normal.
D. Containment design pressure is 15 psig. Peak pressure will be reached SOONER than normal.
(
Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Proposed Answer: 0 D
Explanation (Optional):
The concern with buckling in the ice condenser bays is that it will interfere with the proper operation of the lower ice condenser doors. If the ice condenser doors do not open as design, the containment design pressure of 15 psig could be exceeded.
The time to reach peak containment occurs at approximately 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> after a double-ended shear of the NC piping due to the depletion of the ice in the ice condensers. With the ice condenser doors not opening peak containment pressure will be higher than normal and will be reached sooner than normal.
A. Incorrect: See explanation above. Plausible if the candidate confuses the containment pressure for actuation of Phase B and Containment Spray with the Containment design pressure. Also, the candidate may misunderstand the relationship between available ice condenser surface area and the rate of rise of Containment pressure during a DBA.
B. Incorrect: See explanation above. Plausible if the candidate confuses the containment pressure for actuation of Phase B and Containment Spray with
( the Containment design pressure. Also, Containment pressure will peak
\ sooner than normal.
C. Incorrect: See explanation above. Plausible if the candidate misunderstands the relationship between available ice condenser surface area and the rate of rise of Containment pressure during a DBA.
D. Correct:
Technical Lesson Plan OP-MC- (Attach if not previously Reference(s) CNT-NF, rev 30 pages 19 provided) and 63 Lesson Plan OP-MC- (Including version or CNT-CNT, rev 14 page revision #)
63 Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-CNT-NF, Obj. 20 (As available)
(
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank#
Modified Bank (Note changes or attach
- _ _ _ _ parent)
New x Question History: Last NRC Exam - -------------------------------
Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.5 Content:
55.43 Comments:
Ice Condenser Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):
Relationships between temperature and pressure.
KA is matched because the candidate must understand the potential effect of ice condenser doors not opening on peak containment pressure and the time to reach peak containment pressure during a Design Basis Accident. The effect of the blocked Ice Condenser doors is to reduce the effectiveness of the Ice Condenser to remove thermal energy from Containment.
This question is higher cognitive level because it requires understanding beyond that of fundamental knowledge. It requires the candidate to apply fundamental knowledge to a given condition to predict the impact of those initial conditions.
(
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X
Tier#
Tier # 2 DRAFT Group # 1 KIA # 059A4.03 Importance Rating 2.9 2.9 Main Feedwater Ability to manually operate and / or monitor in the control room:
Feedwater control during a power increase and decrease Proposed Question: Common 58 1 Pt Given the following conditions:
- A power ascension to 100% RTP is in progress on Unit 1
- Power is currently 60%
- 1A S/G CF Control valve fails open Which ONE (1) of the following statements best describes the system response with no operator action?
When the 1A S/G NR level exceeds 83%, a Feedwater Isolation will occur...
A. both FWPTs will go to no-load speed, and a turbine trip will occur, however no reactor trip is generated.
B. both FWPTs will trip which starts the MD CA pumps, and a turbine trip will occur which generates a reactor trip.
C. both FWPTs will go to no-load speed, and a turbine trip will occur which generates a reactor trip.
D. both FWPTs will trip which starts the MD CA pumps, and a turbine trip will occur, however no reactor trip is generated.
(
Page 1 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: 8 B
Explanation (Optional):
At 83% in 1/4 S/Gs a feedwater isolation on all four S/Gs occurs. Additionally, both main CF pump turbines trip which starts both motor-driven CA pumps. Also, the Main turbine trips and with reactor power greater than 48% (P-8) a reactor trip signal is generated as a result of the turbine trip.
A. Incorrect: A feedwater isolation occurs on all four S/Gs. Plausible because a single S/G feedwater isolation on high level in one S/G is a common Westinghouse plant protection scheme.
B. Correct.
C. Incorrect: Both CF pumps trip instead of going to no-load speed. Plausible because both CF pumps could go into recirc at no-load speed and the effect would be the same provided the feedwater isolation occurs as designed.
Both CF pumps tripping is a backup to the feedwater isolation should it be unsuccessful.
D. Incorrect: A reactor trip is generated by the turbine trip. Plausible if the candidate does not remember the P-8 permissive to trip the reactor on a turbine trip when reactor power is >48%.
(
Technical Lesson Plan OP-MC-CF- (Attach if not previously Reference( s)
Reference(s) CF, Main Feedwater, rev. provided) 32, page 35 (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-CF-CF, Obj. 12 (As available)
OP-MC-CF-CF, Obj. 13 OP-MC-CF-CF, Obj. 14 Question Source: Bank# ACFCFR12 Modified Bank (Note changes or attach
- _ _ _ _ _ parent)
New
(
Page 2 of4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 ES-40 1-5 Question Worksheet Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Main Feedwater Ability to manually operate and lor
/ or monitor in the control room:
Feedwater control during a power increase and decrease KA is matched because the candidate must understand the response of the plant to the CF control valve failing open.
This question is comprehension level since the failure occurs during a power ascension and the ability to determine the correct answer is dependent upon understanding the plant response at the given power level.
(
Page 3 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X Tier# 2 DRAFT Group # 1 KfA# 062A3.05 Importance Rating 3.5 3.6 AC Electrical Distribution Ability to monitor the automatic operations of the (SYTEM) including:
Safety-related indications and controls Proposed Question: Common 59 1 Pt Given the following conditions on Unit 1:
- A loss of voltage has occurred on 1ETA
- Blackout loading is in progress
- A Safety Injection signal is received before Blackout loading is completed on 1ETA Which of the following describes the events that occur from the time the Safety Injection signal is received?
(
A. The Blackout load sequence is completed, 1ETA is cleared of all non-SI loads, and the SI load sequence is actuated.
B. The Blackout load sequence is completed, 1ETA is cleared of all loads, and the Slload sequence is actuated.
C. The Blackout load sequence stops, 1ETA is cleared of all non-Slloads, SI loads, and the SI Slload load sequence is actuated.
D. The Blackout load sequence stops, 1ETA is cleared of all loads, and the Slload sequence is actuated.
(
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
When a Blackout has occurred and load sequencing is in progress, if an SI signal is received, the Blackout sequence stops, the effected bus is cleared of non-Slloads, and the Slload SI load sequence is actuated. Slloads which were previously running continue to operate.
A. Incorrect: The Blackout sequence is not completed. It is stopped and the SI sequence is started. Plausible if the candidate misunderstands the function of the Blackout sequencer and believes that the Blackout sequence must be complete to ensure full restoration of power to the Emergency Bus.
B. Incorrect: The Blackout sequence is not completed. It is stopped and the SI sequence is started. Plausible if the candidate misunderstands the function of the Blackout sequencer and believes that the Blackout sequence must be complete to ensure full restoration of power to the Emergency Bus.
C. Correct.
D. Incorrect: The Emergency Bus is not cleared of all loads prior to starting the SI sequence. It is only cleared of non-SI loads. Plausible if the candidate confuses the Blackout sequence and the SI sequence as all loads are
( cleared on a Blackout sequence.
Technical Lesson Plan OP-MC-DG- (Attach if not previously Reference(s) EQB, Diesel Generator provided)
Load Sequencer, rev. 16, page 27 (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-DG-EQB, Obj. 7 (As available)
Question Source: Bank# DGEQB021 Modified Bank (Note changes or attach
- _ _ _ _ _ parent)
New
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
AC Electrical Distribution Ability to monitor the automatic operations of the (SYTEM) including:
Safety-related indications and controls KA is matched because the candidate must possess the ability to monitor the automatic loading of safety-related equipment during all possible load sequence scenarios and determine that the sequencer has operated properly using Main Control Board indications for the various sequencer loads.
(
(
Page 3 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier #
Tier# 2 DRAFT Group # 1 KfA#
KJA# 063A3.01 Importance Rating 2.7 3.1 DC Electrical Distribution Ability to monitor automatic operations of the (SYSTEM) including:
Meters, annunciators, dials, recorders and indicating lights Proposed Question: Common 60 1 Pt Given the following conditions on Unit 1:
- The unit is at 100% power.
- The following annunciator is received in the Control Room:
o BATT EVCAGROUND EVCA GROUND Which ONE (1) of the following describes the indication available if the ground is on the positive leg of battery EVCA, and the resulting operation
( of the DC Bus?
A. Ground indication light on the back of the Main Control Board will be brightly lit. Equipment malfunctions are NOT expected with a ground on one side.
B. Ground indication light on the back of the Main Control Board will be brightly lit. Equipment malfunctions are expected with a ground on either the positive OR negative terminal.
C. Ground indication light on the back of the Main Control Board will be extinguished. Equipment malfunctions are NOT expected with a ground on one side.
D. Ground indication light on the back of the Main Control Board will be extinguished. Equipment malfunctions are expected with a ground on either the positive OR negative terminal.
(
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: 0 D
Explanation (Optional):
A. Correct: Annunciator indicates that light on back of MCB will be brightly lit.
Design of DC Bus is to operate on 1 but not both legs with a ground B. Incorrect: Designed to operate with a ground on 1 terminal, Plausible: Because a ground is not desirable on any part of the system C. Incorrect: Light will be lit. Plausible: Because applicant may assume that light will be out due to no voltage drop from positive leg to ground, resulting in light going out.
D. Incorrect: Light will be lit. Credible for same reason as C, and second part credible for same reason as B Technical Annunciator Response for (Attach if not previously Reference(s)
Reference( s) 1AD 11-B-3 rev 66 page 1AD11-B-3 provided) 21 Lesson Plan OP-MC-EL- (Including version or EPL 125 VDC (EPL) and revision #)
VitaliI &
120 VAC (EPG) Vital &C Power (Rev 23) Pg 47 of 73 Proposed references to be provided to applicants during None examination:
Learning Objective: _ _ _ _ _ _ _ _ _ _ (As available)
Question Source: Bank# ELEPL044 Modified Bank (Note changes or attach
- parent)
New Question History: Last NRC Exam MNS 2007
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
DC Electrical Distribution Ability to monitor automatic operations of the (SYSTEM) including:
Meters, annunciators, dials, recorders and indicating lights KA is matched because the candidate must know the implications the receipt of an annunciator associated with a ground on a battery. He must demonstrate the ability to monitor the condition of the system by recalling the indications which would be associated with receipt of this alarm.
(
(
Page 3 of5 of 5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X X X
Tier Tier# # 1 DRAFT Group # 1 KIA #
KfA# 025AK2.02 Importance Rating 3.2 3.2 Loss of Residual Heat Removal System Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following:
Removal / RHR pumps Proposed Question: Common 61 1 Pt Unit 1 has experienced a large break LOCA.
Given the following conditions:
- Six hours have elapsed since the LOCA
- ES 1.4 (Hot Leg Recirc) has been implemented
- 18 NI pump is unavailable
(
- NO Train 'A' has been aligned for Hot Leg Recirc
- NO Train '8' is aligned for Auxiliary Containment Spray Which of the following best describes the effects on the NO system if the 1A NO pump trips?
A. Flow is lost to the 'A', '8', 'c' 'C' and '0' hot legs.
- 8. Flow is lost to the 'A' and '8' hot legs ONLY.
C. Flow is lost to the '8' and 'c' 'C' hot legs ONLY.
O. Flow is lost to 'A' and '0' hot Legs ONLY.
(
\
Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Proposed Answer: C Explanation (Optional):
With 1 NI-121A unable to open and 1 1NI-121A 1BB NI pump unavailable, ES-1.4 will have the operators align NO Train A to provide flow to the NC system loops 'B' and 'c' hot legs. If the system were in cold leg recirc the system would be providing flow to all four NC loop cold legs.
A. Incorrect: See explanation above. Plausible if the candidate does not understand all flow paths for the NO system. If the system was still on cold leg recirc the NO system would be providing flow to all four NC system cold legs. This answer is plausible if the candidate confuses the available hot leg flow paths with the cold leg flow paths.
B. Incorrect: See explanation above. Plausible if the candidate does not understand all flow paths for the NO system. The two NO trains are split performing separate functions. If the system was still on cold leg recirc, Train A could be providing flow to 'A' and 'B' cold legs. This answer is plausible If the candidate confuses the hot leg and cold leg flow paths.
C. Correct.
O. Incorrect: See explanation above. Plausible if the candidate does not
( understand all flow paths for the NO system and confuses which loops receive flow from the respective NO trains.
Technical Lesson Plan OP-MC-PS- (Attach if not previously Reference(s) NO, rev 37 pages 51,73, provided) 75 (Including version or
_ _ _ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-PS-NO Obj. 8____ (As available)
_O_P-_M_C_-_P_S_-N_O_O_b-"---j._8
~---
Question Source: Bank #
Bank# NRC 1027 Modified Bank (Note changes or attach parent)
New
(
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question History: Last NRC Exam 2003 McGuire NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Loss of Residual Heat Removal System Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following:
Removal / RHR pumps KA is matched because candidate must understand the NO system flow paths for different modes of operation and understand the implications of losing an NO pump for a specific system alignment. Operation of the NO pumps during hot leg recirculation is part of the Low Pressure Injection (LPI) function of the system.
(
(
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X Tier #
Tier# 2 DRAFT Group # 1 KIA # 103K4.06 Importance Rating -3.1 ---
3.7 Containment Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the following:
Containment Isolation System Proposed Question: Common 62 1 Pt Which of the following will occur simultaneously with an automatic Containment Spray Actuation?
A. Main Steam Isolation.
B. Phase A Isolation.
C. Containment Ventilation Isolation.
( D. Feedwater Isolation.
(
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):
The automatic Containment Spray signal is actuated by a Hi-Hi Containment pressure which is the ONLY automatic isolation for Containment Spray. The Hi-Hi Containment pressure signal will also initiate a Main Steam Isolation signal (MSI).
A. Correct.
B. Incorrect: See explanation above. Plausible because a Phase A Isolation will occur on any of the Safety Injection Signals, one of which is the Containment Hi pressure signal. However, by the time pressure is high enough to cause the automatic Containment Spray actuation, the Phase A Isolation should have already occurred.
C. Incorrect: See explanation above. Plausible because the Containment Ventilation Isolation will occur on any of the Safety Injection signals, one of which is the Containment Hi pressure signal. However, by the time pressure is high enough to cause the automatic Containment Spray actuation, the Containment Ventilation Isolation should have already occurred. Also, the Containment Ventilation will also occur on a manual Phase B. A Phase B signal will be generated on the Hi-Hi Containment pressure. However, this is an automatic Phase B and will not generate a Containment Ventilation
( Isolation signal (again it should have already occurred).
D. Incorrect: See explanation above. Plausible because the Feedwater Isolation will occur on any of the Safety Injection signals, one of which is the Containment Hi pressure signal. However, by the time pressure is high enough to cause the automatic Containment Spray actuation, the Feedwater Isolation should have already occurred.
Technical OP-MC-ECC-ISE, rev. (Attach if not previously Reference(s)
Reference(s) _3_1--'--,-',--'-p_a
_3_1---' ......
ge_3_3
-p_a-"' -ge_3_3_ _ _ _ _ provided)
(Including version or
__ __ __ __ _ ____ __ __ _ revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-ECC-ISE Obj. 13 (As available)
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Question Source: Bank #
Bank# ECCISE043 Modified Bank (Note changes or attach
- _ _ _ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Containment Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the following:
Containment Isolation System
(
KA is matched because the candidate must understand all of the isolations which are part of Containment isolation and what causes those isolations. In this case the candidate must understand what will cause a Main Steam Isolation signal relative to the Containment Isolation function.
Page 3 of of55 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X Tier #
Tier# 2 DRAFT Group # 2 KIA # 017K6.01 Importance Rating _2=-.:...:...72.7_ _ 3.0 In-core Temperature Monitor Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):
Sensors and detectors Proposed Question: Common 63 1 Pt Given the following:
- Unit 1 @ 100% RTP
- CETs currently indicate 615°F
- A malfunction of the Reference Junction Box temperature control causes the junction box temperature to INCREASE by 20°F Assuming that ACTUAL core-exit temperature remains constant,
( which ONE (1) of the following lists the new indication for the non-safety related CETs?
(
Page 1 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: 0 Explanation (Optional):
Non-safety related thermocouple indication goes to the OAC via Reference Junction Boxes located in Containment. The Reference Junction Boxes are maintained at a constant temperature by a heater circuit. The CET indicated temperature is based on the temperature difference between the measuring junction at the core exit and the temperature at the reference junction. If the temperature at the reference junction increases by 20°F, the liT i1T between the measuring junction decreases by 20°F and therefore the indicated temperature decreases by 20°F. Since the initial CET temperature was 615°F, the new indicated temperature would be 595°F.
A. Incorrect: See explanation above. Plausible if candidate misinterprets the direction of the failure and believes that indication goes high instead of low. If the indication went high, this would be the correct answer.
B. Incorrect: See explanation above. Plausible if candidate misinterprets the direction of the failure and believes that indication goes high instead of low and believes that the indication is based on the average of the two
( temperatures instead of the difference between the two temperatures.
C. Incorrect: See explanation above. Plausible if candidate believes that the indication is based the average of the two temperatures instead of the difference. If it was based on the average of the two temperatures, this would be the correct answer.
D. Correct.
Technical Lesson Plan OP-MC-IC- (Attach if not previously Reference(s) . . :. .ENA, E=N.. .:. . A. . :. . , - - ,rev.
~--~~~-------
9, page r- =-e. . :. . v.=--9::.2.,--"' ge-=---::. 119 p=a...... . . :. . 9_ _ provided)
(Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P_-_M_C_-_IC_-E_N_A_O-,bj,--.6
_O_P-_M_C_-_IC_-_E_N_A_O_b-Lj_. _ _ (As available)
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank#
Modified Bank (Note changes or attach
- _ _ _ _ parent)
New x Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
In-core Temperature Monitor Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):
Sensors and detectors
( KA is matched because the candidate must understand how in-core thermocouple indication is affected by a malfunction of the reference junction box temperature control (which is part of the detector circuitry).
This is a higher cognitive level question because the candidate must comprehend how a reference junction box temperature malfunction affects CET indication and calculate the new indicated temperature based on the given malfunction.
(
Page 3 of5 of 5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
( Examination Outline Cross- Level RO SRO reference: X X X Tier #
Tier# 1 DRAFT Group # 1 KJA#
KIA # 065AA1.01 Importance Rating -2.7 ---
2.5 Loss of Instrument Air Ability to operate and I/ or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION) and the following:
Remote manual loaders Proposed Question: Common 64 1 Pt Given the following conditions:
- Unit 1 is in Mode 4
- NO system is providing core cooling
- AP-22, Loss of VI has been implemented
- NO system flow rate is being controlled by throttling:
1N1-173A (1 A NO to A & B Cold Legs Cont Outside Isol) 1NI-178B (1B NO to C & 0 Cold Legs Cont Outside Isol) 1NI-178B
(
Which ONE (1) of the following describes the requirements in AP-22 for operating the manual loaders for 1NO-14 and 1NO-29 (1 B/1A NO Hx Outlet Isolation)?
A. Turn the manual loaders 5-6 times in the clockwise direction to ensure that the valves close when VI pressure is returned to normal.
B. Turn the manual loaders 5-6 times in the counter-clockwise direction to ensure that the valves close when VI pressure is returned to normal.
C. Turn the manual loaders 5-6 times in the clockwise direction to ensure that the valves remain open when VI pressure is returned to normal.
O. Turn the manual loaders 5-6 times in the counter-clockwise direction to ensure that the valves remain open when VI pressure is returned to normal.
(
Page 1 of5 Rev Final
ES-401 Sample Written Examination ES-40 1-5 Form ES-401-5 Question Worksheet
( Proposed Answer: C
\
Explanation (Optional):
In AP-22, Operators are procedurally directed to turn the manual loaders for 1ND- NO-14,29 14, 29 and 34 five to six times in the clockwise direction to ensure that they remain open when VI pressure is returned to normal.
A. Incorrect: See explanation above. Plausible because turning the loader in the clockwise direction is the correct direction. The candidate may also believe that turning the loader in the clockwise direction would normally close the valve and it is plausible to believe that having the valves close would be conservative to prevent possible runout of the pumps. However, since the pumps were running to begin with and the valves fail to the open position, having them go closed is less conservative as it imposes a transient on the system.
B. Incorrect: See explanation above. Plausible if the candidate believes that having the valves close when VI is restored is conservative to prevent potential runout of the pumps. Additionally, operating the manual loader in the counter-clockwise direction is the correct direction to have the valves close when VI is restored. However, since the pumps were running to begin with and the valves fail to the open position, having them go closed is less conservative as it imposes a transient on the system.
( C. Correct.
O. Incorrect: See explanation above. Plausible if the candidate believes that D.
operating the manual loaders in the counter-clockwise direction would normally open the valves since having the valves remain open when VI pressure is restored is the correct and conservative action.
Technical AP-22, rev. 28, page 6 (Attach if not previously Reference(s) _ _ _ _
_ _ _ _ _ _ provided)
(Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O-'OP-MC-AP-22, Obj.._4__
P-_M_C_-_A_P_-2_2--'-,_O_bL-j
~~------
4 (As available)
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Question Source: Bank#
Modified Bank (Note changes or attach
- _ _ _ _ parent)
New x Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Loss of Instrument Air Ability to operate and I/ or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION) and the following:
Remote manual loaders KA is matched because candidate must understand the consequences of the loss of VI with regards to controlling the plant and when conditions are met which require Operator action.
This question is higher cognitive level because the candidate must understand the procedure strategy in AP-22 and analyze the answers provided to determine which conditions pose an immediate threat to continued operation of the unit.
Page 3 of5 of 5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
{
\ Examination Outline Cross- Level RO SRO reference: X X X Tier# 3 DRAFT Group #
KIA # G2.3.4 Importance Rating 3.2 3.7 Radiation control Knowledge of radiation exposure limits under normal and emergency conditions.
Proposed Question: Common 65 1 Pt Given the following on Unit 1:
- A valve lineup is being performed in the mechanical penetration area
- An air line failure caused a severe airborne contamination problem
- The Operator performing the lineup received both internal and external contamination that was detected upon attempting to exit the RCA
(
Which ONE (1) of the exposures would exceed a 10CFR20 annual exposure limit?
A. 45 REM to the thyroid.
B. 17 REM to the lens of the eye.
C. 45 REM to the leg below the knee.
D. 17 REM to the skin of the right forearm.
Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Proposed Answer: B8 Explanation (Optional):
The LDE dose limit (lens of the eye) is 15 REM/year. The SDE dose limit (skin and extremities) is 50 REM/year. The CDE dose limit (internal organs) is 50 REM/year.
i A. Incorrect: See explanation explanatibn above. Plausible if the candidate confuses the CDE dose limit with the LDE dose limit.
B. Correct. 15 REM is the LDE dose limit.
C. Incorrect: See explanation above. Plausible if the candidate confuses the SDE dose limit with the LDE dose limit.
D. Incorrect: See explanation above. SDE is an external dose not an internal dose. Plausible if the candidate confuses the SDE dose limit with the LDE dose limit.
Technical Duke Energy Radiation (Attach if not previously Reference(s)
Reference( s) Worker Training, Dose provided)
Limits and Guidelines,
( page 3 of 13 (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: Duke Energy Radiation (As available)
Worker Training, Dose Limits and Guidelines, Enabling Objective 1 Question Source: Bank#
Modified Bank Catawba (Note changes or attach
- NRC parent)
Bank 577 New Question History: Last NRC Exam 2008 Catawba NRC Exam
(
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 41.12 Content:
55.43 Comments:
Radiation control Knowledge of radiation exposure limits under normal and emergency conditions.
KA is matched because the candidate must be familiar with radiation exposure limits under normal conditions.
(
Page 3 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X X
Tier #
Tier# 2 DRAFT Group # 1 KJA#
KIA # 073A1.01 Importance Rating _3_._2 3.2 _ _ 3.5 Process Radiation Monitoring:
Ability to predict and/or monitor changes in parameters associated with operating the (Process Radiation Monitoring) System controls including:
Radiation Levels Proposed Question: Common 66 1 Pt Given the following:
- In preparation for a containment entry RP requested that a U-1 RO to align 1EMF 38.39,40 to sample Upper Containment only,
- Due to a miscommunication from RP the request is never made to realign this sample point to normal.
- 1EMF 38.39 & 40 sample point remains aligned to upper containment ONLY over the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(
- A VQ release in is in progress.
Which ONE (1) of the following describes the effect on the U-1 EMF 38.39,
& 40 sample package's ability to monitor changing radiation levels associated with conditions inside U-1 Containment?
A. Due to the limited amount of communication between atmosphere in upper and lower containment, 1EMF-38 will not be able to detect a 1 GPM NC system leak within one hour.
B. Because air is released from upper containment, this will have no effect on the ability of the affected EMF's to auto terminate a VQ release should radiation levels increase.
C.
C .. Prolonged operation of this EMF sample package aligned to Upper Containment ONLY could result in damage to the associate sample pump resulting in a degraded sample flowrate.
D. Due to the normal mixing of containment atmosphere by the ventilation system, this does not significantly effect the ability of this sample package to sample the containment atmosphere.
(
Page 1 ofof55 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):
A. Correct: According to the basis of T.S. 3.4.15 (RCS Leakage Detection Instrumentation), a sample from the lower containment region is required for NC leakage detection. The reason is that the NC system is physically located within the lower containment region. Applicable RP and Operations procedures reflect this requirement. For example, the Semi-Daily PT has a note to alert the operators that EMF-38 is inoperable if the sample pump is selected to Upper Containment only for greater than 15 minutes.
B. Incorrect: During a va release, air is released from lower containment and added to upper. This is done to prevent inadvertently opening a ice condenser door due to a pressure imbalance. Plausible: This would be a true statement if air was released from upper containment during a va release.
C. Incorrect: As long as at least one of the three sample points is selected damage to the sample pump is not an issue. Plausible: The EMF lesson plan contains the following statement, "To prevent damage to the sample pump, at least one flow path must be opened. The sample air is returned to the containment'\.
containment",. This would add plausibility with a distracter containing a concern with the flowpath alignment.
D. Incorrect: By design there is very limited communication between the upper and lower containment atmospheres. Plausible: The lower containment ventilation system contains significant capability to move a large amount of air. Upper containment is not sealed from lower otherwise water from containment spray and
( condensing water from the outlet of the ice condensers would never make it to the containment sump for recirculation under LOCA conditions. It would not be unreasonable for the candidate to assume there would be a significant amount of communication between the two areas.
Technical Lesson Plan OP-MC-WE- (Attach if not previously Reference(s) EMF (Rev 29) Pg 23 & 25 provided)
(Including version or revision
-- -- -- -- - -- -- -- --- #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P_-_M_C_-W_E_-E_M_F_O-----"bj_:
_O_P-_M_C_-_W_E_-_E_M_F_O_b .....j_:4_ _ (As available)
Question Source: Bank#
Modified Bank # (Note changes or attach
_ parent)
New x Page 2 of5 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.5 Content:
55.43 Comments:
Process Radiation Monitoring:
Ability to predict and/or monitor changes in parameters associated with operating the (Process Radiation Monitoring)
System controls including:
Radiation Levels KA is matched because the question proposes a change in the operational alignment of the containment atmosphere process radiation monitors. The candidate is then required to predict the impact on the monitoring capability of the associated monitors to detect changing radiation levels within the containment atmosphere.
( This question meets the requirement of being classified as analysis level because the candidate must take the information given, alignment change, and predict an outcome or impact to the functional capability of the affect process radiation monitors. He is required to understand both the design of the system and the basis for having the package normally aligned to lower containment.
Page 3 ofof55 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X
Tier #
Tier# 2 DRAFT Group # 1 KIA # 076A1.02 Importance Rating 2.6 2.6 Service Water Ability to predict and/or monitor changes in parameters associated with operating the (Service Water) system controls including:
Reactor and turbine building closed cooling water temperatures.
Proposed Question: Common 67 1 Pt Given the following:
- Unit 2 is operating at 100% RTP
- 'B' Train is in service
- 2A RN train is in operation for testing
- The RN trains are split with 2RN-41 B (Train B to Non-Ess Hdr Isol) closed
- 2B RN pump flow is reading approximately 2700 GPM Which ONE (1) of the following statements correctly describes the potential consequences of positioning the controller for 2RN-190B (RN to B KC HX Control) to a value of 100% demand?
A. Containment temperature will decrease.
B. NC pump stator temperatures will decrease.
C. NC pump bearing temperatures will decrease.
D. Aux Building AHU discharge temperatures will decrease.
(
Page 1 of6of 6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
The action described in the stem of the question would result in maximum flow to the 2B KC heat exchanger and with "B" Train KC in service, KC temperatures would significantly decrease. NC Pump bearing oil coolers are being supplied by the "B" Train KC and would result in the associated decrease in bearing temperatures.
A. Incorrect: With the RN trains split, containment cooling is being supplied from "A" Train RN and RV. Plausible as the action described in the stem of the question would result in a significant decrease in the U-2 "B" train RN pressure. With 2RN-41 B open, this would be a correct statement.
B. Incorrect: NC Pump stator coolers are supplied from the RN Rx Bldg Non-Essential Header. With the trains split, this header is supplied from "A" Train RN. Plausible if the candidate does not realize that in the given configuration, the NCP stator coolers are being supplied from "A" Train.
C. Correct.
D. Incorrect: VA (Aux Bldg Ventilation) is normally supplied by a combination of RN and RV from both Units. With the trains separated the supply from U-2 would be provided form the "A": Train. Plausible if the candidate does not
( realize that in the given configuration, the NCP stator coolers are being supplied from "A" Train.
Technical Lesson Plan OP-MC-PSS- (Attach if not previously Reference(
Reference(s) s) RN (Rev 42) Pg: 31,33 & & provided) 77 (Including version or revision
- -- -- -- - -- -- -- --- #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P_-_M_C_-P_S_S_-_R_N_O---"bj,--:8_ _ (As available)
_O_P_-M_C_-_P_S_S_-R_N_O_b-,--,-j_:
Question Source: Bank#
Modified Bank # (Note changes or attach
_ _ _ _ parent)
New -
X- -
( Question History: Last NRC Exam Page 2 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(( Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.5 Content:
55.43 Comments:
Service Water Ability to predict and/or monitor changes in parameters associated with operating the (Service Water) system controls including: Reactor and turbine building closed cooling water temperatures.
KA is matched because the candidate is presented with a specific configuration of the Nuclear Service Water System. A system control is manipulated and the candidate must evaluate the impact on the KC (Component Cooling) system reactor building non-essential header temperature. This header is a closed loop cooling water system cooled by Nuclear Service Water.
This question is justified as analysis because the candidate muct not only evaluate an abnormal configuration of the RN system, he must then evaluate the impact of making a flow rate adjustment and predict the impact of that adjustment on another system.
Page 3 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X Tier Tier# # 3 DRAFT Group #
KIA KfA# # G2.4.39 Importance Rating -3.9
--- 3.8 Emergency Procedures/Plans (Generic)
Knowledge of the RO's responsibilities in emergency plan implementation.
Proposed Question: Common 68 1 Pt Unit 1 is operating at 100% RTP. Given the following events and conditions:
2100 Power is lost to all Control Room annunciators 2120 The OSM declares an Unusual Event 2125 The Emergency Notification form is completed, and the OSM directs an operator to make the notification to the state and counties 2130 A reactor trip occurs on Unit 1 and the OSM declares a Site
( Area Emergency 2135 The OSM completes a new Emergency Notification Form and directs the notification of state and counties Which ONE (1) of the following indicates the time when the state and counties must be first notified of the events described above?
A. 2135 B. 2140 C. 2145 D. 2150 Page 1 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):
The original declaration time for an event was 2120. State and counties are required to be notified within 15 min of the initial emergency declaration for NOUE. Therefore, the state and counties must be notified by 2135.
A. Correct.
B. Incorrect: See explanation above. Plausible if the candidate believes the clock start when the Emergency Notification Form is completed.
C. Incorrect: See explanation above. Plausible if the candidate believes that if an upgrade occurs prior to the initial notification the 15 minute clock resets to the upgraded declaration time.
D. Incorrect: See explanation above. Plausible if the candidate believes the initial notification clock resets and also starts when the notification form is complete.
Technical Lesson Plan OP-MC-EP- (Attach if not previously
( Reference(s) _E_M_P--,,-(R_e_v_12-L.)_P....,.g,-.
_E_M_P....>..(R_e-=--v-' _19_ _ _ provided)
12-L)_P--"'g'.---....:....19-=----__
(Including version or revision
- - - - - - - - - - #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P_-_M_C_-E_P_-_E_M_P_O_b. . j:_1_2
_O_P-_M_C"--_E_P_-E_M_P_O.......:.b..Lj . .:_1_2__
. _ _ (As available)
Question Source: Bank #
Bank#
Modified Bank # X (Note changes or attach
_ _ _ _ parent)
New Question History: Last NRC Exam Page 2 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 Content:
55.43 Comments:
Emergency Procedures/Plans (Generic)
Knowledge of the RO's responsibilities in emergency plan implementation.
KA is matched because the RO is trained to be able to fill the role of the emergency communicator and this question examines knowledge of the times limits associated with making an initial notification when an upgrade in classification occurs prior to completion of the initial notification.
(
Page 3 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X
Tier #
Tier# 3 DRAFT Group #
KIA #
KJA# G2.3.14 Importance Rating - 3.4
_3_._4__
3.B 3.S Radiation control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Proposed Question: Common 69 1 Pt A male worker needs to repack a valve in an area that has the following radiological characteristics:
- The worker's present exposure is SOD BOO mREM for the year.
- =
General area dose rate = 65 mREM/hr
- Airborne contamination concentration = 20 DAC =
The job will take 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with a mechanic wearing a full-face respirator. It will only take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if the mechanic does NOT wear
( the respirator.
Which of the following choices for completing this job would maintain the workers exposure within the Station ALARA requirements?
A. The worker should wear the respirator otherwise he will exceed 25% of the DAC limit.
B. The worker should NOT wear the respirator because the total TEDE dose received will be greater if he wears one.
C. The worker should NOT wear the respirator because the dose received will exceed neither NRC nor site dose limits.
D. The worker should wear the respirator because the total TEDE dose received will be less than if he does not wear one.
(
Page 1 of4of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: 8 B
Explanation (Optional):
Radiation exposure comparison:
Without respirator
DOE = 65 mrem/hr x 2 hr = 130 mrem DDE From airborne contamination:
=
CEDE =20 DAC 2 hr x 2.5 mrem/DAC-hr = 100 mrem=
TEDE = =130 + 100 ==230 mrem from job Total exposure for year = =800 + 230 ==1030 mrem With respirator
DOE = 65 mrem/hr x 4 hr = 260 mrem DDE CEDE 0 =
TEDE = 260 mrem
Total exposure for year = 260 + 800 = 1060 mrem (with respirator) (without respirator)
TEDE = = 1060 mrem > 1030 mrem ==do NOT use a respirator
( A. Incorrect: See explanation above. Will not exceed 25% the DAC limit -
this is not how DAC is applied to exposure limits. Plausible because 25%
DAC is the limit at which an area requires posting as a high airborne contamination area.
B. Correct.
C. Incorrect: See explanation above. The decision to wear respirator is based on ALARA for that job. It is not related to whether the yearly dose will be exceeded or not. Plausible if the candidate does not know the station admin limit or miscalculates the dose received.
D. Incorrect: See explanation above. The exposure will be greater if you wear the respirator. Plausible if the candidate incorrectly computes the exposure
- this was the correct answer on the 1997 Catawba NRC exam.
Technical GET Training Material, (Attach if not previously Reference(s) Radworker Part 2, slide provided) 18 (Including version or revision #)
Proposed references to be provided to applicants during None examination:
Page 2 of4 of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Learning Objective: OP-MC-RAD-RP, Obj. 60 (As available)
Question Source: Bank #
Bank# RADRPN08 Mod ified Bank Modified Ban k (Note changes or attach
_ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.12 Content:
55.43 Comments:
Radiation control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or
( activities KA is matched because the candidate must identify the magnitude of the exposure hazard for wearing a respirator as opposed to not wearing a respirator.
The question is analysis level since the candidate must use the data given to calculate the worker's exposure with and without a respirator to determine the correct course of action to maintain dose ALARA. The candidate must also recall the relationship between DAC-hours and dose rate.
(
Page 3 of4of 4 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X X
Tier #
Tier# 1 DRAFT Group # 1 KIA # 057AA2.09 Importance Rating -3.1 ---
3.4 Loss of Vital AC Inst. Bus Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION: '
T T-ave.
-ave. and TT-ref
-ref chart recorder Proposed Question: Common 70 1 Pt The following conditions exist on Unit 1: 1:
- Reactor Power is 25%
- A momentary loss of power occurs on EVCA
- When power returns to EVCA the following instrument failures occur:
- First Stage Turbine Impulse Pressure Channel 1 fails high
(
- Power Range Channel N-41 fails high Which ONE (1) of the following correctly completes the statement below?
Tref on the Tave / Tref recorder indicates ...
A. 585°F but control rods do not move.
55rF but the control rods do not move.
B. 557°F C. 585°F and the control rods step out at 72 steps per minute.
D. 55rF 55]DF and the control rods step in at 72 steps per minute.
(
Page 1 of8 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):
The First Stage Pressure Impulse Pressure Channel 1 failing high drives Tref to the 100% value of 585°F. This would normally cause control rods to step out at 72 steps per minute due to the Tave / Tref deviation. However, Power Range Channel N-41 failing high results in an auto and manual rod withdrawal block.
A. Correct.
B. Incorrect: See explanation above. The First Stage Pressure Channel failing high drives Tref to the 100% value of 585°F. Plausible if the candidate misunderstands the First Stage Pressure Channel relationship to Tref and believes that Tref is driven to its no-load value. At 5% power the Tave / Tref deviation would not result in a large enough mismatch to cause the control rods to move.
C. Incorrect: See explanation above. The control rods will not move.
Plausible because Tref does fail to 585°F and a large Tave / Tref deviation is generated. However, with Power Range Channel N-41 failed high, an auto and manual rod withdrawal block is generated.
D. Incorrect: See explanation above. The First Stage Pressure Channel
( failing high drives Tref to the 100% value of 585°F. Plausible if the candidate misunderstands the First Stage Pressure Channel relationship to Tref and believes that Tref is driven to its no-load value. Candidate must also misunderstand that the Tave / Tref deviation is not large enough to cause rod motion.
Technical Lesson Plan OP-MC-IC- (Attach if not previously Reference(s)
Reference( s) IPE, rev. 28 pages 47 and provided) 49 Lesson Plan OP-MC-IC- (Including version or IRX, rev. 23,
--~----~~~-------
--~~--~~~-------
page 15 revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: _O_P_-_M_C_-I_C_-I_P_E---,O---,b.L-j._1_1
_O_P-_M_C_-_I C_-_IP_E---,-O-,-,bJL-'._1_1_ _ (As available) availab Ie)
(
Page 2 of8 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank#
Modified Bank ICIPEN06 (Note changes or attach
- _____ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.10 Content:
55.43 Comments:
Loss of Vital AC Inst. Bus Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION: '
T-ave. and T-ref chart recorder
( KA is matched because the candidate must understand how and instrument failure caused by a loss of power impacts the Tave I/ Tref chart recorder indication.
This question is analysis level as the candidate must evaluate the effect of two separate failures on Main Control board indications and on the Rod Control system to determine the correct answer.
Page 3 of8 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X Tier # 3 DRAFT Group #
KIA #
KJA# G2.2.17 Importance Rating 2.6 Equipment Control:
(Generic): Knowledge of the process for managing maintenance activities during power operations.
Proposed Question: Common 71 1 Pt Which ONE (1) of the following colors associated with the Electronic Risk Assessment Tool identifies a condition where a safety function is immediately and directly threatened?
A. White B. Orange
( c.
C. Red D. Yellow
(
Page 1 of4 of 4 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
In accordance with ERA ERATT criteria a RED condition exists if a Safety Function is immediately and directly threatened.
A. Incorrect: See explanation above. Plausible if the candidate does not understand the criteria for all ERAT level of risk conditions.
B. Incorrect: See explanation above. Plausible if the candidate does not understand the criteria for all ERAT ERAT level of risk conditions.
C. Correct.
D. Incorrect: See explanation above. Plausible if the candidate does not understand the criteria for all ERAT level of risk conditions.
Technical OP-MC-ADM-MRA, OP-MC-ADM-M RA, (Attach if not previously Reference(s)
Reference( s) Maintenance Rule provided)
Assessment, (Rev 10), Pg 45 SOMP 02-02, Operations (Including version or revision Roles In The Risk #)
( Management Process (Rev 5)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-ADM-MRA Obj: 6_ _ (As available)
_O_P-_M_C_-_A_D_M_-_M_R_A_O_b---,-j_:
Question Source: Bank# ADMMRA013 Modified Bank (Note changes or attach
_ _ _ _ parent)
New Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis Page 2 of4 of 4 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet 10 CFR Part 55 55.41 Content:
55.43 Comments:
Equipment Control:
(Generic): Knowledge of the process for managing maintenance activities during power operations.
KA is matched because the overall station risk due to at power maintenance activities are managed by the Electronic Risk Assessment tool (ORAM).
Reactor operators are expected to be familiar with the significance of the levels of risk associated with this process and this question requires the candidate to be knowledgeable with the significance of each "Color".
(
Page 3 of4 of 4 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X Tier# 3 DRAFT Group #
KJA#
KfA# G2.4.45 Importance Rating 4.1 Emergency Procedures/Plans:
Generic : Ability to prioritize and interpret the significance of each Annunciator or alarm Proposed Question: Common 72 1 Pt Unit 1 is being returned to full power following a refueling outage when the following annunciators are received in the Control Room:
- The Safety Breaker and Feeder for 1A NC pump both indicate CLOSED
- No other alarms are received. Reactor power is 45% and
( increasing.
Which ONE (1) of the following would be the correct action for the OATC?
A. Manually trip the reactor.
B. Manually feed the affected S/G.
C. Stop the power increase and investigate.
D. Reduce reactor power to less than 48% and trip the 1A NC pump.
(
\
Page 1 of4of 4 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):
The indications and annunciators presented are indicative of a NC Pump with a sheared shaft. Flow had been lost to the "A" Loop and with reactor power> 48 % a reactor trip due to Lo Flow should have occurred.
A. Correct.
B. Incorrect: See explanation above. Manual Reactor Trip is warranted.
Plausible: If the candidate fails to recognize indications of a NC pump sheared shaft, this would be correct per AP-06 (S!G (S/G Malfunction) Immediate actions the Stm Flow!
Flow/ Feed Flow mismatch annunciator is a entry condition for this AP.
C. Incorrect: See explanation above. Plausible if the candidate failed to realize from the indications the affected NC pump is no longer moving water, this would be a reasonable course of action.
D. Incorrect: See explanation above. Plausible as tripping the "A" NC Pump is warranted based of the given conditions but the power level is irrelevant.
Reducing power to less than P-8 would prevent an auto Rx Trip but in this situation, an ATWS has occurred and this would not be correct.
Technical OMP 4-3 Use of Abnormal (Attach if not previously Reference(s) and Emergency provided)
Procedures (Rev 29)
Pg; 8 of 36 OP-MC-ADM-OMP (Rev (Including version or revision
_2_7--L-) _ _ _ _ _ _
_2_7..L...)- - - - - - - - #) _ _ #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-ADM-OMP Obj #8 (As available)
Question Source: Bank# EPEOR13 Modified Bank # (Note changes or attach
_ _ _ _ _ parent)
New Question History: Last NRC Exam Page 2 of4 of 4 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 Content:
55.43 Comments:
Emergency Procedures/Plans:
Generic : Ability to prioritize and interpret the significance of each Annunciator or alarm KA is matched because the candidate is expected to take a given set of annunciators and indications to determine that a ATWS ATWS has occurred and determine the appropriate action required per Emergency Procedures. The candidate must both understand the significance of the alarms but also prioritize which require action. This is also the basis for this question reaching the Analysis cognitive level.
(
(
Page 3 of4of 4 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Examination Outline Cross- Level RO SRO reference: X X
Tier # 3 DRAFT Group #
KIA # G2.2.4 Importance Rating -3.6 ---
Equipment Control:
(Generic): Ability to explain the variations in control board layouts, systems, instrumentation, and procedural actions between units at a facility.
Proposed Question: Common 73 1 Pt The following conditions exist:
- Both units are operating at 100% RTP
- The following alarms are received on both units:
o 1AO-11 C-5 (XFMR A URGENT ALARM) 1AD-11 o 2AO-11 C-5 (XFMR A URGENT ALARM) 2AD-11
- Each alarm is the result of a loss of BOTH Cooling Groups to the
( respective transformer.
Which ONE (1) of the following describes the difference in the Operator's response to these two annunciators?
A. The 1A Main Transformer cooling must be restored within 8 min 45 sec in order to prevent a turbine runback to <56%.
B. The 1A Main Transformer cooling must be restored within 28 min 45 sec in order to prevent a turbine runback to <56%.
C. The 2A Main Transformer cooling must be restored within 8 min 45 sec in order to prevent a turbine runback to <56%.
o The 2A Main Transformer cooling must be restored within 28 min 45 D
sec in order to prevent a turbine runback to <56%.
Page 1 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet
(
Proposed Answer: C Explanation (Optional):
Per ARP for 2AD-11 C5, A Runback occurs in 8 min 45 sec on loss of power of both cooling groups.
A. Incorrect: There is not Auto Runback associated with the loss of cooling to the 1A Main Transformer. Plausible because this would be the correct answer if it was affecting the 2A Main Transformer.
B. Incorrect: There is no auto runback associated with the loss of cooling to the 1A Main Transformer. Plausible because this answer is correct if the conditions in the stem described a loss of ONE cooling group associated with the 2A Main Transformer.
C. Correct.
D. Incorrect: For the conditions given, a runback would occur sooner.
Plausible because this would be the correct answer if the alarm was due to a loss of one cooling group.
Technical Lesson Plan OP-MC-GEN- (Attach if not previously
( Reference(
Reference(s)s) EHC Digital Electro- provided)
Hydraulic Control System, (Rev 35) Pg 77 Annunciator Response for (Including version or revision
_1_A_D_-_11_re_v_.6_6--,--p--..-.:ag",-e_3_6
_1_A_D_-_1_1_re_v_.6_6_p' --a---"g"----e_3_6_ _ #)
Annunciator Response for 2AD-11 rev.58 page 36 Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-GEN-EHC Obj: 13 (As available)
Question Source: Bank #
Bank#
Modified Bank # (Note changes or attach parent)
New X Question History: Last NRC Exam Page 2 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge X Level:
Comprehension or Analysis 10 CFR Part 55 55.41 Content:
55.43 Comments:
Equipment Control:
(Generic): Ability to explain the variations in control board layouts, systems, instrumentation, and procedural actions between units at a facility.
KA is matched because the candidate is expected to be able to explain the differences in procedural (ARP's) CARP's) actions associated with the same annunciator on both units.
(
(
Page 3 of6 Rev
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X Tier # 2 DRAFT Group # 1 KfA# 022K4.03 Importance Rating 3.6 4.0 Containment Cooling Knowledge of CCS design feature(s) and/or interlock(s) which provide for the following:
Automatic Containment Isolation Proposed Question: Common 74 1 Pt Given the following conditions on Unit 1:
- A LOCA has occurred.
- Safety Injection has been initiated Which ONE (1) of the following describes the operation of the Containment Cooling system based on these conditions?
A. All VU units have started and RV containment isolation valves are
( open.
B. All VU units have started and RV containment isolation valves are closed.
C. All VU units have shunt tripped off and RV containment isolation valves are open.
D. All VU units have shunt tripped off and RV containment isolation valves are closed.
(
Page 1 of5of 5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
As a result of the Safety Injection signal a Phase A signal has also occurred. The Phase A signal causes the VU units to shunt trip off. However, RV remains aligned to the units. RV would isolate if a Phase B signal were received.
A. Incorrect: See explanation above. Plausible if the candidate confuses the operation of the VU units with the VL units. The VL units would start on the Safety Injections signal. Also, RV remains aligned to the VU units.
B. Incorrect: See explanation above. Plausible if the candidate confuses the operation of the VU units with the VL units. The VL units would start on the Safety Injections signal. The candidate may also confuse the operation of the RV containment isolation valves during a Phase A with the operation during a Phase B in which case the valves would close.
C. Correct.
D. Incorrect: See explanation above. Plausible if the candidate confuses the operation of the RV containment isolation valves during a Phase A with the operation during a Phase B in which case the valves would close. Also plausible because the VU fans do shunt trip off due to the Phase A signal.
(
Technical Lesson Plan OP-MC- (Attach if not previously Reference(s) CNT-VUL, rev. 27 page provided) 41 Lesson Plan OP-MC- (Including version or CNT -RV, rev 19 page 37 CNT-RV, revision #)
Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-ECC-ISE, Obj 7
~--~---
(As available)
~--~---
Question Source: Bank#
Modified Bank (Note changes or attach parent)
New x Question History: Last NRC Exam
(
Page 2 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.7 Content:
55.43 Comments:
Containment Cooling Knowledge of CCS design feature(s) and/or interlock(s) which provide for the following:
Automatic Containment Isolation KA is matched because the candidate must understand the operation of the RV system containment isolation valves for various plant conditions.
This question is analysis level because the candidate must comprehend the status of the RV system based on analysis of the given conditions.
(
(
Page 3 of5 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross- Level RO SRO reference: X X X X
Tier # 2 DRAFT Group # 1 KIA # 061A2.05 Importance Rating 3.1 3.4 Auxiliary / Emergency Feedwater Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
Automatic control malfunction.
Proposed Question: Common 75 1 Pt U-1 is operating at 100% RTP. Given the following events and conditions:
- In preparation for a Unit 1 TO CA pump performance test the following valves are positioned as indicated:
o 1CA-64AB 1CA-64AB (TO CA Pump To 1A S/G) -- CLOSEO CLOSED o 1CA-52AB (TO CA Pump To 1B S/G) -- CLOSED CLOSEO o 1CA-48AB (TO CA Pump To 1C S/G) -- OPEN
( o 1CA-36AB 1 CA-36AB (TO CA Pump To 10 S/G) -- OPEN
- An air line supplying 1SA-48ABC (SM FRM S/G 1C TO TO CA PUMP ISOL) ruptures resulting in a loss of air to the valve.
Which ONE (1) of the following describes the impact to the U-1 CA system and what actions are required by the operating crew to mitigate the consequences of this event?
A. ALL flow control valves OPEN:
Crew should close all TO CA flow control valves immediately.
B. ALL flow control valves OPEN:
Crew should close all TO CA flow control valves when directed by procedure.
C. Flow control valves remain AS IS:
Crew should close all TO CA flow control valves immediately.
D. Flow control valves remain AS IS:
Crew should close all TO CA flow control valves when directed by procedure.
Page 1 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):
In the scenario given, the loss of air to the TD TO CA Pump steam supply valve would result in the valve opening and a resultant pump start. This pump is capable of feeding all four S/G's via the four flow control valves listed, two of which are not in their normal full open alignment. During an auto start, these valves are designed to fail open providing full design flow to all S/G's. In this scenario, no auto start has occurred therefore the flow control valves would remain as is. With no reason given to believe otherwise, all S/G levels would be at their respective program values therefore, per OMP 4-3, the operator is allowed to control CA flow without the use of a procedure.
A. Incorrect: See explanation above First part incorrect, second part wrong.
Plausible: Second part is correct, for the first, it would be reasonable for the operator to believe the control valves would fail open on any pump start.
B. Incorrect: See explanation above. Both parts incorrect. Plausible As explained above control valves opening is plausible. For the second part,
( there are only 3 actions operators are specifically allowed to perform outside of procedure so a distracter indicating waiting for procedural guidance would be plausible.
C. Correct.
D. Incorrect: See explanation above. First part correct, second is incorrect.
Plausible: First part correct, second is plausible as explained above.
Technical Lesson Plan OP-MC-CF- (Attach if not previously Reference(s) CA, rev. 39 pages 15 and provided) 17 OMP 4-3 Use of Abnormal (Including version or and Emergency revision #)
Procedures (Rev 29)
Pg 7 of 36 Proposed references to be provided to applicants during None examination:
Learning Objective: OP-MC-CF-CA, Obj. 4, 7 (As available)
(
Page 2 of6 Rev Final
ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank#
Modified Bank (Note changes or attach
- _ _ _ _ parent)
New x Question History: Last NRC Exam Question Cognitive Memory or Fundamental Knowledge Level:
Comprehension or Analysis x 10 CFR Part 55 55.41 41.5 Content:
55.43 Comments:
( Auxiliary I/ Emergency Feedwater Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
Automatic control malfunction.
KA is matched because the candidate is given a scenario where a failure has occurred to the TO CA (Loss of air) which would result in the unintended start of the pump representing a loss of normal automatic control. Given an out of normal alignment of the flow control valves associated with the operation of this pump, he must predict the impact of the pump start on these valves. The candidate is then asked for the proper procedural actions required to mitigate the consequence of this event. Closing the two open flow control valves immediately is directed by Operations Management Procedure 4-3 which allows an operator to control CA flow anytime S/G level is at program which in the situation given, they would be.
This is an analysis level question since the candidate must evaluate whether or not a TO CA pump start due to an inadvertent opening of the steam supply valve 1SA-48ABC would result in the associated flow control valves failing to their full open normal auto start position. While this single piece of information recall could be considered low cog, he is given an abnormal alignment and predict an outcome. Additional recall is required to assess what action must then be taken
( to mitigate this event.
Page 3 of6 Rev Final
(
2009 RO License Exam References Table of Contents
(
The following references are provided:
- MNS U-l Data Book Curve 7.38
- MNS U-lU -1 Data Book Curve 1.1.10b lOb
- Copy of the Steam Tables