ML033090464
| ML033090464 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/21/2003 |
| From: | Duke Energy Corp |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-369/03-302, 50-370/03-302 | |
| Download: ML033090464 (52) | |
Text
Final Submittal (Blue Paper)
- 1.
Senior Operator Written Examination With Answers, KAs, and Answer Sheet MCGUlRE OCTOBER 2003 EXAM 50-369 & 50-370/2003-302 OCTOBER 21,2003
US. Nuclear Regulatory Commission McGuire Nuclear Station SRO Written Examination Applicant Information Name:
Date:
October 2 1, 2003 FacilityAJnit:
McGuire Region:
I1 Reactor Type:
W Start Time:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with a 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone reauire an 80.00 percent to pass. You have eight hours to complete the combined examination, and three hours if you are only takine the SRO portion.
Applicant Certification All work done on this examination is my OM.
I have neither given nor received aid Applicant's Signature Results SRO-Only / Total Examination Values 25 i 25 Points Applicant's Scores i
Points Applicant's Grade i
Percent NUREG-1021, Draft Revision 9
QUESTION #l 1
MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 1081 Answer: B Unit 1 is operating at 100 % power when a loss of VI event occurs.
AP/l/A/5500/22 (Loss of VI) has been implemented.
VI header pressure is 55 psig and going down.
Which of the following conditions would initially jeopardize the plant and require the SRO to direct tripping the Unit 1 Reactor per AP/liAi5500/22 1 Ptis)
(Loss of VI)?
A.
B.
C.
D.
1NV-238 (Charging Line Flow Control) fails closed.
1CF-23AB (B S/G CF Control Vlv) fails closed.
1RN-252B (RB Non Ess Sup Cont Outside Isol) fails closed.
1NV-34A (,,A NC Pump Return Isolation) fails closed.
____-_l___l_l_l_----_I---I----------------
Distracter Analysis:
A.
Xncorrect:..lNV-238 fails open.
Plausible: If loss of all charging and seal injection was criteria for Rx trip and operator thought valve failed closed.
Correct: Step 12 of Mi22 checks S/G levels stable, if not and level is going down in uncontrolled manner, then trip Rx. With 1CF-23 closed, S/G level would be rapidly decreasing.
Incorrect: Eventually M/22 fold out page would direct tripping the Rx if NC Pump temperatures got high enough.
Plausible 1RN-252B does fail closed and could eventually lead to a Rx trip (see above)
Incorrect:. 1NV-34A fails open on loss of VI.
Plausible B.
C.
D.
Page 1 of 49 RESTRICTED ACCESS 10/2 1/2003
QUESTION # 2 MCGUIRE NUCLEAR STATION SRO EXAM Level: SRO KA: 065 AA2.06 3.614.2 Lesson Plan Objective: OP-MC-AP-22 Obj 3 Source: New Author: Rob Billings Level of knowledge: Memory
References:
- 1. M i 2 2 Basis Document, page 13 Page 2 of 49 RESTRICTED ACCESS 1012112003
QUESTION # 3 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 1075 Answer: B 1 Pt(s)
Unit 2 has just completed a refueling outage. Two hundred (200) ice baskets were reloaded during the outage. Chemistry has determined that the pH of the ice in the baskets that were reloaded have an average pH of 8.0, verses the 9.0 to 9.5 that is required. Boron concentration is 1850 ppm.
Which one of the following statements correctly describes the concerns with the sample?
A.
B.
C.
D.
Reduced boron solubility following a LOCA Reduced iodine removal in the event of a LOCA Increased caustic stress corrosion following a LOCA Insufficient sump boron concentration following a LOCA
__1_____1___-__111__1-111-------1---1--1------------------
Distracter Analysis: The key to this question is realizing that the basis for maintaining limits on basic pH is to enhance iodine removal (retention in sump water). A more neutral pH would retain less than the assumed amount of iodine. The other distracters are either incorrect chemical responses to a drop in pH or a response not of concern.
A.
Incorrect:
Plausible:
B.
Correct:
C.
Incorrect:
Plausible:
D.
Incorrect:
Plausible:
Level: SRO KA: SYS 027 G2.1.32 (3.413.8)
Lesson Plan Objective: OP-MC-CNT-NF Obj. 18 Source: NEW Level of knowledge: Memory Author: JHZ Page 3 of 49 RESTRICTED ACCESS 10/2112003
QUESTION # 4 MCGUIRE NUCLEAR STATION Page 4 of 49
References:
- 1. Lesson Plan OP-MC-CNT-NF page 67
- 2. Tech Spec Basis page B3.6.12-8 RESTRICTED ACCESS SRO EXAM 10/21/2003
QUESTION # 5 MCGUIRE NUCLEAR STATION Page 5 of 49 RESTRICTED ACCESS SRO EXAM 1012 1/2003
QWSTION # 6 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 1080 Answer: C 1 Pt(s)
Given the following events and conditions on Unit 1 :
Mode 3 in preparation for a reactor startup Reactor trip breakers are closed and shutdown banks withdrawn I&E is replacing a failed Containment Pressure Channel II transmitter.
The associated bistables are in their Technical Specification required position.
A loss of lEKVA occurs.
Which one of the following statements correctly describes a concern requiring prompt operator attention?
A.
Placing control rods in manual B.
Placing CF Regulating Valves in manual.
C.
Terminating inadvertent Safety Injection.
D.
Terminating inadvertent Containment Spray.
Page 6 of 49 Distracter Analysis: The key is realizing the failed instrument channel would have one SI bistable tripped by Tech Specs and the redundant channel trips on the loss of the instrument bus, resulting in an inadvertent SI.
A.
Incorrect: The reactor is already tripped.
Plausible: This is an immediate action per the Abnormal Procedure for loss of instrument bus, but the SRO is expected to prioritize concurrent procedures, and apply the appropriate one (reactor trip procedure)
Incorrect: Already have FW Isolation Plausible:. Immediate action per the AP (see above)
Incorrect: Containment Spray would not initiate Plausible. If the Operator thought the Tech Spec required position was tripped and thought the failed position of the bistable was tripped.
B.
C.
Correct:
D.
Level: SRO 10CFR55.43(b)5 KA: 000057 AA2.19 Lesson Plan Objective: OP-MC-IC-IPE Obj 6 RESTRICTED ACCESS 10/21/2003
QUESTION # 7 MCGUIRE NUCLEAR STATION Page 7 of 49 Source: BANK Author: John Zelm Level of knowledge: Anaylsis
References:
- 1. Lesson Plan OP-MC-IC-EE page 37
- 2. Tech Spec 3.3.2, page 3.3.2-10 & 3.3.2-3 RESTRICTED ACCESS SRO EXAM 10/2 1/2003
QUESTION # 8 MCGUIRE NUCLEAR STATION Bank Question: 1088 Answer: C SRO EXAM 1 Pt(s)
Given the following events and conditions on Unit 1:
Unit 1 is at 100 %power.
1NV-244A (Charging Line Cont Outside Isol) fails closed.
Immediate Actions of AP/I/A/5500/12 (Loss ofLetdown or Charging) are performed.
Assume no further Operator actions are taken.
Which one (1) of the following describes when the Pressurizer would become INOPERABLE per Technical Specifications?
Reference Provided Data Book A.
Approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> due to low level.
B.
Approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> due to low level.
C.
Approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> due to high level.
D.
Approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> due to high level.
______-_11___1_______--1--------1-1--1-------------------------------------
Analysis: WhenlNV-244 closes and letdown is isolated, 1NV-238 will throttle down to its minimum flow limit of 32 gpm. Assuming 12 gpm seal return flow that leaves a net positive flow of 20 gpm into the NC System.
Per DATA book curve 7.38,55% level = 8000 gals. 92% level = 12700 12700-8000 = 4700 gals.
4700 gals/20 gpm = 235 minutes (approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) until Reactor 4700 galdl2 gpm = 392 minutes (approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />) until Reactor gals.
trip trip Page 8 of 49 RESTRICTED ACCESS 10/2 1/2003
QUESTION # 9 MCGUIRE NUCLEAR STATION SRO EXAM If the examinee incorrectly assumes level will decrease to 17 YO (3000 gals per the curve), 8000-3000 = 5000 gals, 5000gals/20gpm = 250 minutes (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) 5000gaIs/lZgpm = 417 minutes (7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Distracter Analysis:
A.
Incorrect:. Level will increase not decrease.
Plausible: If examinee thinks there is a net negative charging flow imbalance of 20 gpm.
B.
Incorrect:. Level will increase not decrease.
Plausible: If examinee thinks there is a net negative charging flow imbalance of 12 gpm.
C.
Correct:
D.
Incorrect:. Level will increase at a rate of 20 gpm.
Plausible: If examinee thinks charging flow imbalance of 12 gpm.
Level: SRO KA: 000022 AA2.04 (2.9/3.8)
Lesson Plan Objective: OP-MC-PS-ILE Obj 7 & 12 Source: NEW Level of knowledge: Analysis
References:
- 1. Lesson Plan OP-MC-PS-ILE page 17
- 2. Tech Spec 3.4.9, Pressurizer Page 9 of 49 RESTRICTED ACCESS 10/21/2003
QUESTION I# 10 MCGUIRE NUCLEAR STATION Bank Question: 1006.1 Answer: D SRO EXAM 1 Pt(s)
An NLO has been dispatched to discharge the Ventilation Unit Condensate Drain Tank (WCDT) to the Floor Drain Tank (FDT). As the discharge is being established, the IEMF-44 flow meter ruptures and 1EMF-44 LOSS OF SAMPLE FLOW annunciator alarms.
Which one of the following describes the reason for this incident?
A.
B.
Both Unit 1 W C D T pumps were simultaneously started.
1 WL-359 ( WCDTPuinp Recirc Throttle) was opened too far and too much flow was initiated.
Radwaste Chemistry failed to open 1WM-222 (VUCDT to RC Disch Hdr).
1WL-359 was not throttled prior to VUCDT pump start.
C.
D.
Page 10 of 49 Distracter Analysis:
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
Plausible D.
Correct:.
Level: SRO KA: 073 G 2.1.32 (3.4/3.8)
Lesson Plan Objective: OP-MC-WE-RLR Obj. 5 Source: BANK Level of knowledge: Memory
References:
- 1. OP-MC-WE-RLR page 17
- 2. OP/l/A/6500/01A page 16 RESTRICTED ACCESS 10/21/2003
QUESTION # 11 MCGUIRE NUCLEAR STATION SRO EXAM Bank Ouestion: 1084 Answer: B
/ /
1 Pt(s)
Given the following events and conditions on Unit 1:
Unit 1 has experienced a large break LOCA.
FWST level is 178and decreasing.
Subcooling is -5 degrees.
ng statements in correctly describes the required above conditions?
Reference Provided ECA 1.1 and Enclosures I & 4 Cross tie Unit 2 and Unit 1 FWST to extend injection time.
Stop one NV and one NI pump to extend FWST inventory.
an NC pump to provide forced cooling.
D.
Start the 1A ND pump and reduce SI flow to 390 gpm to match SI flow to decay heat load.
Page 11 of 49 Distracter Analysis:
A.
Incorrect:
Plausible B.
Correct.
C.
Incorrect:
Plausible:.
D.
Incorrect:
Plausible:
Level: SRO 10CFR55.43@)5 RESTRICTED ACCESS 10/2 1/2003
QUESTION # 12 MCGUIRE NUCLEAR STATION SRO EXAM KA: W E 11 EA2.2 (3.414.2 )
Lesson Plan Objective: OP-MC-EP-E-1 Obj. 3 Source: BANK Level of knowledge: Analysis
References:
- 1.
- 2.
Page 12 of 49 RESTRICTED ACCESS 10/2 112003
QUESTION # 13 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 1082 Answer: D Given the following events and conditions on Unit 1 :
1 Pt(s)
Large break LOCA inside containment with fuel damage Currently the crew is implementing E-1 (Loss ofReactor or Secondaiy Coolant)
Hydrogen Analyzer concentration reading is 1% and increasing EMF readings are as follows:
9 9
IEMF-51A (Reactor Building Activity) 25 R/hr 1EMF-51B (Reactor Building Activity) 37 R/hr Which one of the following statements describes the correct instrument used to determineprocedure, and the correct mitigating strategy to address the above conditions?
nr*
Reference Provided EP/l/A/5000/F-Opage 9 A.
Hydrogen Analyzer EP/l/A/5000/FR-Z.4 (Response to High Containment Hydrogen)
Place Hydrogen recombiners in service at 4%
B.
Hydrogen Analyzer EP/l/A/5000/FR-Z.4 (Response to High Containment Hydrogen)
Obtain station management recommendation to reduce hydrogen concentration by feed and bleed.
C.
IEMF-51A (Reactor Building Activity)
EP/l/A/5000/FR-Z.3 (Response to High Containment Radiation Levels)
Ensure containment isolation Place VE in service D.
1EMF-51B (Reactor Building Activity)
EP/l/A/5000/FR-Z.3 (Response to High Containment Radiation Levels)
Ensure containment isolation Place VE in service
_1______111__11______---1---1---1-----1---------------------
Distracter Analysis:
A.
Incorrect:
Plausible:
Page 13 of 49 RESTFUCTED ACCESS 10/21/2003
QUESTION # 14 MCGUIRE NUCLEAR STATION Page14of49 B.
Incorrect:
C.
Incorrect:
Plausible:
D.
Correct Plausible:
Level: SRO 10CFR55.43(b)4 KA: AEPE W16 G 2.4.6 (3.1/4.0)
Lesson Plan Objective: OP-MC-EP-FRZ Obj. 3 Source: NEW Author: CWS Level of knowledge: Memory
References:
- 1. OP-MC-EP-FRZ pages 53 & 55
- 2. EP/l/N500O/F-O page 9
- 3. EP/l/A/5000/FR-Z.3 RESTRICTED ACCESS SRO EXAM 10/21/2003
QUESTION # 15 MCGUIRE NUCLEAR STATION SRO EXAM Bunk Question: I086 Answer: A 1 Pt(s)
Unit 2 is at 100% power when 2A NC Pump # 1 seal leak-off rapidly increases to 6 gpm. Unit 2 has entered AP/2/A/5500/08 (Malfunction ofNC Pump).
Which one of the following correctly describes the concern with this condition and basis for Enclosure 1 (NC Pump Post Trip Actions) actions?
A.
High #1 seal leak-off could lead to a seal LOCA, closing the individual seal return within 5 minutes of securing the NC Pump will control the transient prior to overheating the seals.
High #1 seal leak-off could lead to a seal LOCA, waiting longer than five minutes to close the seal return after securing the NC Pump allows the NC Pump to coast to a stop.
High #1 seal leak-off could lead to excessive #2 seal DP, closing the individual seal return within 5 minutes of securing the NC Pump will control transient prior to overheating the seals.
High #1 seal leak-off could lead to excessive #2 seal DP, waiting longer than five minutes to close the seal return after securing the NC Pump allows the NC Pump to coast to a stop B.
C.
D.
__________1_11___________________I______-_-----------------------
Distracter Analysis:
A, Correct:
B.
Incorrect:
Plausible:
C.
Incorrect:.
Plausible:
D.
Incorrect:.
Plausible:
Level: SRO KA: SYS 003 A2.01 (3.5/3.9)
Lesson Plan Objective: OP-MC-PS-NCP Obj 12 Source: New Level of knowledge: memory Page 15 of49 RESTRICTED ACCESS 10/21/2003
QUESTION # 16 MCGUIRE NUCLEAR STATION Page 16 of 49
References:
- 1. Lesson Plan OP-MC-PS-NCP page 27.
- 2. AP/08, Malhnction of NC Pump, Enclosure 1.
- 3. AP/08 Basis Document, Page 27.
RESTRICTED ACCESS SRO EXAM 10/21/2003
QUESTION # 17 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 1077 Answer: E Unit One was operating at 100% power when a LOCA occurred. Given the following events and conditions:
1 Pt(s)
STA determines RED Path for FR-P.l (Response to Imminent Pressurized Thermal Shock Condition) is valid FR-P.l is entered from FR-Z.1 (Response io High Containment Pressure)
Reactor Coolant (NC) pressure is 350 psig and slowly decreasing Which one of the following statements correctly describes the procedural guidance for performing an NC system soak?
A.
Do not cooldown NC System until temperature has been stable for 60 minutes and raise NC pressure to within the limits of the Post-Soak Limit Curve.
Do not cooldown NC System until temperature has been stable for 60 minutes and do not raise NC pressure Cooldown to within the limits of the PostSoak Cooldowu Limit Curve within 30 minutes and do not raise pressure.
Cooldowu to within the limits of the Post-Soak Cooldowu Limit curve within 30 minutes and raise pressure to within the limits of the Post-Soak Cooldown Limit Curve.
B.
C.
D.
______________________I_________________---------------_-------_-----
Distracter Analysis: The key to this question is to realize the basis for the soak step is to minimize additional stresses (no cooldown for 60 min and no pressure increases).
A.
Incorrect:
Plausible:
B.
Correct:.
C.
Incorrect:
Plausible:
D.
Incorrect:
Plausible:
Level: SRO 10CFR55.43(b)5 2353X KA: EAFE 00001 1 ES 2.14 (3.6*/4.0)
Lesson Plan Objective: OP-MC-EP-FRF Obj. 4 Page 17 of 49 RESTRICTED ACCESS 10/2 112003
QUESTION # 18 MCGUIRE NUCLEAR STATION SRO EXAM Source: NEW Author: CWS Level of knowledge: Comprehension
References:
- 1. OP-MC-EP-FRP page 43
- 2. EP/I/A/5000/FR-P.l page 28 Page 18 of 49 RESTRICTED ACCESS 10/2 1/2003
QUESTION # 19 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 1079 Answer: D Given the following events and conditions on Unit 2:
1 Pt(s)
Unit 2 is at 100% power.
The following events all OCCUT October 1,2003 At 0800, Power Range Detector N41 was removed from service to replace a relay associated with the High Flux trip function. The channel was returned to service at 0900.
At 0915, Power Range Detector N42 was removed from service to replace a relay associated with the High Flux trip function. The channel was returned to service at 1015.
At 1500, an I&E Supervisor notifies the Control Room SRO that the relays installed earlier in N41 and N42 were the incorrect relays and the High Flux trip function associated with those channels will not function as designed.
Which one of the following statements correctly describes required Technical Specification actions based on the above conditions?
Reference Provided Tech Spec 3.3.1 and Table 3.3.1-1 A.
Place INOPERABLE channels in tripped condition AND reduce THERMAL POWER to 5 75% RTP by 0300 October 2,2003.
Place one INOPERABLE channel in tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND replace inoperable relay within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Be in MODE 3 by 0300 on October 2,2003.
Return at least one channel to service by 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> or commence a shutdown to place the unit in Mode 3 by 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />.
B.
C.
D.
Page 19 of 49 Distracter Analysis:
A.
Incorrect:
Plausible:
B.
Incorrect.
C.
Incorrect:
Plausible:
D.
Correct:
Plausible:
RESTRICTED ACCESS 10/21/2003
QUESTION # 20 MCGUIRE NUCLEAR STATION SRO EXAM Level: SRO 10CFR55.43@)2 KA: G2.1.12 Lesson Plan Objective: OP-MC-ADM-TS Objs. 5 & 6 Source: BANK Level of knowledge: Analysis
References:
- 2. Tech Spec Table 3.3.1-1 Page20of49 RESTRICTED ACCESS 10/2 112003
QUESTION # 21 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 1089 Answer: C Unit 2 was operating at 100% power when a small LOCA occurred Given the following events and conditions:
1 Pt(s)
The crew has entered EP/1/A/50OO/E-O (Reactor Trip or Safety Injection)
Containment pressure reac c &. 5 ed psig and increasing.
What action (if any) should the crew take regarding the NCPs?
A.
Secure all NCPs.
B.
C.
D.
The inadequate core cooling monitor indicates -10 degrees subcooling.
All NI and NV pumps have malfunctioned and will not start.
Secure 3 NCPs and leave 1 running.
No action, the NCPs must continue to run.
NCPs must continue to run, unless NCP HI Vibration Alarm is received.
_____________11___11_-I----I--------------------------------------------
Distracter Analysis:
A.
Incorrect:
B.
Incorrect:.
C.
Correct:
D.
Incorrect:
Plausible:
Level: SRO 10CFR55.43(b)5 KA: 2.4.49 (4.014.0)
Lesson Plan Objective: OP-MC-EP-INTRO Obj 18 OP-MC-ADM-OMP Obj 8 Source: BANK Catawba 2003 NRC exam Level of knowledge: Memory
References:
- 1. Lesson Plan OP-MC-EP-INTRO page 59
- 2. OMP 4-3, Use of Abnormal and Emergency Procedures, page 7 Page 21 of 49 RESTRICTED ACCESS 1012 112003
QUESTION # 22 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 210.IA Answer: D Page 22 of 49 Given the following conditions at 0200:
Wind direction = 130" Wind speed = 8 MPH Containment radiation levels 1EMF-51A=810R/hr 1EMF-SIB = 815 R/hr Which one of the initial protective action recommendation is correct in accordance with RP/O/N5700/04 (General Emergency).
References Provided RP/O/M5700/04 A.
No protective action recommendation is required, continue assessment.
B.
Evacuate zones: L,B,M,C,N,A,D,O,~E,F,G,H,J Shelter zones: I,K,P,Q,S C.
Evacuate zones: L,B,M,C,N,A,D,O,R Shelter zones: E,F,G,H,I,J,K,P,Q,S D.
Evacuatezones: L,B,M,C,O,N,RA Shelter zones: D,E,F,G,H,I,J,K,P,Q,S Distracter Analysis:
A.
Incorrect:
Plausible:
B.
Incorrect:
C.
Incorrect:
Plausible:
D.
Correct answer RESTRICTED ACCESS 10/2 1/2003
QUESTION # 23 MCGUIRE NUCLEAR STATION Page 23 of 49 Level: SRO 10CFR55,43(b)5 KA: G 2.4.44 ( 2.U4.0)
Source: Bank Lesson Plan Objective: OP-MC-EP-EMP Obj. 11
References:
RP/O/A/5700/004 Enclosure 4.2 RESTRICTED ACCESS SRO EXAM 10/21/2003
QUESTION # 24 MCGUIRE NUCLEAR STATION SRO EXAM Bank Ouestion: 264.1 Answer: D 1 Pt(s)
Unit 2 was operating at 60% power when an ATWS event occurs. Two (2) of the three (3) pressurizer safetyrelief valves fail to actuate. Reactor Coolant pressure transient peaks at 2740 psig.
Which one of the following describes the safety limit value, and allowable action time applicable to this transient?
A.
2485 psig 15 minutes B.
2735 psig 15 minutes C.
2485 psig I 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D.
2735 psig I 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Distracter Analysis:
A.
B.
__-_1______1___1___1_------------------1----------
Incorrect: safety limit is 2735 psig, allowable action time is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Plausible: psychometric balance Incorrect: allowable action time is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Plausible: the safety limit is correct and the allowable action time is correct for modes 3-6 Incorrect: safety limit is 2735 psig Plausible: allowable action time is correct C.
D.
Correct Answer:
Level: SRO IOCFR55.43(b)2 Source: BANK Author: BCH Objective: OP-MC-IC-IPE Obj. 14
Reference:
Tech Spec 2.2 OP-MC-IC-IPE pagel9 KA: 2.2.22 (3.4/4.1)
Page 24 of 49 RESTRICTED ACCESS 10/21/2003
QUESTION # 25 MCGUIRE NUCLEAR STATION SRO EXAM Bank Ouestion: 1087 Answer: B 1 Pt(s)
Unit 1 is in Mode 3. In preparation for unit start up, maintenance tests the lift settings of 20% of the MSSVs as required by Tech Specs. In each case, maintenance adjusts the lift setting as close to the desired lift setpoint as possible. The following are the test results:
1SV-20 lifts at 1203 psig initially, maintenance adjusts lift setting to 1 172 psig.
1SV-15 lifts at 1215 psig initially, maintenance adjusts lift setting to 1190 psig.
ISV-10 lifts at 1170 psig initially, maintenance adjusts lift setting to 1 190 psig.
1SV-5 lifts at 1225 psig initially, maintenance adjusts lift setting to 1215 psig.
Based on the test results, which one of the following statements is correct?
A.
B.
C.
D.
Reference Provided Tech Spec 3.7.1 Unit start up can continue provided Rated Thermal Power is maintained below 58%.
Unit start up can continue provided Power Range set points are reduced to < 58 % within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and RTP can not exceed 58%.
Unit start up into MODE 2 is not allowed and Power Range set points must be reduced to < 58 % within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Unit start up into MODE 2 is not allowed and Power Range set points must be reduced to < 39 %.within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Distracter Analysis:
A.
Incorrect: -.
B.
Correct Plausible:
Page 25 of 49 RESTRICTED ACCESS 10/2 1/2003
QUESTION # 26 MCGUIRE NUCLEAR STATION Page 26 of 49 C.
Incorrect: -.
Plausible: -
D.
Incorrect: -
Plausible: -
Level: SRO KA: 2.2.21 (2.3/3.5)
Lesson Plan Objective: OP-MC-ADM-TS Obj 8 OP-MC-STM-MS Obj 13 Source: New-Level of knowledge: Analysis
References:
- 2. Tech Spec 3.0.4, page 3.0-1 RESTRICTED ACCESS SRO EXAM 10/2 112003
QUESTION # 27 MCGUIRE NUCLEAR STATION SRO EXAM Bunk Question: 495.1 Answer: B 1 Pt(s)
Unit 1 is in Mode 6. Given the following alarms:
Which one of the following describes the correct operator response?
A.
B.
C.
D.
1EMF-17 (Spent. Fuel Building Bridge) Trip 2 1EMF-36 (Unit Vent High Gas Radiation) Trip 1 Implement AP/l/A/5500/41 (Case ZZ Loss of Spent Fuel Level).
Implement APll/A/5500/25 (Spent Fuel Damage).
Implement AP/l/A/5500/41 (Case ZLoss of Spent Fuel Cooling).
Direct Radiation Protection to survey the Spent Fuel Pool area to verify the alarms.
Page 27 of 49 RESTRICTED ACCESS 10/2 1/2003
QUESTION # 28 MCGUIRE NUCLEAR STATION SRO EXAM Distracter Analysis:
A.
Incorrect:
Plausible:
B.
Correct: answer C.
Incorrect:
Plausible:
D.
Incorrect Plausible:
Level: SRO 10CFR55.43(b)5 KA; EAPE 061 AA2.01 (333.7)
Lesson Plan Objective: OP-MC-AP-25 Obj. 1 Source: BANK Level of Knowledge: Memory
References:
AP/ 1 /A/5 5 00/025 Page 28 of 49 RESTRICTED ACCESS 1 012 112003
QUESTION d 29 MCGUIRE NUCLEAR STATION Bank Question: 9 79.1 Answer: D SRO EXAM 1 Pt(s)
Unit 1 is at 100% RTP when:
The valve positioner for condenser dump valve 1SB-12 fails.
Control room indication shows the valve OPEN.
Control Rods Bank D is parked at 216 steps.
Which one of the following actions correctly describes plant response and the FIRST direction from the SRO to CLOSE the open condenser dump valve?
A.
Rods will withdraw and the SRO should dispatch an NLO to manually close the condenser dump isolation valve.
No rod movement will occur and the SRO should instruct RO to depress the CLOSE pushbutton on the condenser dump valve control room switch.
Rods will withdraw and the SRO should instruct IAE to energize the P-12 solenoids to close the condenser dump valve.
No rod movement and the SRO should instruct the RO to select OFF RESET on the STEAM DUMP INTLK BYPASS switches.
B.
C.
D.
Distracter Analysis:
A.
Incorrect:. This is only done if the OFF RESET does not work B.
Incorrect:. There are no pushbuttons for these valves C.
Incorrect:
Plausible:
D.
Correct:. This is the first action of the RNO of the AP..
Level: SRO IOCFR55.43@)5 KA: SYS 039 A2.04 (3.413.7)
Lesson Plan Objective: OP-MC-STM-ISE Obj. 4 Source: MODIFIED Level of knowledge: Comprehension Page 29 of 49 RESTRICTED ACCESS 1 012 112003
QUESTION # 30 MCGUIRE NUCLEAR STATION SRO EXAM
References:
- 1. OP-MC-STM-DE page 55
- 2. AP/l/A/5500/01 Steam Leak page 5 Page 30 of49 RESTRICTED ACCESS 10/21/2003
QUESTION # 3 1 MCGUIRE NUCLEAR STATION SRO EXAM Page 3 1 of 49 RESTRICTED ACCESS 1012 1/2003
QUESTION # 32 MCGUIRE NUCLEAR STATION SRO EXAM Bank Ouestion: 121.1 Answer: C 1 Pt(s)
An operator has been working as listed below:
10/15/2003 1900 Starts Shift Turnover in control room 1930 Assumes shift duties 10/16/2003 0730 0800 Starts NRC requalification exam 1130 Completes NRC requalification exam 1900 Starts shift turnover 1930 Assumes relief shift duties 0730 Relieved of duties in control room Departs site Relieved of duties in control room Departs site for home and rest What action (if any) must the operator take to comply with Tech Spec 5.2.2 regarding limits on overtime hours?
Reference Provided Tech Spec 5.2.2 A.
B.
No action required by the operator Notify the OSM and obtain approval prior to assuming the watch at 1900 on 10/16.
C.
Submit Request for Work Hours Extension Form to be approved by the Station ManagerlDesignee prior to 1900 on 10/16.
D.
Submit Request for Work Hours Extension Form to be approved by the Station ManagerlDesignee prior to 0330 on 10/17.
______________________l___l_____
Distracter Analysis:
A.
Incorrect:
B.
Incorrect:.
Page 32 of 49 RESTRICTED ACCESS 10/2 1/2003
QUESTION # 33 MCGUIRE NUCLEAR STATION SRO EXAM C.
Correct:
Plausible:
D.
Incorrect:
Plausible:
Level: SRO 10CFR55.43(b)2 KA: 2.1.5 (2.3/3.4)
Lesson Plan Objective: OP-MC-ADM-DE, Obj 9 Source: BANK Level of knowledge: Memory
References:
- 1. Tech Spec 5.2.2, Unit Staff
- 2. NSD-200, Appendix A, Request for Work Hours Extension Page 33 of 49 RESTRICTED ACCESS 10/21/2003
QUESTION # 34 MCGUIRE NUCLEAR STATION SRO EXAM Bank Ouestion: 1076 Answer: B 1 Pt(s)
Given the following events and conditions on Unit 1:
FWST Channel 4 level transmitter was discovered frozen at 0600.
Technical Specification actions for FWST Channel 4 have not been initiated.
At 0630 a LOCA occurs At 0630 a loss of instnunent buss IEKVA occurs and results in FWST Channel 1 low level bistable fails to the non tripped condition.
Which one of the following statements correctly describes the required operator response concerning the ND System swap over to the containment sump?
A.
Verify auto swap over occurs as designed when FWST Channel 2 level gets to 180 inches.
Manually swap ND pump suction to the containment sump per EP/l/A/5000/ES 1.3 (Transfer to Cold Leg Recirc) when the FWST Channel 2 gets to 180 inches.
Immediately (after 1 minute) reset SI and Sequencers and stop ND pumps.
Select SS Latched and then verify auto swap over of ND pump suction per EP/l/A/5000/ES 1.3 (Transfer to ColdLeg Recirc) when FWST level Channel 2 gets to 180 inches.
B.
C.
D.
Page 34 of 49 Distracter Analysis: The key to this question is realizing that FWST Channels 1,2 and 4 provide inputs to the autoswap feature of the ND sump valves. This feature is a 2/3 logic. With channel 4 frozen it will not perform its desired function. With Channel 1 not tripped no automatic swapover will occur. Note: because of mods over the years, there is no Channel 3.
A.
Incorrect:
B.
Correct:.
Plausible C.
Incorrect:
Plausible, D.
Incorrect:
Plausible, if channel 1 bistable was not picked-up and Operator thought SS Latched would help RESTRICTED ACCESS 10/2 1 /2003
QUESTION # 35 MCGUIRE NUCLEAR STATION Page 35 of 49 Level: SRO 10CFR55.43(b)5 KA: SYS 013 A2.04 (3.6/4.2)
Lesson Plan Objective: OP-MC-FH-FW Obj. 3 OP-MC-PS-ND Obj. 7 Source: NEW Level of knowledge: Comprehensive Author: CWS
References:
- 1. OP-MC-PS-ND pages 29,31 and 65
- 2. OP-MC-FH-FW pages 35 and 65 RESTRICTED ACCESS SRO EXAM 10/2 1 /2003
QUESTION # 36 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 1085 Answer: B 1 Pt(s)
You are the Control Room SRO. At 0200 you are notified by RP that Criticality Radiation Monitor IEMF-17 (Unit 1 Spent Fuel Pool Radiation Monitor) is inoperable.
Which one of the following correctly describes the actions required per SLC 16.7.6 (Radiation Monitoring for Plant Operation)?
A.
B.
Immediately ensure Unit 1 VF system is in the Filtration mode.
Notify RP to immediately provide a portable continuous monitor with the same Alarm Setpoint in the Unit 1 SFP area.
Ensure Unit 1 VF system is in the Filtration mode before 0300.
Notify RP to provide a portable continuous monitor with the same Alarm Setpoint in the Unit 1 SFP area before 0300.
C.
D.
Page 36 of 49 Distracter Analysis:
A.
Incorrect:
Plausible:.
B.
Correct:
C.
Incorrect:.
Plausible:
D.
Incorrect:.
Plausible:
Level: SRO 10CFR55.43@)4 KA: 2.3.3 (1.U2.9)
Lesson Plan Objective: OP-MC-WE-EMF Obj 10 Source: New Level of knowledge: memory
References:
- 1. SLC 16.9.7 Radiation Monitoring for Plant Operation
- 2.
RESTRICTED ACCESS 10/2 1/2003
QUESTION # 37 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 871.2 Answer: D Unit 1 has implemented EP/l/A/5000/ES-0.3 (natural Circulation Cooldown with Steam Void in Vessel) when a YELLOW path occurs on Reactor Coolant Inventory due to RVLIS Upper Range level indication 400%.
Which one of the following statements correctly describes the proper procedure flowpath?
1 Pt(s)
A.
B.
C.
D.
Transition to EP/l/A/5000/FR-I.3 (Response to Voids in the Reactor Vessel) because EOP usage requires transitioning from an ES procedure for a YELLOW path if there are no other higher priority critical safety functions.
Transition into EP/l/A/5000/FR-I.3 (Response to Voids in the Reactor Vessel) in order to vent the reactor vessel void through the head vent and collapse the void to allow the cooldown to continue.
Do not implement EP/l/A/SOOO/FR-I.3 (Response to Voids in the Reactor Vessel) because this procedure requires starting one NCP, which cannot he done with a void in the reactor vessel due to the potential for gas binding.
Do not implement EP/l/A/5000/FR-I.3 (Response to Voids in the Reactor Vessel) because this would cause a loss of RCS inventory, as the reactor coolant would flash to steam when the reactor vessel head vent was opened.
A.
B.
C.
D.
Page 37 of 49 Incorrect: EOP usage allows but does not require transitioning to FR procedures.
Plausible: If candidate is unfamiliar with the EOP usage rules Incorrect: Although this is a true statement for FR-1.3, it does not apply to the case above when conducting a cooldown in ES-0.3.
Plausible: This is the purpose of FR-1.3.
Incorrect: An NCP can be started with a void in the reactor vessel and will be started in FR-1.3 if the attempt to collapse the void by repressurizing the system fails.
Plausible: If the candidate is concerned that starting the NCP will destroy the pump.
Correct: ES-0.3 maintains a void under controlled conditions. FR-1.3 is prohibited in ES-0.3. If the head were vented, the steam void RESTRICTED ACCESS 10/21/2003
QUESTION # 38 Page 38 of 49 MCGUIRE NUCLEAR STATION SRO EXAM would not be eliminated. As pressure is decreased, water would flash to steam to replace the steam being vented. Void size would remain essentially the same and the net is a loss of system inventory.
KA: W/E 10 EA2.1 (3.213.9)
Lesson Plan Objective: OP-MC-EP-FRI Obj. 4 Source: BANK Level of knowledge: memory
References:
- 1. OP-MC-EP-EO page 195
- 2. OP-MC-EP-FRI pages 13 & 53
- 3. EP/l/A/5000/FR-L3 page 2 RESTRICTED ACCESS 1012 I 12003
~ _ _ _
QUESTION # 39 MCGUIRE NUCLEAR STATION Page 39 of 49 RESTRICTED ACCESS SRO EXAM 1012112003
QUESTION # 40 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 999.1 Answer: B 1 Pt(s)
Which one of the following must the Control Room SRO ensure prior to authorizing a Liquid Waste Release from the Waster Monitor Tank (WMT)?
A.
B.
C.
A source check has been performed on EMF-44.
The required number of RC pumps is in operation.
The Recommended Release Rate is equal to the Allowable Release Rate.
The Expected CPM of EMF 44 and the EMF 44 Trip I Setpoint are less than the EMF 44 Trip 2 Setpoint D.
Page 40 of 49 Distracter Analysis:
A.
B.
Correct:
C.
D.
Incorrect:.EMF 49 is utilized Incorrect:. EMF 49 is used for WMT releases Plausible:
Incorrect: Recommended release rate must be less than allowable release rate Plausible:
Level: SRO 10CFR55.43(b)
KA: APE 000059 AA 2.0.2 (2.913.9)
Lesson Plan Objective: OP-MC-WE-FUR Obj. 3 Source: Bank, 2002 NRC Retake Exam Level of knowledge: Memory
References:
- 1. OP-MC-WE-RLR pages 11 & 13 RESTRICTED ACCESS 10/2 112003
QUESTION # 41 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 881.1 Answer: B Unit one was operating at 100% power when a total loss of onsite and offsite power occurred. Given the following events and conditions:
Systems operate normally 1 Pt(s) lEVDA is supplying normal full power loads No battery charger is available BATT EVCA UNDERVOLTAGE alarm is LIT Which one of the following statements correctly describes the SROs response to the degraded voltage?
A.
After approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, ensure via the OAC the vital battery output breaker opened automatically when bus voltage decreased to 105 volts.
Dispatch an NLO to manually open the vital battery output breaker when bus voltage falls to 105 volts.
After approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, ensure via the OAC the vital battery output breaker opened automatically when bus voltage decreased to 107 volts.
Dispatch an NLO to manually open the vital battery output breaker when bus voltage falls to 107 volts.
B.
C.
D.
____________________________I___________----------------------------------------
Distracter Analysis:
A.
Incorrect: the vital battery breaker does not automatically open Plausible: partially correct
~ the design time for sustaining loads is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Correct: below this value the battery could be damaged or components will begin to fail.
Incorrect: the battery is expected to last for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and there is no automatic trip associated with low voltage Plausible: the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> requirement for battery performance is typical of the aux batteries - voltage limit is 107 volts.
Incorrect: the vital batteries are not designed to sustain loads for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Plausible: partially correct - DC bus protection is achieved by manually opening the breaker
~ voltage limit is 107 volts.
Level: SRO 10CFR55.43(b)6 B.
C.
D.
Page 41 of 49 RESTRICTED ACCESS 10/2 1/2003
QUESTION # 42 Page 42 of 49 MCGUIRE NUCLEAR STATION KA: APE 058 AA2.02(3.3*/3.6)
Lesson Plan Objective: OP-MC-AP-15 Obj. 2 Source: Modified Level of knowledge: Comprehensive
References:
- 1. Ap-15 Background Document pages 4,40
- 2. AP/l/N5500/015 page 57 RESTRICTED ACCESS SRO EXAM 10/2 1/2003
QUESTION # 43 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 181.6 Answer: A 1 Pt(s)
Unit 1 was operating at 100% when a loss of offsite power and LOCA occurred concurrently. Both Diesel Generators fail to start. The operators implemented EPil/A/5000/E-O (Reactor Trip or Safety Injection) and then transitioned to EP/l/A/5000/ECA-O.O (Loss of All AC Power). In EP/1/A/5000/ECA-0.0 (Loss of All AC Power) the crew was attempting to start the 1A Diesel Generator.
Given the following critical safety function status indications:
Containment
~ ORANGE 0
Inventory
~ YELLOW 0
Integrity-ORANGE Subcriticality - ORANGE 0
Heatsink-RED 0
Core Cooling
~ RED Which ONE (1) of the following actions is required by EOPs?
A.
Transition to EP/l/A/SOOO/FR-C.l (Response to Inadequate Core Cooling) after exiting EP/l/A/SOOO/ECA-O.O (Loss of All AC Power).
Immediately transition to EP/l/A/SOOO/FR-C.l (Response to Inadequate Core CooIing).
Transition to EP/l/A/SOOO/FR-H.l (Response to Loss of Secondary Heat Sink) after returning to EP/l/A/SOOO/E-O (Reactor Trip or Safety Injection).
Immediately transition to EP/l/A/SOOO/FR-H.l (Response to Loss of Secondary Heat Sink).
B.
C.
D.
Distracter Analysis:
Once E-0 has been exited it is appropriate to implement CSFSTs.
However, in the case of ECA 0.0 there is no power and CSFSTs are not implemented until power is restored. Once power is restored then the crew will then return to E-0 and implement the status trees.
RESTRICTED ACCESS 1 012 112003 Page 43 of 49
QUESTION # 44 MCGUIRE NUCLEAR STATION SRO EXAM A.
Correct B.
Incorrect:
C.
Incorrect:
D.
Incorrect:
LEVEL:
SRO 10CFR55.43(b)S SOURCE:
Modified LESSON:
OP-MC-EP-INTRO OBJECTIVE:
OP-MC-EP-INTRO Obj. 3,6
REFERENCES:
OMP 4-3 Use of Abnormal and Emergency Procedures pages 15 to 18 OP-MC-EP-INTRO pages 29 & 29 KA:
EAPE WE06 EA 2.1(3.4/4.2)
Page 44 of 49 RESTRICTED ACCESS 10/2 1/2003
~
QUESTION # 45 Page 45 of 49 MCGUIRE NUCLEAR STATION RESTRICTED ACCESS SRO EXAM 1012 1/2003
QUESTION # 46 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 1078 Answer: C 1 Pt(s)
Given the following events and conditions on Unit 1:
90%RTP 1A RC pump is tagged for motor repair 1B RC pump motor breaker tripped due to overcurrent 2 minutes ago While responding to the 6.9 KV switchgear room an NLO accidentally trips open the 1C RC pump breaker Which one of the following statements describes the correct plant response and sequence of procedure implementation?
A.
An automatic turbine trip occurs on % RC pump trip logic.
AP/l/A/S500/02 (Turbine Generator Trip) and EP/l/A/SOOO/E-O (Reactor Trip or Safety Injection) will be implemented.
C-9 permissive will be lost and the unit will runback due to OTDT. AP/l/A/5500/03 (Load Rejection) and AP/l/A/SSO0/23 (Loss of Condenser Vacuum) will be implemented.
Condenser vacuum will go down until the turbine trips.
AP/l/A/5500/23 (Loss of Condenser Vacuum) and EP/l/A/500O/E-O (Reactor Trip or Safety Injection) will be implemented.
Condenser vacuum will go down until the turbine trips.
AP/l/A/SS00/23 (Loss of Condenser Vacuum) and AP/l/A/5500/02 (Turbine Generator Trip) will be implemented.
B.
C.
D.
Page 46 of 49
~~~~~~~~~
~~~~
Distracter Analysis: In this event vacuum will decrease until a turbine trip is warranted. This is 20 vacuum by the AOP. Before 20 is reached a turbine trip should occur automatically. The reactor trip if greater than P-8. If the turbine does not trip the reactor will be tripped. In either instance the crew will enter E-O.
A.
Incorrect:
Plausible:
B.
Incorrect:
C.
Correct:
Plausible.
D.
Incorrect:
Plausible:
RESTRICTED ACCESS 10/21/2003
QUESTION # 47 MCGUIRE NUCLEAR STATION SRO EXAM Level: SRO 10CFR55.43@)5 KA: SYS 078 A2.02 (2.5/2.7)
Lesson Plan Objective: OP-MC-AP-23 Obj. 2 Source: NEW Author: RDB Level of knowledge: Comprehensive
References:
- 1. AP/l/Ai5500/23 page 1
- 2. APD3 Background Document page 4 Page 47 of 49 RESTRICTED ACCESS 1012112003
QUESTION # 48 MCGUIRE NUCLEAR STATION SRO EXAM Bank Question: 1083 Answer: D 1 Pt(s)
Given the following events and conditions on Unit 1:
Unit 1 is 35% RTP.
Pressurizer Pressure Control Selector switch is in the U2 position 1NC-31B (Pressurizer PORV Isolation Valve) is closed due to 1NC-32B (Pressurizer PORV) leakage.
Channel 2 Pressurizer Pressure fails HIGH.
Pressurizer Pressure Control Selector switch is placed in the U3 position per procedure.
INC-36B fails to close when the Operator places the switch in the closed position.
Which one of the following statements correctly describes the SRO directions to the RO to isolate lNC-36B?
A.
B.
Place the Pressurizer Master to MANUAL and adjust the output to 50%.
Place the control switch for 1NC-35B (Pressurizer PORV Isolation Valve) to CLOSED.
Place the control switch for 1NC-36B (Pressurizer PORV) to OVERRIDE.
Place the control switch for 1NC-35B (Pressurizer PORV Isolation Valve) to OVERRIDE.
C.
D.
Page 48 of 49 Distracter Analysis: The key to this question is to realize the AP guidance is written assuming closing the one failed PORVs block valve. Since one block valve is already closed, the procedure guidance is incomplete, and the SRO should cue the RO to utilize the over-ride feature to get the second block valve closed.
A.
Incorrect:
Plausible B.
Incorrect:
C.
Incorrect:
Plausible:
D.
Correct:
Plausible:
Level: SRO 10CFR55.43(b)5 RESTRICTED ACCESS 10/2 1/2003
QUESTION # 49 MCGUIRE NUCLEAR STATION SRO EXAM KA: EAPE 000027 AA2.15 (3.714.0)
Lesson Plan Objective: OP-MC-PS-NC Obj. 13 Source: NEW Author: RDB Level of knowledge: Comprehensive
References:
- 1. OP-MC-PS-NC page 37
- 2. AP/l/A/5500/11 page 2 Page 49 of 49 RESTRICTED ACCESS 1012112003
r 0
1 2
J 4
5 6
7 PART 1 CODE S.S. NUMBER AT LEFT BY FILLING IN THE APPROPRIATE BOXES ACCORDING TO PART 1 CODE S S NUMBER AT LEFT BY FILLING IN THE APPROPRIATE BOXES ACCORDING TO THE EXAMPLE 1
- EXAMPLE:
A 8 ' -b D
' E '
~~
~
~
~
~~~
.. ~
ERASE COMPLETELY TO CHANGE I J PPT J ENPF J OTHER J -
~
- My signature on this form is my declaration that the responses given on this examination are entirely my own. It further declares that I am aware that I am subject to termination from the training program immediately, and in addition, will be subject to further disciplinary action up to and including discharge from the company for cheating and/or compromising this exam.
~~~~~~
~
~
(Trainee Signature)