ML050480088
| ML050480088 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 12/23/2004 |
| From: | Gosekamp M Entergy Nuclear Northeast |
| To: | Caruso J NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| BVY 04-137, TDL 04-014 | |
| Download: ML050480088 (178) | |
Text
!m i-EntergY Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
Vermont Yankee P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500 Tel802 257 5271 December 23,2004 TDL 04-0 14 BVY 04-137 Regional Administrator, Region 1 ATTN: Mr. John Caruso United States Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415
References:
(a)
License No. DPR-28 (Docket No. 50-271)
Subject:
Senior Reactor Operator Licensing Examination, Vermont Yankee, February 2005 Enclosed for your review are the examination materials to support the Vermont Yankee NRC Examination scheduled for the week of February 1,2005.
Per ES-20 1, Attachment 1, regarding examination security, I would request that the enclosed materials be withheld from public disclosure until after the examinations have been completed.
This examination has been developed in accordance with NUREG-1021 Revision 9. The written examination sample plan has changed. The JPM selections and scenarios have been modified based on discussions between yourself and Mr. Kevin Murphy during the preparation week.
For any additional assistance, please call Frank Fagan at (802) 258-4256 or myself at (802) 258-4161.
Sincerely, Entergy Nuclear Northeast - Vermont Yankee Michael E. Gosekamp Operations Training Superintendent c:
USNRC Resident Inspector - VYNPS (Attachments Withheld from Public Disclosure)
USNRC Project Manager - VYNPS (Attachments Withheld from Public Disclosure)
Document Control Desk - (Attachments Withheld from Public Disclosure)
VT Department of Public Service (Attachments Withheld from Public Disclosure)
Material Required for 2005 NRC Written Examination Question E
I loo Material Required EOP-1 EOP-3 EOP-1 OP 4114 Figure 1 T.S. 4.4.A EOP-2 ON 3152 EOP-2 EOP-4 AP 3 125 Appendix A OP 3020 flowchart with Tables A and B blacked out AP-0156 AP-3 125 Appendix A EOP-2 EOP-4 EOP-3
~
T.S Table 3.1.1 page 1 and notes 1-5 AP 3125 Appendix A Note: The following is removed from the EOPs:
EOP-1 EOP-2:
Caution Table, Table A EOP-3 Caution Table, EOP-4 Caution Table, Table A, Table S Overrides including Rad Release ovemde
MASTER EXAMINATION AND ANSWER KEY SENIOR REACTOR OPERATOR (UPGRADE) TRAINING PROGRAM Course: 2005 SROU/SROI Exam Activity Code:
Date Exam Prepared: 4 November 2004 Date Exam Taken: 31 January 2005 Prepared By Date Approved By L
W Form TDD-5.2.2 Date Rev. 8,09/00
EXAMINATION SENIOR REACTOR OPERATOR (UPGRADE) TRAINING PROGRAM Course: 2005 SROU/SROI Exam Activity Code:
Date Exam Prepared: 4 November 2004 Date Exam Taken: 31 January 2005 Exam Questions 5978 1 LOT-00-202 CRO 3j l
a 2
b 3
c 4
d 5
a 6
b 7
d 8
b 9
a 10 a
11 d
12 d
13 d
14 b
15 b
16 c
17 b
18 d
19 b
20 a
21 b
22 a
23 b
24 a
25 d
26 a
27 c
28 d
29 a
30 a
31 b
32 b
33 b
34 b
35 c
36 a
u 5930 5 5979 2 5605 5 5620 1 3707 2 5980 0 5677 2 3640 4 3541 2 5775 6 5765 3 5933 4 5920 4 5973 4 3548 3 2226 2 5921 3 3718 8 5971 1 1055 2 246 4
2991 4 5972 4 5938 3 3448 2 3563 6 5981 1 5940 4 5941 6 5943 3 5944 3 3886 5 639 2
5945 3 5922 3 LOT-00-602 LOT-00-264 LOT-0 1-262 LOT-0 1-262 LOT-00-600 LOT-00-6 12 LOT-00-274 LOT-00-604 LOT-00-60 1 LOT-00-601 LOT-00-607 LOT-00-206 LOT-00-6 10 LOT-00-607 LOT-00-607 LOT-00-6 10 LOT-00-2 1 1 LOT-00-603 LOT-00-286 LOT-00-602 LOT-00-288 LOT-00-288 LOT-00-2 17 LOT-00-600 LOT-00-611 LOT-0 1-626 LOT-00-6 10 LOT-00-276 LOT-00-206 LOT-00-209 LOT-00-211 LOT-00-2 12 LOT-02-2 15 LOT-00-621 LOT-05-2 15 CRO 2 CRO 11 CRO 17 CRO 15 CRO A3 CRO 3 CRO 3 CRO 1.m CRO 3 CRO 3 CRO 2 CRO 5,7 CRO 5, l l CRO 3 CRO2&3 CRO 4 CRO 3 CRO 4a CRO 1 CRO 5 CRO 7 CRO 14 CRO 20 CRO 3 CRO 5 CRO 3 CRO 3 CRO 2c CRO 7,8 CRO 6 CRO 3,8 CRO 13 CRO 3 CRO-3 CRO-3,4 1
1 5
1 1
3 3
1 2
2 1
1 1
4 1
3 3
1 2
1 5
1 3
2 1
5 3
1 1
1 1
1 2
2 1
3 29500UAK2.04 1 295001/2.4.50 1
295003/AA1.01 1 295004/AK3.O 1 1 295005/AK2.08 1 295006/AK3.01 0 295016/AA1.05 1 295018/AKl.Ol 0 295019/2.4.49 1
295021/AK2.02 0 295023/AA2.04 0 295024EK3.08 1 295025EK2.06 1 295026EK1.01 1 295028EK3.03 0 29503OEK1.03 1 29503 U2.4.18 0
295037EK2.04 1 29503U2.4.47 1
600000/AK3.04 0 295002/AK2.11 1 295010/AK3.02 0 295012/AA1.01 0 295013/AK3.01 1 295013/AA2.02 0 295032EK3.01 1 295034EK1.02 1 203000/2.4.22 1
205000/2.4.45 1
206000/A2.15 1
209001/K2.02 1
21 1000/K1.07 0
212000/A4.12 1
215003/K1.02 1
215004/K1.06 1
215005/K3.06 1
37 c
5924 2 v
38 c
1360 3 39 b
5946 5 40 d
5974 3 41 d
5948 3 42 a
5985 0 43 a
5949 4 44 b
5737 1
45 b
5983 0 46 c
5925 4 47 d
5977 4 48 a
5927 1
49 b
5989 3 50 a
5950 2 51 c
3741 3 52 c
5951 2 53 c
165 4
54 b
5873 1 55 b
5928 3 56 c
5953 4 57 a
5988 2 58 c
5639 4 59 c
6002 1 60 d
3588 1 61 c
5957 3 62 d
5990 4 63 c
3839 3 64 d
5958 3 65 a
5993 2 66 b
5996 1
67 d
3596 3 68 a
5959 2 69 c
5961 4 70 b
5962 1 71 a
5965 4 72 c
5966 2 73 b
3668 1
74 b
5968 2 75 d
5969 3 76 d
5984 2 77 c
5881 6 78 d
5932 3 79 a
5992 5 80 a
5690 2 81 d
5935 4 82 d
5998 3 L
LOT-00-2 17 LOT-00-2 17 LOT-00-239 LOT-00-218 LOT-0 1-223 LOT-01-223 LOT-00-602 LOT-0 1-259 LOT-00-26 1 LOT-03-262 LOT-03-262 LOT-00-283 LOT-00-263 LOT-00-263 LOT-01-262 LOT-00-239 LOT-00-60 1 LOT-00-20 1 LOT-00-202 LOT-00-204 LOT-00-2 16 LOT-00-205 LOT-0 1-626 LOT-00-233 LOT-00-234 LOT-00-239 LOT-00-307 LOT-00-286 LOT-00-205 LOT-03-400 LOT-00-283 LOT-00-206 LOT-00-4 13 LOT-0 1-2 15 LOT-00-603 LOT-00-404 LOT-00-6 10 LOT-00-622 LOT-00-900 LOT-00-276 LOT-00-60 1 LOT-00-60 1 LOT-00-604 LOT-00-402 LOT-00-900 LOT-00-602 CRO-3,22 CRO 4 CRO 6,7 CRO 7 CRO 7 CRO 3,5 CRO 5e CRO 3 CRO 7 CRO 6 CRO 3 CRO 5 CRO 9 CRO 6,7 CRO 3 CRO 1 CRO 2c CRO 3 CRO l l c CRO 2 CRO 3,4 CRO 3 CRO 1 CRO 3 CRO A2, A5 CRO 2f CRO 5 CRO 1 CRO 7 CRO 7 CRO 9 CRO 5 CRO 3 CRO 3 CRO 1 CRO l a CRO 3 SRO 3,4 SRO 7 SRO 8 SRO 6 SRO 2,3 SRO 4,5 SRO 10 CRO-2 CRO-6,7 4
2 1
1 1
1 1
1 1
5 1
3 1
1 2
1 2
1 3
1 1
1 1
2 1
1 3
1 1
1 2
1 1
1 1
1 5
1 1
1 1
1 1
1 1
1 217000/K5.01 1
217000/A3.03 1
21 8000/A2.03 1
2 1 8000/K5.O 1 1
223002/A2.07 0
223002/K6.02 1
239002/A4.06 1
259002/A2.01 1
26 lOOO/A3.03 0
262001K1.04 1
262002/A1.02 0
262002Kl.06 0
263000K2.01 1
263000K5.01 0
264000/K5.06 1
300000/K1.05 0
400000/K3.O 1 1
201003/A2.05 0
20200 UA4.12 1
204000/A3.O 1 0
216000/K5.13 0
219000K4.03 1
223001/A1.02 0
233000/A3.02 0
234000K3.O 1 1
239001K6.04 0
245000K3.07 1
286000K4.06 0
290002K4.05 0
0/2.1.08 0
0/2.1.19 1
0/2.1.32 1
0/2.2.13 0
0/2.2.30 0
0/2.3.11 0
0/2.3.O 1 0
0/2.4.01 0
0/2.4.17 0
0/2.4.29 0
29501 8/AA2.03 1 295019/2.1.32 1
29502UAA2.06 1 295025EA2.01 0 295026/2.4.33 0
29503 U2.1.14 1
600000/AA2.13 1
83 d
u 84 b
85 d
86 d
87 a
88 c
89 c
90 a
91 d
92 d
93 c
94 d
95 a
96 a
97 c
98 b
99 b
100 a 5937 4 5999 0 5987 2 2524 4 5982 4 5994 3 3901 3 6000 2 5995 4 237 2
5956 2 5997 2 5960 3 5963 2 5964 4 5967 3 6001 2 5970 2 LOT-00-402 LOT-00-6 10 LOT-00-61 1 LOT-00-607 LOT-00-6 10 LOT-05-2 15 LOT-00-60 1 LOT-0 1-262 LOT-00-601 LOT-04-2 15 LOT-00-400 LOT-0 1-400 LOT-00-308 LOT-00-402 LOT-00-402 LOT-00-404 LOT-03-400 LOT-00-900 SRO 1 1
SRO 3 1
SRO 3 1
SRO 2,3 1
SRO 3 3
SRO 1 1
SRO 10 2
SRO 7 1
SRO 10 1
SRO 1 2
SRO 12 1
SRO 1 1
SRO 1 1
SRO 15 1
SRO 5e 1
SRO 5 1
SRO 1 1
SRO 2 1
161 Ky@q
- :E$&
%~&<*kr Question Level Totals 0
Fundamental KnowledgeMemory 4 1 1
Comprehension 2
Analysis 59 0
295010/2.4.30 0
295014/2.1.06 1
295036EA2.02 1 206000/2.4.06 1
21 1000/2.4.07 1
2 1500YA2.06 1
239002/A2.01 1
264000/A2.10 0
201002/A2.03 1
21500UA2.07 1
22600U2.2.17 0
0/2.1.13 0
012.1.04 1
0/2.2.07 1
0/2.2.20 1
012.3.02 0
0/2.4.05 0
0/2.4.3 2 1
Originator: Fagan, Frank N.
Last Revised: 12/22/2004 2:02:01 PM by Hallonquist, Nora E.
W
~~
Date:
Region:
I Start Time:
ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet FacilityNnit: Vermont Yankee Reactor Type:
G E Finish Time:
U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
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 require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO I SRO-Only / Total Examination Values 100 75 25 I
I Points Applicant's Scores I
/
Points Percent I
/ -
Applicant's Grade
- - ~ - -
W MASTER EXAMINATION AND ANSWER KEY SENIOR REACTOR OPERATOR (UPGRADE) TRAINING PROGRAM Course: 2005 SROU/SROI Exam Activity Code:
Date Exam Prepared: 4 November 2004 Date Exam Taken: 31 January 2005 Prepared By Date Approved By Date Form TDD-5.2.2 v
Rev. 8,09100
2005 SROU/SROI Ouestion No. 1 Exam Bank Question No.: 5978 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-202 Objective: CRO 3j Question Level: Comprehension Select the correct answer:
While operating at full power the plant experiences a jet pump failure.
How should the pressure regulating system respond to the transient?
- c. EPR stroke decreases and MPR stroke remains constant, MPR controlling Dressure Correct Response - Jet pump failure causes a decrease in core flow which in turn causes a reduction in power. At lower powers steam line pressue decreases. The decreased pressure is sensed by the EPR/MPR. The EPR is in control but they both lower together and the MPR never takes control.
Incorrect - Strokes of EPR/MPR decrease with decreasing pressure Incorrect - EPR setpoint controls at a lower pressure and thus stays in control
- d. MPR stroke increases and EPR stroke remains constant, MPR controlling Dressure Incorrect - Strokes decrease
References:
ON 3141; OP 0105; LOT-00-249 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 2000090501 Respond to Jet Pump Failure Knowledge of the interrelations between and the following 3.3 PARTIAL OR COMPLETE LOSS OF FORCED CORE I 13.3 I
FLOW CIRCULATION: (CFX 41.7,45.8):
Reactodturbine pressure regulating system: Plant-Specific Static Simulator Exams: None Last Revised: 12/22/2004 12:13:26 PM by Hallonquist, Nora E.
L..
2005 SROU/SROI Question No. 2 Exam Bank Question No.: 5930 Revision: 5 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-602 Objective: CRO 2 Question Level: Comprehension Select the correct answer:
The plant is at 30% power. Due to high vibrations, the "B" Reactor Recirc pump has been removed from service per OP 2110, "Reactor Recirculation System". The CRO then receives the following CRP 9-4 alarms:
MG SET "A" GEN m L D GND (4-A-3) and "A" MG Set voltage and current are fluctuating excessively.
The CRS should direct:
indications warrant a RR pump trip. OT 3 1 18 requires a scram if operating in natural circulation.
Incorrect - A scram is required if operating Incorrect - The indications warrant removing the "A" MG from service and the Rx is NOT in an instability region at 30%
Dower and in natural circulation.
trip "A" Recirc MG and monitor for reactor instability.
in natural circulation reduce "A" Recirc MG to min speed and insert control rods to exit the exclusionhuffer region.
References:
OT 3 118; ARS 4-A-3 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 2007830501 Respond to Recirc Pump Trip
W 295001 2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual (CFR 45.3)
Static Simulator Exams: None Last Revised: 12/22/2004 12: 14:09 PM by Hallonquist, Nora E.
3.3 3.3
W 2005 SROU/SROI 295003 I AA1.O1 Ouestion No. 3 Exam Bank Question No.: 5979 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-264 Objective: CRO 11 Question Level: Comprehension Select the correct answer:
Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C.
POWER: (CFR 41.7,45.6): A.C. electrical distribution svstem 3.7 3.8 The plant experiences a LOCA and all ECCS pumps and the Diesels are operable and running.
Five minutes later, an LNP occurred but 4T2 did not trip, what would be the status of the "A" DG and its A/C electrical distribution system?
DG running with its output breaker open
- d. DG tripped with its output breaker open b
Incorrect - Output breaker won't close.
Incorrect - Outrut breaker won't close.
Correct Response - Output breaker requires to see 4T2 open before it will close.
Incorrect - Distractor makes candidate think the output breaker closed (it doesn't),
tripped open and caused a D.G. trip
References:
OT 3122; OP 2142 Source: New Required Student
References:
None SRO
Reference:
None Task Associations Respond to Loss of Normal Power Static Simulator Exams: None Last Revised: 12/22/2004 12: 14:48 PM by Hallonquist, Nora E.
2005 SROU/SROI Question No. 4
. SRO Only: No Instructor Guide: LOT-01-262 Objective: CRO 17 Exam Bank Question No.: 5605 Revision: 5 Point Value: 1 Question Level: Comprehension Select the correct answer:
RHRSW Pump C is running for torus cooling. The operator notices that there is no light indication for the pump but the pump shows amp indication. The cause for the loss of indication is determined to be blown fuses at the 4KV breaker cubicle.
If not corrected and an LNP and LOCA were to occur, the C RHRSW pump breaker would:
trip and could be restarted from the control room.
L stay connected and could cause an overload if B & D Service Water (SW)
References:
USFAR 8.5.3, Table 8.5.1A Source: New Required Student
References:
None SRO
Reference:
None Task Associations Incorrect - Without control power breaker will not trir, Incorrect - Without control power breaker will not trip Incorrect - B & D SW pumps come off of Bus 3 and will remain under 3000 KW (7 day overload condition)
Correct Response - Loss of light indication from local fuses occurs from loss of control power. To trip a breaker electrically requires control power. The RHRSW pump load sheds and other equipment sequences on. The diesel has an overload rating of 3025 KW for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. With the diesel auto loaded, the pumps and RHRSW pump will cause the diesel to exceed 3025 KW.
2627390401 Respond to Loss of DC Control Power to a 4KV Bus d
Knowledge and Abilities Associations
Static Simulator Exams: None Last Revised: 12/22/2004 12:15: 15 PM by Hallonquist, Nora E.
2005 SROU/SROI Question No. 5 Exam Bank Question No.: 5620 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-262 Objective: CRO 15 Question Level: Comprehension Select the correct answer:
The plant is operating normally at 100% power, when the generator primary lockout relay energizes due to a fault in the 345 KV yard. With the 115 KV yard still energized, what is the status of the electrical distribution system 10 seconds after the lockout?
References:
UFSAR 8.4.5.1; ON 3155 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 2007020501 Respond to Loss of Normal Power 295005 AK2.08 Knowledge of the interrelations between and the following 3.2 3.3 MAIN TURBINE! TRIP: (CFR 41.7,45.8): A.C. electrical distribution Static Simulator Exams: None Last Revised: 12/22/2004 12:15:46 PM by Hallonquist, Nora E.
i/
2005 SROU/SROI 295006 Question No. 6 Exam Bank Question No.: 3707 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-600 Objective: CRO A3 Question Level: Fundamental KnowledgeMemory Select the correct answer:
AK3.01 Knowledge of the reasons for the following responses as 3.8 3.9 they apply to SCRAM: (CFR 41.5,45.6): Reactor water level response The reactor is at 100% power with FWLC in 3-element control when a manual scram is inserted.
Immediately following the scram, reactor water level will:
References:
LOT-00-2 16; EOP-1 Study Guide Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2000330501 Respond to a Reactor SCRAM Static Simulator Exams: None Last Revised: 12/22/2004 12:16:38 PM by Hallonquist, Nora E.
i/
2005 SROU/SROI Question No. 7 Exam Bank Question No.: 5980 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-612 Objective: CRO 3 Question Level: Comprehension Select the correct answer:
Given the following conditions:
RCIC is to be operated from the Alternate Shutdown Panel All transfer switches have been placed to emergency with the exception of MTS-13-1, A loss of bus DC-2 then occurs 125V DC Manual RCIC Transfer Switch (located in the RCIC Comer Room)
The RCIC System:
ONLY.
oDeration of RCIC from the Control Room can be operated from the ALT S / D panel ONLY.
Incorrect - The loss of DC-2 and failure to transfer power with MTS-13-1 leaves RCIC without Dower can be operated from the ALT S / D panel or from the control room.
Incorrect - DC2 is the normal power supply to the RCIC loads. The transfer switch disconnects DC2 and connects DC-1AS. If not transferrqd, a loss of DC2 prevents any operation.
Correct Response - DC2 is the normal power supply to the RCIC loads. The transfer switch disconnects DC2 and connects DC-1AS. If not transferred, a loss of DC2 prevents any operation.
cannot be operated from the ALT S/D panel nor from the control room.
References:
OP 3126; LOT-00-612 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 2177030101 Operate RCIC System from RCIC Alternate Shutdown Panel CP-82-1
Static Simulator Exams: None Last Revised: 12/22/2004 2:18:41 PM by Hallonquist, Nora E.
u 2005 SROU/SROI L.
- d. Isophase bus coolers, Generator hydrogen coolers Incorrect - Gen H2 coolers cooled by SW Question No. 8 Exam Bank Question No.: 5677 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-274 Objective: CRO 3 Question Level: Fundamental KnowledgeMemory Select the correct answer:
295018 The running TBCCW pump has tripped and the standby pump can not be started.
AKl.01 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: (CFR 41.8 to 41.10): Effects on componentlsystem operations If no operator action is taken, which of the following components will be effected?
I a. I Turbine lube oil coolers, Condensate I Incorrect - Lube oil coolers cooled by SW I
References:
ON 3 165; LOT-00-274 Source: New Required Student
References:
None SRO
Reference:
None Task Associations E
d 2747060401 Respond to Loss of Power to TBCCW Knowledge and Abilities Associations 3.5 3.6 U Static Simulator Exams: None Last Revised: 12/22/2004 12: 17:41 PM by Hallonquist, Nora E.
L/
2005 SROU/SROI
- d.
Only A & B air compressors have started on low air pressure Incorrect - No auto start of A & B Question No. 9 Exam Bank Question No.: 3640 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-604 Objective: CRO 1.m Question Level: Comprehension Select the correct answer:
295019 Station air compressors C and D are running in "LEAD" when a Service Air line break and LNP occurs. Following the LNP, the plant conditions are as follows:
2.4.49 Ability to perform without reference to procedures those 4.0 4.0 actions that require immediate operation of system components and controls (CFR 41.10,43.2,45.6)
Emergency Diesel Generators running and loaded SA-PCV-1, Service Air Pressure Control Valve, controlling pressure at 83 psig No operator actions have been taken Which one of the following is the status of the Air System?
L, started on low air Dressure.
References:
OT 3 122 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations
Static Simulator Exams: None Last Revised: 12/22/2004 12: 19: 14 PM by Hallonquist, Nora E.
2005 SROU/SROI u
Ouestion No. 10 Exam Bank Question No.: 3541 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-601 Objective: CRO 3 Question Level: Fundamental Knowledge/Memory Select the correct answer:
I LOSS OF SHUTDOWN COOLING: (CFR 41.7,45.8): - I The plant is in an outage with the following conditions:
Refueling is underway Shutdown cooling has been lost ON 3 156, Loss of Shutdown Cooling, has been enetered
& 4 The CRS should direct feed with and bleed Condensate Transfer through the CS system; with RCU.
CS pumps; through an open SRV Correct Response - ON 3 156 actions Incorrect - CS is not an approved system and procedurally the SRV can only be used with RHR with the reactor head installed.
Condensate and Feed using the condensate Incorrect - Condensate and feed are not an pumps; with RCU.
approved system and normally during an outage both the condensate/feed and circ.
water (needed for cooling) are removed from service Incorrect - Not an approved method with the head off.
RHR pumps; through an open SRV
References:
ON 3 156 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2000150501 Respond to a Loss of Shutdown Cooling Knowledge and Abilities Associations
I Reactor water cleanur, Static Simulator Exams: None Last Revised: 12/22/2004 1:09:41 PM by Hallonquist, Nora E.
I
u 2005 SROU/SROI
- a.
- b.
Ouestion No. 11 Exam Bank Question No.: 5775 Revision: 6 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-601 Objective: CRO 3 Question Level: Fundamental KnowledgeMemory Select the correct answer:
Lift the bundle, place the bundle in its Halt refueling. Notify SM and Ops Supt for Dermission to re-commence fuel move.
Incorrect - Not allowed by Precaution 19; OP 1101 Incorrect - Ops Supt required to restart; evacuation reauired proper location and then halt refueling.
During refueling operation a bundle being transferred from the Reactor vessel to the spent fuel pool is inadvertently dropped 1 foot, on the top of the spent fuel racks.
295023 The action(s) required in response to this event is:
AA2.04 Ability to determine and/or interpret the following as they 3.4 4.1 apply to REFUELING ACCIDENTS:(CFR 41.10,43.5, 45.13): Occurrence of fuel handling; accident L-
References:
OP 1101; ON 3153 Source: New Required Student
References:
None SRO
Reference:
None Task Associations
~~~~~~
.l 7 4
4 1...L,..
2737060101-- Respond to Automatic Actions from Local Monitors Static Simulator Exams: None Last Revised: 12/22/2004 12:20:13 PM by Hallonquist, Nora E.
2005 SROU/SROI Question No. 12 Exam Bank Question No.: 5765 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-607 Objective: CRO 2 Question Level: Comprehension Select the correct answer:
The following plant conditions exist:
'A' RHR spraying DW and torus DW pressure 6 psig and lowering slowly Torus pressue 6.5 psig and lowering slowly RHR DRYWELL PRESS HI (3-L-1) alarming When the high drywell pressure alarm clears, vacuum breakers.
isolates to prevent operation of the
- a. Drywell Spray only; Torus to Drywell i-
- b. Drywell and Torus Spray; Torus to Drywell Drywell Spray only; Reactor Building to Torus Building to Torus
References:
EOP-3 Study Guide Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations Incorrect - Both sprays isolate Incorrect - On a LOCA the Torus to Drywell Vacuum breaker would open up normally.
Incorrect - Both sprays isolate Correct Response - If primary containment goes negative air will be drawn in from the reactor building 2057220101 Startup the RHR System in the Drywell Spray Mode 295024 EK3.08 I Knowledge and Abilities Associations Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE (CFX 41.5, 45.6): Containment spray: Plant-specific 3.7 4.1
L/
Static Simulator Exams: None Last Revised: 12/22/2004 1:02:38 PM by Hallonquist, Nora E.
2005 SROU/SROI Ouestion No. 13 Exam Bank Question No.: 5933 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-206 Objective: CRO 5,7 Question Level: Comprehension Select the correct answer:
The plant was at 100% power when a steam leak occurs in the steam tunnel. The current plant conditions are:
- DW pressure is 2.0 psig and steady
- Steam tunnel temperature has just reached 212°F and is slowly increasing
- Reactor level is at a low of 120" and slowly decreasing
- Reactor pressure is at a high of 1020 psig and slowly increasing Which one of the following plant systems is currently available to control reactor pressure?
I a. I RWCU Incorrect - GP5 isolation due to 127" level I Incorrect - GP1 isolation due to 212°F Incorrect - GP1 isolation due to 212°F Correct Response - No initiation signal present and the isolation occurs at 212°F after 35 min T.D.
P 21 15; T.S. Table 3.2.1
References:
None SRO
Reference:
None Task Associations 2007400501 Control RPV Pressure Using Bypass Valves, HPCI, RCIC, SRVS, RWCU, Steam Line Drains KnowledEe and Abilities Associations REACTOR PRESSURE and the following: (CFR 41.7, 45.8): HPCI: Plant-specific Static Simulator Exams: None
Last Revised: 12/22/2004 1:22:32 PM by Hallonquist, Nora E.
2005 SROU/SROI Question No. 14 Exam Bank Question No.: 5920 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-610 Objective: CRO 5, 11 Question Level: Comprehension Select the correct answer:
Plant conditions are:
Torus temperature 200°F Core Spray A flow 3800 gpm with injection into the vessel Which one of the following is the LOWEST torus pressure at which the "A" CS pump NPSH requirement is met?
- a. IJpsig
- d. 0 psig Required Student
References:
EOP-1 Source: VY Exam Bank SRO
Reference:
None Task Associations Incorrect - Pressure too high for torus temp. A torus temp of 217°F is needed for 15 psig.
Correct Response - The intersection of 200°F and 3800 gpm occurs between 5 and 10 psig, the next highest pressure should be utilized.
Incorrect - Pressure is too low. At this flow a torus temp of 195°F or less is required.
Incorrect - Pressure is too low. At this flow a torus temp of 171°F or less is required.
2000190501 Respond to High Torus Water Temperature
u Static Simulator Exams: None Last Revised: 12/22/2004 12:22:00 PM by Hallonquist, Nora E.
following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: (CFR 41.8 to 41.10): Pump NPSH
2005 SROU/SROI 295028 EK3.03 Knowledge of the reasons for the following responses as 3.6 3.9 they apply to HIGH DRYWELL TEMPERATURE (CFR 41.5,45.6): Drywell spray operation: Mark-I&II Question No. 15 Exam Bank Question No.: 5973 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-607 Objective: CRO-3 Question Level: Fundamental Knowledge/Memory -
Select the correct answer:
A small break LOCA has occurred and DW temp is increasing. DW sprays are initiated to maintain temperature below 280°F. Any higher temperature would always:
b
References:
EOP-3 Study Guide Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2000210501 Respond to High Drywell Temperature Static Simulator Exams: None Last Revised: 12/22/2004 12:23:31 PM by Hallonquist, Nora E.
W L
- d.
2005 SROU/SROI excessive hydrodynamic loading on downcomer piping during RPV Emergency Demessurization.
Question No. 16 Exam Bank Question No.: 3548 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-607 Objective: CRO 3 Question Level: Comprehension Select the correct answer:
295030 An ATWS condition with a Group 1 isolation and SLC failure had occurred with the following current conditions :
EK1.03 Knowledge of the operational implications of the following concepts 3.8 4.1 as they apply to LOW SUPPRESSION POOL WATER LEVEL (CFR 41.8 to 41.10): Heat capacity All rods have been inserted Torus Temperature - 180°F and increasing Torus Level - 9 ft and decreasing Reactor Pressure - 860 psig and rising slowly The CRS determines an RPV-ED is required.
This RPV-ED is performed to avoid:
overpressurizing the Primary Containment during RPV Emergency Depressurization.
I Incorrect - Unrelated to SRV tailpipes Incorrect - Level instrumentation affected by drywell temp Correct Response - Highest torus temp which does not exceed PCPL-A on RPVED Incorrect - Hydrodynamic loading on downcomers not relevant to HCTL
References:
EOP 3 Study Guide Source: 2003 VY NRC Exam Required Student
References:
Reference:
None Task Associations 3440420302/03 Direct Corrective Actions to Mitigate the Consequences of an Off Normal Event Static Simulator Exams: None Last Revised: 12/22/2004 2: 16: 19 PM by Hallonquist, Nora E.
2005 SROU/SROI
- d.
To ensure MSIVs can be reopened concurrent with high main steam line radiation.
Incorrect - EOP-2, ARC/OR-5 states that MSNs should only be reopened if MSL Hi Rad signal is not present.
Ouestion No. 17 Exam Bank Question No.: 2226 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-610 Objective: CRO 2 & 3 Question -Level: Fundamental KnowledgeAIemory Select the correct answer:
Which ONE of the following is the basis for bypassing the PCIS Group 1 Low-Low Reactor Water Level Isolation logic in EOP-2, Level Power Control (implementing Appendix P)?
Water Level does not prevent a large positive reactivity insertion..This is for anticiDatinrr an RPVED.
allowed in EOP-2.
References:
EOP-2 Study Guide Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 3 101070502/0 Direct Bypassing of Group I Isolation Signals 3
1 295031 I 2.4.18 I Knowledge of specific bases for EOPs (CFR 41.10,45.13) I 2.7 I 3.6 I Static Simulator Exams: None Last Revised: 12/22/2004 12:24:25 PM by Hallonquist, Nora E.
2005 SROU/SROI 295037 Ouestion No. 18 Exam Bank Question No.: 5921 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-21 1 Objective: CRO 4 Question Level: Comprehension Select the correct answer:
EK2.04 Knowledge of the interrelations between SCRAM 4.4 4.5 CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN and the following: (CFR 41.7,45.8): SBLC system Plant conditions are as follows:
ATWS with power at 35%
MSIVs are closed CRS has directed SLC injected Determine the MINIMUM amount of time required to inject Cold Shutdown Boron Weight into the RPV if injecting at the MINIMUM operable flow rate.
I a. I20 minutes I Incorrect - HSB Dercentage I
35 = 41.4 minutes
References:
VY Tech Specs; OP 41 14; EOP-2 Source: VY Exam Bank Required Student
References:
VY Technical Specifications 4.4.A; OP 41 14 Figure 1; EOP-2 SRO
Reference:
None Task Associations 2000200501 Respond to ATWS Event(s)
Static Simulator Exams:' None Last Revised: 12/22/2004 12:29:23 PM by Hallonquist, Nora E.
2005 SROU/SROI Ouestion No. 19 Exam Bank Question No.: 3718 Revision: 8 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-603 Objective: CRO 3 Question Level: Comprehension Select the correct answer:
During 100% power operation, a sudden rise in off-gas rad levels occurs. The plant has entered ON 3 152, "Offgas High Radiation". Plant conditions are:
ERFIS is unavailable Reactor power: 1593 MWt SJAE Off Gas Rad: PRM 17-150A - 23 m/hr and increasing PRM 17-150B - 28 m/hr and increasing K-Factor (from Chemistry): 2.4 Determine the pci/sec activity and the required 150,000 ucilsec reduction is not reauired.
References:
ON 3152 Source: VY Exam Bank Required Student
References:
ON 3152 SRO
Reference:
None Task Associations 200709050 1 Respond to High Off-Gas Radiation
.-J I295038 12.4.47 I Abilitv to diagnose and recognize trends in an accurate and 13.4 13.7 I
L' timely manner utilizing the appropriate control room reference material (CFR 41.10,43.5, 45.12)
Static Simulator Exams: None Last Revised: 12/22/2004 12:30: 15 PM by Hallonquist, Nora E.
2005 SROU/SROI Ouestion No. 20 Exam Bank Question No.: 5971 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-286 Objective: CRO 4a Question Level: Fundamental Knowledge/Memory Select the correct answer:
A fire has occurred in the East Switchgear room. The fire is automatically extinguished and the fire is verified to be out. The Shift Manager directs all personnel in the Admin Building lower level and lobby area be evacuated. The reason this is done is:
atmosphere.
Room
- c. Water may enter the RCA and spread contamination.
will occur Incorrect - No automatic water deployment
- d. These areas are the assembly area for the fire brigade.
Incorrect - This is brigade assembly area but building evacuation is not done for this reason SRO
Reference:
None Task Associations 2867290401 Knowledge and Abilities Associations Respond to Pyrotronics Panel Alarms they apply to PLANT FIRE ON SITE:: Actions contained in the abnormal procedure for plant fire on site Static Simulator Exams: None Last Revised: 12/22/2004 12:30:36 PM by Hallonquist, Nora E.
2005 SROU/SROI
- d.
Question No. 21 Exam Bank Question No.: 1055 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-602 Objective: CRO 1 Question Level: Comprehension Select the correct answer.
contains no actions for these Conditions.
Incorrect - OP 2150 contains no actions for OP 2150, AOG/Air Evacuation During 100% power operations the following indications are observed:
- AOG inlet flow increases
- COND VAC LO (7-H-3) alarm is in
- Steam seal pressure is zero
\\
Given these indications, which procedure would address all three of the above conditions?
LOSS OF MAIN CONDENSER VACUUM: (CFR 41.7, 45.8): Seal steam: Plant-Specific Incorrect - The Turbine Generator OP I a loss of steam seal pressure.
References:
OT 3120; ARS 7-H-3 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2000080501 Respond to a Loss of Condenser Vacuum Knowledge and Abilities Associations
v Static Simulator Exams: None Last Revised: 12/22/2004 12:31: 10 PM by Hallonquist, Nora E.
2005 SROU/SROI 295010 Question No. 22 Exam Bank Question No.: 246 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-288 Objective: CRO 5 Question Level: Fundamental KnowledgeMemory Select the correct answer:
AK3.02 Knowledge of the reasons for the following responses as 3.4 3.4 they apply to HIGH DRYWELL PRESSURE: (CFR 41.5, 45.6): Increased drvwell coolinrr The plant has experienced a LOCA and a loss of normal power. Drywell pressure is 6 psig and steady.
An operator has placed the DRYWELL RRU PCIS TRIP MCA BYPASS SW keylock in the MCA Bypass position on CRP 9-25. This starts RRU numbers immediately for the purpose of 1 and 3; controlling primary containment pressure and temperature
- b. 2 and 4; controlling primary containment pressure and temperature
- c. 1 and 3; mixing the drywell atmosphere to prevent the formation of pockets of Hydrogen
- d. 2 and 4; mixing the drywell atmosphere to prevent the formation of pockets of Hydrogen Correct Response - 1 and 3 start immediately, helps maintain containment allow restart of RRUs 2 and 4 Incorrect - RRUs limit the average Drywell operating temperature to less than 150°F during normal oueration Incorrect - Requires use of a pushbutton to restart RRUs 2 and 4
References:
OP 21 15 Source: VY Exam Bank Required Student
References:
'None SRO
Reference:
None Task Associations 2227020401 Startup Drywell RRUS Following a LOCA
Static Simulator Exams: None Last Revised: 12/22/2004 1:21:22 PM by Hallonquist, Nora E.
L-
L,'
2005 SROU/SROI to the Group 3 signal The RRUs will trip on thermal overload.
The RRUs will continue to run indefinately since the MCALOCA Bypass is in Bypass.
The RRUs will continue to run since all fans are now in A & B run.
operation.
Correct Response -
Incorrect - will allow restart but will trip on overload Incorrect - will trip on thermal overload.
Ouestion No. 23 Exam Bank Question No.: 2991 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-288 Objective: CRO 7 Question Level: Fundamental KnowledgeMemory Select the correct answer:
The plant was operating at 100% power when the following occurred:
A small break LOCA results in DW temperature and pressure rise The CRS directs restarting all available RRUs Predict the long term operation of the RRUs.
I C.
- d.
References:
CWD b191301 sh 1415 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2227020401 Startup Drywell RRUS Following a LOCA Knowledge and Abilities Associations apply to HIGH DRYWELL TEMPERAT-:
(CFR 41.7, 45.6): Drywell ventilation system Static Simulator Exams: None Last Revised: 12/22/2004 12:33: 13 PM by Hallonquist, Nora E.
u
2005 SROU/SROI 7 2 Question No. 24 Exam Bank Question No.: 5972 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-217 Objective: CRO 14 Question Level: Comprehension Select the correct answer:
During power ascension following a short duration shutdown, a PCIS logic failure results in Group 1 Isolation. The following conditions exist as of 0100:
RCIC running in pressure control mode at 400 gpm Level control is with feedwater HPCI in standby Neither loop of RHR is currently available for torus cooling due to a combination of logic Suppression pool temp 84°F Suppression pool level 68,600 cu ft The PCIS logic failure, which is keeping the main steam lines isolated, will not be If RHR repair is prioritized, RHR should be available for torus cooling in 4 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and mechanical failures repaired for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Which of the following describes the appropriate course of action?
- b.
C.
- d.
Maintain RCIC in service. Attempt to-recover RHR and place in torus cooling.
Torus temperature will stay below the 110°F T.S. limit.
Shutdown RCIC. Attempt to recover RHR and place in torus cooling. Torus temperature will stay below the EOP entry condition.
Maintain RCIC in service. Attempt to repair the PCIS logic failure and open the MSIVs. Torus temperature will stay below the 110°F T.S. limit.
Shutdown RCIC. Attempt to repair the PCIS logic failure and open the MSIVs.
Torus temperature will stay below the EOP Correct Response - Torus cooling is required because with RCIC in operation without cooling the torus temperature will rise at 3°F per hour. Torus temperature would reach 110°F at 0940, so if torus cooling can be restored within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the 110 OF T.S. limit would not be exceeded.
Incorrect - SRV operation would result in torus temperature rising more rapidly than if RCIC were in service; additionally, the EOP entry condition is only 90°F Incorrect a At 3°F per hour heat-up rate and ten hours to open the MSIVs, would reach 114°F at 0940. Recovering torus cooling is required.
Incorrect - SRV operation would result in torus temperature rising more rapidly than if RCIC were in service; additionally, the
I entry condition.
References:
OP 2121 Source: New Required Student
References:
None SRO
Reference:
None I EOP entry condition is only 90°F.
L.
295013 Task Associations AK3.01 Knowledge of the reasons for the following responses as 3.6 3.8 they apply to HIGH SUPPRESSION POOL WATER TEMPERATURE: (CFR 41.5,45.6): Suppression pool cooling operation 2170020201 Perform RCIC Pump Operability Test Static Simulator Exams: None Last Revised: 12/22/2004 12:33:32 PM by Hallonquist, Nora E.
2005 SROU/SROI v
Question No. 25 Exam Bank Question No.: 5938 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-600 Objective: CRO 20 Question Level:' Fundamental KnowledgehIemory Select the correct answer:
Following a scram the CRS directs the CRO to maintain RPV pressure between 800 and 1000 psig using SRVs. The CRO uses repeated openings of the "A" SRV to stay within the pressure band. The CRS should direct the BOP to:
interval of 3 minutes per valve to minimize nitrogen depletion in accumulators.
- b. cycle through SRVs without any time I
I limitation.
Incorrect - Lift interval is 5 minutes per OP 2122 and no nitrogen depletion will occur since cont nitrogen is lined up Incorrect -Must limit time interval per OP 2122 Incorrect - 10 minutes exceeds allowable time interval per OP 2122 Correct Response - Per OP 2122 precaution
References:
OP 2122 Source: 2001 Fitzpatrick Exam Required Student
References:
None SRO
Reference:
None Changed from an SRO question to an RO question Task Associations 3100040502/0 Control RPV Pressure Below 1055 PSIG after a SCRAM 3
295013 AA2.02 Ability to determine andor interpret the following as they 3.2 3.5 apply to HIGH SUPPRESSION POOL WATER TEMPERATURE:(CFR 41.10,43.5,45.13): Localized heatingstratification Static Simulator Exams: None Last Revised: 12/22/2004 3:41:27 PM by Murphy, Kevin u
2005 SROU/SROI Ouestion No. 26 Exam Bank Question No.: 3448 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-61 1 Objective: CRO 3 Question Level: Comprehension Choose the correct answer:
An unisolable leak from the RWCU system is in progress. All attempts to isolate the leak have been unsuccessful, and the following plant conditions exist:
RPV pressure is 800 psig and steady RPV level is 150 inches and steady All injection systems are available with CondensateFeedwater in service All control rods are fully inserted in the core Channel 12 (RB SW 252') temperature is 175°F and steady Channel 15 (RB NW 280') temperature is 165°F and steady All other RB locations are i 103°F and steady What is the reason and required action for conducting a normal or emergency depressurization?
than one area is affected indicating a threat because two-areas have temperature above to secondary containment integrity.
Anticipating an RPV-ED is appropriate because one area is above max safe level indicating a potential threat to secondary containment in te rrri tv.
max safe with an unisolable primary system leak.
Incorrect - Two different areas are above max safe. RPV-ED is required now.
A normal cooldown using TBVs is appropriate since the condition is not widespread and the main condenser is available.
Incorrect - An unisolable primary system leak requires RPV-ED, not a cooldown.
A normal cooldown using SRVs is appropriate since the condition is not widespread and use of the SRVs will limit the sDread of the contamination.
Incorrect - An unisolable primary system leak requires RPV-ED, not a cooldown.
References:
EOP Bases Source: VY Exam Bank\\
Required Student
Reference:
Reference:
None
u 2005 SROU/SROI Ouestion No. 27 Exam Bank Question No.: 3563 Revision: 6 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-626 Objective: CRO 5 Question Level: Comprehension Select the correct answer:
A small primary system leak into secondary containment has forced entry into EOP-4 based on area temperature and water level. Reactor Buiiding HVAC has been restarted via implementation of OE 3 107 Appendix AA, Bypassing Reactor Building No Shortly thereafter, the Reactor Building Vent Rad Monitors indicate 150 mdhr.
The appropriate system and operator response is:
- a. No automatic system response from the Rx Building W A C since Appendix AA has bvuassed trius, no manual actions reauired Building HVAC since Appendix AA has and SBGTS start.
References:
OE 3107 Appendix AA; OP 2115 Source: New Required Student
References:
None SRO
Reference:
None Task Associations Incorrect - AA only bypasses Hi Drywell and Low Level Isolation, not RB HVAC or SBGT svstem Incorrect - "AA" does not bypass RB HVAC Isolation, only Hi Drywell & Low level Correct Response - Appendix AA does NOT bypass Rad Monitor Isolation.
SBGT will start and RB HVAC will trip and isolate.
Incorrect - SBGT system auto start will occur 2000 17050 1 Respond to Containment Isolations c-
EK1.02 Knowledge of the operational implications of the following concepts as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION:
fCFR 41.8 to 41.10): Radiation releases Static Simulator Exams: None Last Revised 12/22/2004 1:06:3 1 PM by Hallonquist, Nora E.
2005 SROU/SROI Question No. 28 Exam Bank Question No.: 5981 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-610 Objective: CRO 3 Question Level: Comprehension Select the correct answer:
During an ATWS, the following conditions exist:
RPV Level is 45" RPV Pressure is 850 psig Reactor Power - IRM Range 5 decreasing 45 rods not inserted Torus Temperature - 150°F "A/B" RHR operating in torus cooling as directed by EOP-3 A loss of condensate and feedwater results in lowering RPV level requiring RPV-ED.
Regarding RHR operation during and after depressurization of the RPV, which of the following describes the actions required and the reason for those actions?
remain in torus cooling to ensure the Heat Capacity Temperature Limit is not exceeded because protecting containment integrity is the priority.
Following the RPV-ED, A and B RHR will be returned to torus cooling to ensure the Heat Capacity Temperature Limit is not exceeded because protecting containment integrity becomes the priority.
During the RPV-ED, A or B RHR will be lined up for RPV injection to ensure there is not an excessive loss of RPV inventory because ensuring adequate core cooling is the Drioritv.
Following the RPV-ED, A or B RHR will be lined up for controlled RPV injection, because ensuring adequate core cooling becomes the priority.
Incorrect - RHR pumps will be placed in pull-to-lock to prevent inducing a power excursion due to rapid.injection during depressurization.
Incorrect - Steam flow no longer provides adequate core cooling, and Core Spray injects inside the core shroud, so RHR injection is required to assure adequate core cooling.
Incorrect - RHR pumps will be placed in pull-to-lock to prevent inducing a power excursion due to rapid injection during depressurization. Steam flow provides adequate core cooling.
Correct Response - Steam flow no longer provides adequate core coolng, and Core Spray injects inside the core shroud, so RHR injection is required for adequate core cooling.
References:
EOP Bases Source: New Required Student
References:
Reference:
None v
Task Associations 2000200501 Respond to ATWS Event(s) u 203000 2.4.22 Knowledge of the bases for prioritizing safet functions 3.0 4.0 during abnormal/emergency operations (CFR 43.5,45.12)
Static Simulator Exams: None Last Revised: 12/22/2004 12:34:50 PM by Hallonquist, Nora E.
u 2005 SROU/SROI 1,
damage indicated by radiation.
- c. RHR WATER CONDUC HI indicates Incorrect - Radiation does not affect Question No. 29 Exam Bank Question No.: 5940 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-276 Objective: CRO 3 Question Level: Comprehension Select the correct answer:
- d.
The plant is in cold shutdown with "B" RHR in shutdown cooling. The following annunciators have been received:
radiation release conductivity.
SERVICE WATER EFFLUENT RAD HI indicates in leakage from the normal fuel uool cooling; heat exchangers Incorrect - Fuel pool cooling is cooled by RBCCW.
RHR WATER CONDUC HI (3-L-7)
SERVICE WATER EFFLUENT RAD HI (3-F-6) 205000 Which of these annunciators should receive the highest priority and why?
2.4.45 Ability to prioritize and interpret the significance of each 3.3 3.6 annunciator or alarm (CFR 43.5,45.3,45.12)
References:
ARS 3-L-7,3-F-6 Source: 2001 Clinton 1 NRC Exam Required Student
References:
None SRO
Reference:
None Task Associations 2057090101 Operate the RHR System in the Shutdown Cooling Mode 3410340302/0 Direct Actions to Ensure Compliance with Local, State and Federal 3
Environmental Regulations
Static Simulator Exams: None Last Revised: 12/22/2004 2: 19:04 PM by Hallonquist, Nora E.
c
2005 SROU/SROI Question No. 30 Exam Bank Question No.: 5941 Revision: 6 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-206 Objective: CRO 2c Question Level: Comprehension Select the correct answer:
During a manual start of the HPCI System with HPCI flow of 150 gpm a control oil leak develops in the HPCI System causing a complete loss of control oil pressure. As a result of the control oil leak:
and the operator must manually close HPCI 25 (Min Flow Valve).
No operator action is required.
- c. HPCI Stop and Control Valve will close and HPCI 25 (Min Flow Valve) will go closed. No operator action is required.
- d. Only HPCI Stop Valve will close, HPCI 25 (Min Flow Valve) remains open and HPCI 25 must be manually closed.
Correct Response - HPCI 25 will not auto close until $00 pgm.
Incorrect - HPCI Stop and Control Valves will close, HPCI 25 will be open &
reauires manual closure.
Incorrect - HPCI 25 will be open and requires manual closure.
Incorrect - Both HPCI Stop and Control Valve will close.
References:
OP 2120 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 2060050101 Manually Initiate HPCI Knowledge and Abilities Associations 206000 A2.15 1 Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR 41.5 / 45.6):
Loss of control oil pressure: BWR-2, 3,4 3.4 3.5 4
L' Static Simulator Exams: None Last Revised: 12/22/2004 12:35:10 PM by Hallonquist, Nora E.
v 2005 SROU/SROI Question No. 3 1 Exam Bank Question No.: 5943 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-209 Objective: CRO 7, 8 Question Level: Comprehension Select the correct answer:
The plant was performing a startup when an LNP occurs. The following plant conditions exist during the LNP:
"B" D/G started and tripped on lockout Rx pressure is at 300 psig and constant Rx level reached a low of 141" and is slowly increasing DW pressure reached a high of 20 psig and is constant Fifteen (15) seconds after the LNP, what is the status of CS injection valves: CS-12A and CS-12B?
CS-12B - stroking open CS-12B - shut CS-12B - stroking open CS-12A - shut CS-12B - shut
References:
OP 2123 Source: New Required Student
References:
None SRO
Reference:
None Incorrect - Bus 3 does not have power due to D/G failure (A, C incorrect). CS-12B will remain shut.
Correct Response - Bus B does not have power due to D/G failure (A, C incorrect).
CS-12B will remain shut. CS-12A will open because accident signal (High Drywell Pressure) with a low pressure condition.
Incorrect - Bus 3 does not have power due to D/G failure (A, C incorrect). CS-12B will remain shut.
Incorrect - Valves would remain shut if Dressure were high Task Associations L.,,
2097010401 Maintain Reactor Water Level with Core Spray
209001 Static Simulator Exams: None Last Revised: 12/22/2004 12:36:50 PM by Hallonquist, Nora E.
K2.02 Knowledge of electrical power supplies to the following:
2.5 2.7 (CFR 41.7): Valve power
2005 SROU/SROI Ouestion No. 32 Exam Bank Question No.: 5944 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-21 1 Objective: CRO 6 Question Level: Fundamental KnowledgelMemory Select the correct answer:
The high pressure tap for the jet pump differential pressure indication is sensed from:
L-Incorrect - Tap is below LOT-00-2 1 1 TransDarencv 5 Correct Response-Tap is below the core plate on the inner pipe, see LOT-00-21 1 TransDarencv 5
References:
LOT-00-21 1 Transparency 5 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 2027120201 Perform Jet Pump Operability Test 21 1000 K1.07 Knowledge of the physical connections andor cause-effect 2.6 2.6 relationships between STANDBY LIQUID CONTROL SYSTEM and the following: (CFR 41.2 to 41.9 / 45.7 to 45.8): Jet pump differential pressure indication: Plant-Specific Static Simulator Exams: None Last Revised: 12/22/2004 2: 19:30 PM by Hallonquist, Nora E.
2005 SROU/SROI Ouestion No. 33 Exam Bank Question No.: 3886 Revision: 5 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-212 Objective: CRO-3,4 Question Level: Comprehension Select the correct answer:
The Scram Discharge Volume Water Level Bypass keylock switch was placed in BYPASS to reset a scram, and was left in that position.
During the subsequent startup with the mode switch in STARTUP/HOT STBY and power on Range 2 of the IRMs, the following alarms are received:
SDV NORTH NOT DRAINED (5-B-7)
SCRAM VOL DISCH WTR LVL HI (5-L-6) (Red Window)
BEFORE the alarms, the scram instrument volume vent and drain valves were AFTER the alarms, the scram instrument volume vent and drain valves are now
- a. Open; Open Incorrect - The scram is not bypassed in S/U or Run. the valves will close.
Open; Shut Correct Response - Startup requires a mode switch change. Changing the mode switch deactivates the bypass switch. The discharge volume scram is active, causes a scram and valves to close.
- c. Shut; Open
- d. Shut; Shut Incorrect - Following the scram, when the Incorrect - The scram is not bypassed in S/U or Run, the valves will close.
switch is placed in BYPASS and the scram reset, the valve will open.
References:
ARS 5-L-9,5-L-6 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2120030101 Bypass a Trip Condition on an RPS Channel L*
instrument volume vent andor drain valves Static Simulator Exams: None Last Revised: 12/22/2004 12:37:45 PM by Hallonquist, Nora E.
L 2005 SROU/SROI 215003 K1.02 Knowledge of the physical connections andor cause-effect 3.6 3.6 relationships between INTERMEDIATE RANGE MONITOR (EM) SYSTEM and the followinrr: (CFR Question No. 34 Exam Bank Question No.: 639 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-02-215 Objective: CRO 3,8 Question Level: Comprehension Select the correct answer:
A reactor startup is in progress with the following conditions:
Reactor power is 25 on Range 3 IRM 'IF" bypassed IRM "C" exhibits erratic behavior. The "C" IRM is declared INOPERABLE and bypassed.
What additional actions, if any, should be implemented?
the same rod block channel, but in different RPS channels. There are still two W
J
References:
OP 2 13 1 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2157160401 Respond to IRM System Alarms
I Static Simulator Exams: None Last Revised: 12/22/2004 12:38:04 PM by Hallonquist, Nora E.
141.2 to 41.9 / 45.7 to 45.8): Reactor manual control
2005 SROU/SROI Question No. 35 Exam Bank Question No.: 5945 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-621 Objective: CRO 13 Question Level: Comprehension Select the correct answer:
A large break LOCA has occurred and the Severe Accident Guidelines (SAGS) are being implemented with the following indications:
All RPV water level instruments are downscale SRMs are fully inserted and the count rate is downscale "A" Core Spray was restored and RPV water level begins to rise.
What is the MINIMUM RPV water level at which the SRMs indication will be valid?
I d. I Bottom active fuel (-144 inches)
Incorrect - Not minimum level Incorrect - Not minimum level Correct Response - SRMs must be covered with water to thermalize neutrons. When the SRMs are fully inserted in the core, they are 18" below the core midplane (-
87"). Therefore, the lowest RPV water level where the SRMs are covered with water is at -48".
Incorrect - SRM uncovered Task Associations 2150230101 Operate the Neutron Monitoring System Knowledge of the physical connections and/or cause-effect 2.8
'v' relationshim between SOURCE RANGE MONITOR I
12*8 I
L Static Simulator Exams: None Last Revised: 12/22/2004 1: 1756 PM by Hallonquist, Nora E.
(SRM) SYSTEM and the following: (CFR 41.2 to 41.9 /
45.7 to 45.8): Reactor vessel
2005 SROU/SROI Question No. 36 Exam Bank Question No.: 5922 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-05-215 Objective: CRO 3 Question Level: Comprehension Select the correct answer:
During operation at rated power, the following indications are received on CRP 9-5:
APRM DWNSCL (5-M-4) annunciator APRM downscale light for APRM "C" ROD WTHDRW BLOCK (5-D-3) annunciator If the "C" IRM Mode Switch was placed in STANDBY what response would result?
IRM "C" INOP or Hi-Hi condition at CRP 9-12 only and a half scram
- d. IRM "C" INOP or Hi-Hi condition indicated at CRP 9-5 and 9-12 with no RPS actuation CorrezResponse - Taking the IRM Mode Switch out of operate results in an INOP condition. Companion APRM downscale and INOP IRM results in RPS actuation.
With Mode Switch in RUN the alarms and indications are on the 9-12 onlv.
Incorrect - No 9-5 indication, half scram only Incorrect - RPS actuates Incorrect - RPS actuates, no 9-5 indication
References:
OP 2132; ARS 5-M-4 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2150230101 Operate the Neutron Monitoring System
- L K3.06 Knowledge of the effect that a loss or malfunction of the AVERAGE POWER RANGE MONITOFULOCAL POWER RANGE MONITOR SYSTEM will have on following: (CFR 41.7 / 45.4): IRM: Plant-Specific 3.5 3.6 Static Simulator Exams: None Last Revised: 12/22/2004 1: 17:32 PM by Hallonquist, Nora E.
c
W L
2005 SROU/SROI Question No. 37 Exam Bank Question No.: 5924 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-217 Objective: CRO-3,22 Question Level: Comprehension Select the correct answer:
The plant is operating at 100% power when a Loss of Normal Power occurs. RCIC is manually initiated for RPV level control and has the following indications:
Pump Discharge Pressure - 825 PSIG Pump Suction Pressure - 18" Hg Vac Turbine Speed - 2300 RPM Turbine Inlet Pressure - 820 PSIG Turbine Exhaust Pressure - 4 PSIG For the above conditions, WHICH ONE of the following is correct?
Incorrect - Allowable turbine exhaust pressure is 0-20 psig
- d. Continued RCIC operation is allowed.
Incorrect - Suction pressure is below allowable band
References:
OP 2121 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 2170030101 Manually Initiate Startup of the RCIC System
2 17000 K5.01 Knowledge of the operational implications of the following concepts as they apply to REACTOR CORE!
ISOLATION COOLING SYSTEM (RCIC): (CFR 41.5 /
45.3): Indications of pump cavitation 2.6 2.6 Static Simulator Exams: None Last Revised: 12/22/2004 1:07:46 PM by Hallonquist, Nora E.
L 2005 SROU/SROI 217000 Question No. 38 Exam Bank Question No.: 1360 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-217 Objective: CRO 4 Question Level: Comprehension Select the correct answer:
A3.03 Ability to monitor automatic operations of the REACTOR 3.7 3.6 CORE ISOLATION COOLING SYSTEM (RCIC) including: (CFR 41.7 / 45.7): System pressure Following a reactor scram, RCIC is injecting to the reactor vessel. The RCIC flow control unit is placed in MANUAL and as the reactor is depressurized, Reactor pressure drops from 900 psig to 500 psig.
Select the effect the drop in system inlet pressure will have on RCIC flow and speed.
References:
OP 2 12 1 Source: 2003 VY NRC Exam Required Student
References:
None SRO
Reference:
None Incorrect - Flow increases Incorrect - Flow increases Correct Response - In manual, speed is automatically kept constant. RCIC has a centrifugal pump. As reactor pressure decreases, flow will increase as per a twical DumD curve.
Incorrect - Turbine and pump speed constant in manual Task Associations 2177130401 Maintain Reactor Water Level with RCIC u
Static Simulator Exams: None
Last Revised: 12/22/2004 2:15:49 PM by Hallonquist, Nora E.
c b
2005 SROU/SROI Ouestion No. 39 Exam Bank Question No.: 5946 Revision: 5 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-239 Objective: CRO 6,7 Question Level: Comprehension Select the correct answer:
The plant is in hot shutdown preparing for a planned outage, and the following conditions exist:
Drywell is de-inerted for entry with all nitrogen to containment secured Instrument air to containment in service, but a leaking spectacle flange has The inboard and outboard MSIVs have closed Reactor pressure is.980 psig and rising depressurized the header Because the SRVs would be unavailable after maintained using
, RPV pressure would BEST be sustained SRV opening to conserve pneumatics, but analyzing the given conditions, the use of HF'CI and RCIC are allow for 2-5 openings. Using HPCI and RCIC conserves pneumatics for potential
References:
UFSAR Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2007400501 Control RPV Pressure Using Bypass Valves, HPCI, RCIC, SRVS, RWCU, u
Steam Line Drains
Knowledge and Abilities Associations Ability to (a) predict the impacts of the following on the AUTOMATIC DEPRESSURIZATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR 41.5 / 45.6): Loss of air sumlv to ADS valves: Plant-Specific 3.4 3.6 Static Simulator Exams: None Last Revised: 12/22/2004 12:41:28 PM by Hallonquist, Nora E.
u 2005 SROU/SROI Question No. 40 Exam Bank Question No.: 5974 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-218 Objective: CRO-2 Question Level: Comprehension Select the correct answer:
A small-break LOCA has occurred, HPCI and RCIC have failed. The following plant conditions were achieved as of 1100:
- Drywell pressure
- RPV level
- Low Pressure ECCS 3.0 psig and slowly increasing 125 inches, with level falling at 4.25 inches per minute Two RHR pumps running with normal discharge pressure Assume no operator action is taken, at what time will the ADS valves FIRST open?
References:
OP 2132 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2187010401 Inhibit Automatic Initiation of ADS L-Knowledge and Abilities Associations
218000 Static Simulator Exams: None Last Revised: 12/22/2004 12:41:45 PM by Hallonquist, Nora E.
K5.01 Knowledge of the operational implications of the 3.8 0.8 following concepts as they apply to AUTOMATIC DEPRESSURIZATION SYSTEM: (CFR 41.5 / 45.3):
ADS logic operation
U 2005 SROU/SROI Question No. 41 Exam Bank Question No.: 5948 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-223 Objective: CRO 7 Question Level: Fundamen tal Knowledge/Memory Select the correct answer:
The CRO is at the controls when he receives a radiation alarm and no automatic actions occur.
The BOP operator obtains the following backpanel rad monitor readings:
A Refuel floor 50 mrhr B Refuel floor 30 mrhr A RB Exhaust 7 mrhr B RB Exhaust Failed u scale A
For the Group 3 isolation valves the operators should:
1-causes a comdete isolation
References:
ON 3153; ARS 5-J-1 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 2000170501 Respond to Containment Isolations Knowlec 223002
- e and Abilities Associations A2.07 Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/
NUCLEAR STEAM SUPPLY SHUT-OFF; and (b) based those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR 41.5 / 45.6): Various process 2.7
I instrumentation failures Static Simulator Exams: None Last Revised: 12/22/2004 1:17:06 PM by Hallonquist, Nora E.
~L' 2005 SROU/SROI
- b.
- c.
- d.
PCIS Group 5 will actuate, both inlet PCIS Incorrect - CU-18 will not shut valves will isolate PCIS Group 5 will NOT actuate, only one Incorrect - GP 5 signal present < 127" inlet PCIS valve is available for isolation PCIS Group 5 will NOT actuate, both inlet Incorrect - GP 5 signal present < 127" PCIS valves are available for isolation Question No. 42 Exam Bank Question No.: 5985 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-223 Objective: CRO 7 Question Level: Comprehension Select the correct answer:
.-/
During a reactor startup, the following conditions exist:
following will have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/ NUCLEAR STEAM SUPPLY Rx Pressure 15Opsig RPV Water Level 160" using condensate RWCU letdown 60 gallons/minute A loss of DC-2 occurs concurrent with a reactor scram due to high IRM condition. RPV level decreases to 124" and recovers to 155".
What is the effect on PCIS Group 5?
References:
OP 21 15; OP 2145 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 2000170501 Respond to Containment Isolations Knowledge and Abilities Associations
1 -
I 1 SHUT-OFF: (CFX 41.7 / 45.7): D.C. electrical distribution I I
I Static Simulator Exams: None Last Revised: 12/22/2004 12:42:29 PM by Hallonquist, Nora E.
L' L
W 2005 SROU/SROI 239002 A4.06 Ability to manually operate andor monitor in the control 3.9 4.1 room: (CFR 41.7 / 45.5 to 45.8): Reactor water level Question No. 43 Exam Bank Question No.: 5949 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-602 Objective: CRO 3,5 Question Level: Comprehension Select the correct answer:
Following a feedwater transient the following plant conditions exist:
DW pressure 2.8 psig Rx level 255" Rx pressure 900 psig and rising If an SRV is used for pressure control, the opening time may be operation should be confirmed using the and the SRV
References:
OT 31 14, Note, Section 7 Source: new Required Student
References:
None SRO
Reference:
None Task Associations 2007400501 Control RPV Pressure Using Bypass Valves, HPCI, RCIC, SRVS, RWCU, Steam Line Drains Knowledge and Abilities Associations
i/
Static Simulator Exams: None Last Revised: 12/22/2004 1: 1654 PM by Hallonquist, Nora E.
2005 SROU/SROI Ouestion No. 44 Exam Bank Question No.: 5737 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-259 Objective: CRO 5e Question Level: Comprehension Select the correct answer:
The plant is operating at 100% ower. The "A" main steam line flow signal fails to "0" due to a blown fuse.
A procedure to mitigate the transient.
S D d ?
Without operator action, predict the RPV water level response, and determine the correct level below the turbine trip setpoint, OT 3114 Reactor High Level Incorrect - Stabilizes at lower level Correct Response - SF input 1/4 of signal.
Level signal compensates for SFEF mismatch.
Incorrect - Water level lowers Incorrect - Water level lowers
References:
OT 3 1 13 Source: 2003 VY NRC Exam Required Student
References:
None SRO
Reference:
None Task Associations 2000310501 Respond to Low Reactor Water Level lities Associations Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR 41.5 / 45.6): Loss of any number of main steam flow intmts
Static Simulator Exams: None Last Revised: 12/22/2004 2:15:07 PM by Hallonquist, Nora E.
2005 SROU/SROI
- d.
Question No. 45 Exam Bank Question No.: 5983 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-261 Objective: CRO 3 Question Level: Fundamental KnowledgeMemory Select the correct answer:
closed, open, open Incorrect - 1 N l B open on auto initiation only, not HPCI start The following plant conditions exist:
Plant is at 1 S B t T "A" aligned fw-yenting SBGT "B" in standby liQeup
/
HPCI is started for the full flow test surveillance with no further operator action. What is the position of the following SBGT Valves:
Inlet Isolation SGT-2A Inlet Isolation SGT-2B Inlet Bypass SGT-lA/B
References:
OP 2 1 17 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 2610010101 Perform Lineups on the SBGT System Knowledge and Abilities Associations
',A I261000 I A3.03 1 Ability to monitor automatic operations of the STANDBY 13.0 12.9 I
v i GAS TREATMENT SYSTEM including: (CFX 41.7 /
45.7): Valve oDeration Static Simulator Exams: None Last Revised: 12/22/2004 12:43:33 PM by Hallonquist, Nora E.
i, 2005 SROU/SROI 262001 Question No. 46 Exam Bank Question No.: 5925 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-03-262 Objective: CRO 7 Question Level: Comprehension Select the correct answer:
K1.04 Knowledge of the physical connections and/or cause-effect 3.1 3.4 relationships between A.C. ELECTRICAL DISTRIBUTION and the following: (CFR 41.2 to 41.9 /
45.7 to 45.8): Unintermptible power supply The "UPS FDR SIG BLK" keylocks are inadvertently left in "BLK". A LOCA and LNP occurs.
How will UPS respond?
AC drive when the emergency diesel A/C UV clears, the AC motor starts.
Incorrect - The only delay in the system is
@$3:
J&2i generators power busses 3/8 and 4/9.
AC drive 5 minutes after the emergency diesel generators power busses 3/8 and 4/9.
a 2 sec delay for RHR 27 operation.
L
References:
OP 2143; LOT-00-264 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2007020501 Respond to Loss of Normal Power Static Simulator Exams: None Last Revised: 12/22/2004 12:43:59 PM by Hallonquist, Nora E.
b' 2005 SROU/SROI 262002 Question No. 47 Exam Bank Question No.: 5977 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-03-262 Objective: CRO 6 Question Level: Fundamental KnowledgeMemory Select the correct answer:
A1.02 Ability to predict and/or monitor changes in parameters 2.5 2.9 associated with operating the UNINTERRUPTABLE 1s including: (CFR The "A" UPS requires maintenance and is to be removed from service per OP 2143, "480 and Lower Voltage System". The first step is for the BOP to place UPS-1A Control Selector Keylock Switch on CRP 9-3 to OFF. The BOP should expect Bus 89A voltage to:
References:
OP 2143 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 2627310101 Transfer MCC-89A(B) Power from RUPS to the Maintenance TIE
L 2005 SROU/SROI v
Question No. 48 Exam Bank Question No.: 5927 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-283 Objective: CRO 3 Question Level: Fundamental Knowledge/Memory Select the correct answer:
- b. John Deere Diesel
- c. Alt S/D Batt 1AS
- d. Alt S / D Batt 2AS An electrical fault occurred on Bus 1 three seconds ago, generating an LNP signal and a load shed. What is the CURRENT power source for ERFIS?
c
References:
OP 2148 (Discussion Section)
Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Correct Response - Transfers to battery on loss of power Incorrect - A loss of Bus 1 will result in a loss of Bus 11 (and if sustained, an auto start of the JDDG); however, the arrangement with the batteryhnverter will result in a seamless transfer to battery Dower without transfer of the static switch Incorrect - 1AS does NOT supply power to ERFIS Incorrect - 2AS does NOT supply power to ERFIS Task Associations 2007020501 Respond to Loss of Normal Power Knowledge and Abilities Associations relationships between UNINTERRUPTABLE POWER SUPPLY (A.C./ D.C.) and the following: (CFR 41.2 to 41.9 / 45.7 to 45.8): Unit computer: Plant-Specific Static Simulator Exams: None Last Revised: 12/22/2004 12:44:41 PM by Hallonquist, Nora E.
u 2005 SROU/SROI 263000 Question No. 49 Exam Bank Question No.: 5989 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-263 Objective: CRO 5 Question Level: Comprehension Select the correct answer:
K2.01 Knowledge of electrical power supplies to the following:
3.1 3.4 (CFR 41.7): Major D.C. loads An electrical transient has occurred resulting in the following:
VITAL MG SET DCLOSSDC RUN (8-P-8) vc---
BUS 8 MCC TROUBLE (8-J-8)--
Bus 8 voltage - 480V Bus 9 voltage - 480V FWLC and FRVs remain in automatic What is the DC electrical power supply for the Vital AC MG? &-
l Dower is unavailable to the Vital AC MG.
motor on the MG set Incorrect - If DC power was lost the FRVs would have locked up.
References:
ARS (8-P-8); OP 2144 Source: New Required Student
References:
None SRO
Reference:
None Task Associations
Static Simulator Exams: None Last Revised: 12/22/2004 1:08:27 PM by Hallonquist, Nora E.
L' 2005 SROU/SROI 263000 Question No. 50 Exam Bank Question No.: 5950 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-263 Objective: CRO 9 Question Level: Fundamental KnowledgeMemory Select the correct answer:
K5.01 Knowledge of the operational implications of the 2.6 2.9 following concepts as they apply to D.C. ELECTRICAL DISTRIBUTION: (CFR 41.5 / 45.3): Hydrogen generation during battery charging BAT" RM EXH FAN (SEF-3) has tripped.
Which of the following describes a required action and the reason for that action?
v When battery room exhaust fan SEF-3 is
References:
OP 2192 Precaution #19 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations
Static Simulator Exams: None Last Revised: 12/22/2004 12:45:04 PM by Hallonquist, Nora E.
W 2005 SROU/SROI Question No. 5 1 Exam Bank Question No.: 3741 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-262 Objective: CRO 6,7 Question Level: Comprehension Select the correct answer:
During power operations, the following occurs:
DW pressure rises to 4 psig The 3Tl breaker trips on overload Which of the statements below accurately describes the loads response when the Diesel energizes the bus?
L-I a. 1 The SW, RHR, and Core Spray pumps start immediately since their breakers are immediately, the SW pump sequences on in 10 seconds The SW pump and 1 RHR start immediately followed by the second RHR pump and finally the Core Spray pump immediately followed by 1 RHR pump and finally the 2nd RHR DumD Incorrect - Core Spray and 1 RHR pump starts are delayed by 10 sec and 5 sec respec ti vel y Incorrect - SW pump starts immediately, CS pump starts are delayed Correct Response - Correct loading has SW and 1 RHR pump start immediately followed by 1 RHR pump (5 sec) and CS pump (10 sec)
Incorrect - Core Spray pump start is delayed
References:
UFSAR Table 8.5.lb Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2007020501 Respond to Loss of Normal Power b
I 264000 I K5.06 I Knowledge of the operational implications of the 13.4 13.5 I
i/
Static Simulator Exams: None Last Revised: 12/22/2004 12:45:28 PM by Hallonquist, Nora E.
following concepts as they apply to EMERGENCY GENERATORS (DIESELLJET): (CFR 41.5 / 45.3: Load seauencing c
c' 2005 SROU/SROI 300000 Question No. 52 Exam Bank Question No.: 5951 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-239 Objective: CRO 3 Question Level: Fundamental Knowledge/Memory Select the correct answer:
K1.05 Knowledge of the physical connections andor cause-effect 3.1 3.2 relationships between INSTRUMENT AIR SYSTEM and the following: (CFR 41.2 to 41.9 / 45.7 to 45.8): Main Steam Isolation valve air The plant is operating at 70% reactor power.
The CRO depresses the TEST pushbutton for MS-86B, 'B' OUTBOARD MSIV.
As bleeds off, the MSIV will close I d. I air; in 3-5 seconds Incorrect - Outboard MSIVs use air not nitrogen Incorrect - Outboard MSIVs use air not nitrogen and the valve closes slowly with the test pushbutton Correct Response - Outboard MSIVs use air not nitrogen Incorrect - The valve will close slowly using. the test Dushbutton.
References:
OP 4113; OP 2191 Source: Fitzpatrick 2003 Required Student
References:
None SRO
Reference:
None Task Associations
. Ta
~~~~~~
2397030201 Perform MSIV Partial Closure Test Static Simulator Exams: None Last Revised: 12/22/2004 1:25:26 PM by Hallonquist, Nora E.
L, 2005 SROU/SROI 400000 Ouestion No. 53 Exam Bank Question No.: 165 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-601 Objective: CRO 1 Question Level: Comprehension Select the correct answer:
K3.01 Knowledge of the effect that a loss or malfunction of the 2.9 3.3 COMPONENT COOLING WATER SYSTEM will have on following: (CFR 41.7 / 45.4): Loads cooled by CCWS The plant is operating at full power when the CRO observes the following alarming annunciators:
mTEL POOL CLG SYS TEMP HI (4-H-7)
DWL EQMT DRN SUMP TEMP HI (4-L-3)
RX BLDG EQMT DRN SUMP SOUTH TEMP HI (4-L-5)
RX BLDG EQMT DRN SUMP NORTH TEMP HI (4-M-5)
Predict the effect on additional plant equipment.
References:
ON 3147; ARS 4-H-7,4-L-3,4-L-5,4-M-5 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations ond to RBCCW Failure Static Simulator Exams: None Last Revised: 12/22/2004 12:45:52 PM by Hallonquist, Nora E.
2005 SROU/SROI
- d.
Question No. 54 Exam Bank Question No.: 5873 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-201 Objective: CRO 2c Question Level: Fundamental KnowledgeMemory Select the correct answer:
Given the following:
- The plant is operating at 100% power
- An Accumulator Trouble alarm is received for a control rod at position 48
- The alarm is determined to be caused by low accumulator pressure
- An A 0 is asked to clear the alarm condition While the accumulator is isolated and is being recharged, a reactor scram occurs.
How will the control rod respond and what followup action is required?
The control rod will drift into the fultly inserted position.. Restore the accumulator to service immediately.
- a. The control rod will remain at its present position and not move. Restore the accumulator to service immediately.
The control rod will scram within Tech Spec allowable insertion time. Verify all rods inserted using the PSRP.
than Tech Spec allowable insertion time.
Verify all rods inserted using the PSRP.
Incorrect - at an RPV pressure of > 800 psig, control rods will scram within TS allowable limits due to the dP of reactor pressure alone (no accumulator required)
Correct Response - at an RPV pressure of
> 800 psig, control rods will scram within TS allowable limits due to the dP of reactor pressure alone (no accumulator reauired)
Incorrect - at an RPV pressure of > 800 psig, control rods will scram within TS allowable limits due to the dP of reactor pressure alone (no accumulator required)
Incorrect - at an RPV pressure of > 800 psig, control rods will scram within TS allowable limits due to the dP of reactor Dressure alone (no accumulator reauired)
References:
T.S. Bases 3.3.D Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None L-,
Task Associations u
I201003 I A2.05 2010010404 Respond to Control Rod Drive Accumulator Trouble Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR 41.5 / 45.6): Reactor Scram 4.1 4.1 Static Simulator Exams: None Last Revised: 12/22/2004 12:46:20 PM by Hallonquist, Nora E.
2005 SROU/SROI Question No. 55 Exam Bank Question No.: 5928 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-202 Objective: CRO-6,7 Question Level: Comprehension Select the correct answer:
During a reactor startup with both Recirc Pumps operating at minimum speed and reactor power at 20%, the "A" Recirc Pump trips.
The drive flow in Recirc Loop "B" is observed to be 4.6 mlbhr.
How will indicated core flow on the ERFIS Power-to-Flow map and CRP 9-5 recorder compare to actual flow, and why?
- a.
C.
- d.
Indicated flow is lower than actual due to reverse (negative) flow in the "A" loop jet pumps Indicated flow is lower than actual due to forward (positive) flow in the "A" loop jet pumps Indicated flow is higher than actual due to reverse (negative) flow in the "A" loop jet Pumps Indicated flow is higher than actual due to forward (positive) flow in the "A" loop jet pumps Incorrect - Flow is forward Correct Response - At driving flows of <5 mlb/hr in the operating loop, forward flow will occur in the idle loop but it will be subtracted as though it were reverse flow, causing indicated core flow to be less than actual Incorrect - The core flow summer will subtract a greater flow signal than is actually bypassing the core, resulting in an indicated flow that is lower than actual flow Incorrect - At a driving flow of > 5mlb/hr in the operating loop, reverse flow will occur in the idle loop jet pumps, AND the core flow summer will subtract a greater flow signal than is actually bypassing the core, resulting in an indicated flow that is lower than actual
References:
OP 21 10 Source: VY Exam Bank Required Student
References:
None L
Reference:
None
L Task Associations i'
I 299009030 1 Report Abnormal Parameters or Conditions Ability to manually operate andor monitor in the control room: (CFR 41.7 / 45.5 to 45.8): Core flow Static Simulator Exams: None Last Revised: 12/22/2004 12:47:05 PM by Hallonquist, Nora E.
u 2005 SROU/SROI
- b.
Question No. 56 Exam Bank Question No.: 5953 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-204 Objective: CRO 3 Question Level: Fundamental KnowledgeMemory Select the correct answer:
During a reactor startup with "A" RWCU pump inservice operating in the letdown mode for RPV water level control, the following alarm is observed:
RWCU DRAIN LINE PRESS HYLO (4-5-6)
Predict the automatic response of the RWCU system.
RWCU pump tripped Drain flow regulator (PCV-55) remains I a.1 Drain flow regulator (PCV-55) shut, I I 31 RWCU pump operating
- d. Drain flow regulator (PCV-55) remains open, RWCU pump operating i--
References:
ARS 4-5-6 Source: New Required Student
References:
None SRO
Reference:
None Task Associations Incorrect - PCV-55 shut only. RWCU DumD unaffected.
Incorrect - PSV-55 shuts pump, should n o t trip Correct Response - PSV-55 shuts pump, unaffected by signal Incorrect - PCV-55 shut 2040080101 Operate the RWCU System to Conduct Letdowns Knowledge and Abilities Associations WATER CLEANUP SYSTEM including: (CFR 4 1.7 /
45.7): System pressure downstream of the pressure regulating valve: LP-RWCU Static Simulator Exams: None Last Revised: 12/22/2004 12:47:24 PM by Hallonquist, Nora E..
L-',
2005 SROU/SROI Question No. 57 Exam Bank Question No.: 5988 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-216 Objective: CRO 1 IC Question Level: Fundamental Knowledge/Memory Select the correct answer:
During a reactor plant cooldown with the following conditions:
RPV water level 151" steady RPV Pressure 260 psig and decreasing DW Temp 215 O F and rising slowly If conditions continue to degrade, the RPV water level instruments are susceptible to leg flashing resulting in RPV water indicated level failing reference; high reference; low variable; high variable; low Correct Response - When reference legs flash, the sensed dP goes down, causing indicated level to rise.
Incorrect - When reference legs flash, the sensed dP goes down, causing indicated level to rise.
Incorrect - The reference legs are much longer than the variable legs and are significantly more affected by Drywell temperature. The variable legs are kept full bv the reactor water.
Incorrect - When reference legs flash, the sensed dP goes down, causing indicated level to rise.
References:
EOP-1 Study Guide Source: New Required Student
References:
None SRO
Reference:
None Task Associations
/;*a 4 II-.
2000210501 Respond to High Drywell Temperature u Knowledge and Abilities Associations
following concepts as they apply to NUCLEAR BOILER INSTRUMENTATION: (CFX 41.5 / 45.3): Reference leg Static Simulator Exams: None Last Revised: 12/22/2004 12:48:30 PM by Hallonquist, Nora E.
c
L v
2005 SROU/SROI Question No. 58 Exam Bank Question No.: 5639 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: CRO 2 Question Level: Comprehension Select the correct answer:
A small break LOCA has occurred resulting in the following parameters:
DW Pressure - 8 psig RPV Water Level - 135" RPV Pressure - 860 psig RHR Pump "A" was placed in torus cooling due to a high torus temperature.
Subsequently, a large break LOCA results in an RPV water level of -200".
Without operator action, what is the expected RHR system response, and the impact on vessel injection flow?
- a.
- b.
- d.
RHR-65A remains closed, and the torus cooling lineup isolates. "A" RHR injection flow of approximately 13,000 gpm is expected.
RHR-65A opens, but the torus cooling lineup is unaffected. "A" RHR injection flow of approximately 6,500 gpm is expected.
RHR-65A remains closed, and the torus cooling lineup isolates. "A" RHR injection flow of approximately 6,500 gpm is expected.
RHR-65A opens, but the torus cooling lineup is unaffected. "A" RHR injection flow of approximately 13,000 gpm is expected.
Incorrect - Only 1 RHR pump is operating instead of 2 pumps.
Incorrect - Torus cooling valves isolate by interlock (2/3 C.H.) to divert flow to vessel. RHR-65A remains closed. Only 1 RHR pump is operating instead of 2 pumps.
Correct Response - Torus cooling valves isolate by interlock (2/3 C.H.) to divert flow to vessel. Only 1 RHR pump is oDerating. instead of 2 mmm.
Incorrect - Torus cooling valves isolate by interlock (2/3 C.H.) to divert flow to vessel. RHR-65A remains closed. Only 1 RHR pump is operating instead of 2
+
References:
OP 2124 Source: VY 2002 NRC Exam Required Student
References:
None SRO
Reference:
None Task Associations
~
Startup the RHR System in the Torus Cooling Mode
POOL COOLING MODE design feature(s) and/or interlocks which provide for the following: (CFR 41.7):
Unintentional reduction in vessel injection flow during accident conditions: Plant-SDecific Static Simulator Exams: None Last Revised: 12/22/2004 3:42:20 PM by Murphy, Kevin
2005 SROU/SROI Question No. 59 Exam Bank Question No.: 6002 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-626 Objective: CRO 3,4 Question Level: Fundamental KnowledgeMernory Select the correct answer:
The following conditions exist post LOCA:
DW pressure 35 psig rising slowly What actions (if any) are required to reduce DW pressure using the Torus Hardened Vent Flowpath to the Stack and predict the DW pressure response?
Open TVS-86, Torus Vent Valve.
DW pressure will immediately start to lower.
TVS-86, Torus Vent Valve, wi automatically open a t h p s i g k DW pressure will lower.
Y Open TVS-86, Torus Vent Valve.
DW pressure will continue to rise teS4 DW pressure to lower.
TVS-86, Torus Vent Valve, will automatically open at 2.5 psig.
DW pressure will continue to rise t d 9 until the rupture disc ruptures, causing i until the rupture disc ruptures, causing Y
W pressure to lower.
Incorrect - DW pressure will not lower until rupture disc ruptures.
Incorrect - No aut ures with TVS-86, normally closed.
psig, rupture disc will not be subjected to the pressure with TVS-86 closed.
Correct Response - Rupture disc is designed to rupture between 56-62 psig, TVS-86 is normally closed and must be opened.
Incorrect - No auto features with TVS-86, normally closed. At 59 psig, rupture disc will not be subjected to the pressure with TVS-86 closed.
References:
OP 21 15 Discussion Section Page 6; OE 3 107 Appendix HH Source: New Required Student
References:
None SRO
Reference:
None Task Associations
~~~~~
2007800501 Perform Primary Containment Venting per APPENDIX HH W
Knowledge and Abilities Associations
associated with operating the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES Static Simulator Exams: None Last Revised: 12/22/2004 1:16:28 PM by Hallonquist, Nora E.
'W 233000 2005 SROU/SROI A3.02 Ability to monitor automatic operations of the FUEL 2.6 2.6 POOL COOLING AND CLEAN-UP including: (CFR 41.7 / 45.7): Pump trip(s)
Question No. 60 Exam Bank Question No.: 3588 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-233 Objective: CRO 3 Question Level: Fundamen tal KnowledgeMemory Select the correct answer:
The plant is in normal full power operations with Fuel Pool Cooling Pump "A" in service.
A leak develops upstream of inlet isolation valve, FPC-220 and F'PC-221.
As fuel pool level starts to drop, what is the expected system response?
FPC-220/221 remain open and FPC Pump "A" continues to run.
FPC-220/221 remain open and FPC Pump "A" trips.
FPC-220/221 close and FPC Pump "A" continues to run.
FPC-220/221 close and FPC Pump "A" trips.
Incorrect - Valves isolate, pump trips on isolate Incorrect-pumptrips on lowsuction messure Correct Response-Valves close on low level signal, Pumps will trip on low suction Dressure
References:
OP 2184 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2337140401 Respond to Fuel Pool Cooling System Alarms Knowledge and Abilities Associations Static Simulator Exams: None Last Revised: 12/22/2004 12:49:50 PM by Hallonquist, Nora E.
d'
2005 SROU/SROI FUEL HANDLING will have on following: (CFR 41.7 /
45.4): Reactor manual control system: Plant-Specific Question No. 61 Exam Bank Question No.: 5957 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-234 Objective: CRO 1 Question Level: Comprehension
- A*************************************************************
Select the correct answer:
i During refueling operations, the following conditions exist:
Mode Switch in REFUEL Refuel platform over the core Control Rod 26-27 at position 04 Grapple up and open The Reactor Manual Control System 1 ill initiate a rod block if conditions already exist for a rodblock.
(a I This signal is the missing input, no rod block.
Incorrect - Not an input to refuel interlock Correct Response - A load cell failure will result in indications of a fuel bundle grappled. This will satisfy refuel interlock Discussion
References:
None SRO
Reference:
None Task Associations 23471 10201 Perform Functional Test of Refueling Interlocks Know1edg.e and Abilities Associations
Static Simulator Exams: None Last Revised: 12/22/2004 1: 16:14 PM by Hallonquist, Nora E.
i-2005 SROU/SROI Ouestion No. 62 Exam Bank Question No.: 5990 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-239 Objective: CRO 3 Question Level: Fundamental KnowledgeMemory Select the correct answer:
The reactor scrams on high drywell pressure, and the following indications exist:
RX SAFETY VLV OPEN (3-B-1) has alarmed The acoustic monitor indicates SV-70C is open Reactor pressure is 900 psig and lowering Which of the following describes the current condition of the plant?
- a. SV-70C should be open. Steam is passing from the C main steam line directly to the drywell.
- b. SV-70C should have closed. Steam is passing from the D main steam line directla the torus.
- c. SV-70C should be open. Steam is passing from the D main steam line directly to the torus.
__c Incorrect - SV-70C relieves directly to the drywell, Even if SV-70C had lifted normally, it should have reseated at 1180
- psig.
Incorrect - SV-70C is located on the C IMSL.
Incorrect - SV-70C is located on the C MSL. Even if SV-70C had lifted normally, it should have reseat at 1180 the C MSL and relieves directly to the S 3-B-1
References:
None I
Requir SRO
Reference:
NT-Task Associations 2000270501 Respond to a Loss of Feedwater Knowledge and Abilities Associations
(239001 K6.04 Knowledge of the effect that a loss or malfunction of the following will have on the MAIN AND REHEAT STEAM SYSTEM: (CFR 41.7 / 45.7): Relief valve operability: Plant-Specific 3.4 3.5 Static Simulator Exams: None Last Revised: 12/22/2004 1:08:44 PM by Hallonquist, Nora E.
u 2005 SROU/SROI Question No. 63 Exam Bank Question No.: 3839 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-307 Objective: CRO A2, A5 Question Level: Comprehension Select the correct answer:
A reactor shutdown is in progress with reactor power at 43% RTP. The following annunciator alarms:
STOPKTRL VLV FAST CLOSURE BYP (5-K-8)
What is the effect on RPS if a turbine trip were to occur, why?
- a. Reactor scram will occur because the margins to the fuel thermal-hydraulic limits are challeneed.
L immediate scram is required due to reactor ion transient limits are reactor pressurization transient limits are NOT challenged.
Incorrect - Scram will not occur, reason is correct Incorrect - Scram will not occur, reason is correct Correct Response - T.S. bases discusses the pressurization transient above 30%
RTP Incorrect - Limits are challenged above 30% RTP
References:
T.S. 3.1 Bases; ARS 5-K-8 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2450120101 Shutdown the Turbine Generator Knowledne and Abilities Associations
Static Simulator Exams: None Last Revised: 12/22/2004 1:16:02 PM by Hallonquist, Nora E.
MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS will have on following: (CFR 41.7 / 45.4):
W'
- b.
2005 SROU/SROI Both a high temperature and an ionization signal are required for the alarm. After 22 seconds, either one is adequate for the svstem to actuate.
Question No. 64 Exam Bank Question No.: 5958 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-286 Objective: CRO 2f Question Level: Fundamen tal KnowledgeMemory Select the correct answer:
Concerning the Recirc MG Set fire protection system:
Which of the following describes the required combination of high temperature and ionization signals for both the alarm and the actuation to occur?
L
- a. Both a high temperature and an ionization signal are required for the alarm. After 22 seconds, both are also required for the svstem to actuate.
Incorrect - Either to alarm Incorrect - Either to alarm Incorrect - Both to actuate Correct Response - Either to alarm, both to actuate
References:
OP 2186 Discussion Section Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 286729040 1 Respond to Pyrotronics Panel Alarms Knowledee and Abilities Associations U
feature(s) and/or interlocks which provide for the following: (CFR 41.7) (CFR 41.5 / 45.3) (CFR 41.7 / 45.7)
(CFR 41.5 / 45.5) (CFR 41.5 / 45.6) (CFR 41.7 / 45.7)
(CFR 41.7 / 45.5 to 45.8): Fire suppression capability that does not rely on the displacement of oxygen (Halon):
Plant-SDecific Static Simulator Exams: None Last Revised: 12/22/2004 1:15:48 PM by Hallonquist, Nora E.
2005 SROU/SROI 290002 K4.05 Knowledge of REACTOR VESSEL INTERNALS design 3.3 3.5 feature(s) and/or interlocks which provide for the following: (CFR 41.7): Natural circulation Question No. 65 Exam Bank Question No.: 5993 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: CRO 5 Question Level: Fundamental KnowledgeMemory Select the correct answer:
With the vessel head installed, and a loss of shutdown cooling, what is the MINIMUM level at which natural circulation is established?
I b+
I RPV water level just above the bottom of the steam separators RPV water level at the top of the steam seDarators RPV water level at the middle of the steam dryer skirt RPV water level at the top of the steam drver bottom of the predryers on the steam separator, creating a natural circulation path between the inside and outside of the I
Incorrect - Excessively high water level Incorrect - Excessively high water level
References:
ON 3 156 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations 2057090101 Operate the RHR System in the Shutdown Cooling Mode Static Simulator Exams: None Last Revised: 12/22/2004 12:51:36 PM by Hallonquist, Nora E.
.u
~..-/
2005 SROU/SROI 0
Question No. 66 Exam Bank Question No.: 5996 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-03-400 Objective: CRO 1 Question Level: Fundamental KnowledgeMemory Select the correct answer:
2.1.OS Ability to coordinate personnel activities outside the 3.8 3.6 control room (CFR 45.5,45.12,45.13)
A tagging evolution in the 345 KV switchyard needs to be completed.
How should this activity be coordinated?
- c. Dispatch 1 operator at a time to hang tags to ensure independent verification is maintained.
- d. Dispatch 2 operators to hang tags ensuring separation is maintained for independent verification Dumoses.
Incorrect - Will not meet DP 0166 standard peer check for 345 KV tagging evolution, Incorrect - Will not meet DP 0166 standard 7
Incorrect - Will not meet DP 0166 standard
References:
DP 0166, Page 35,1.2.b.14 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 3410380302/0 Interpret and Ensure Compliance with Plant Administrative Procedures 3
During Normal and off Normal Plant Operations Static Simulator Exams: None Last Revised: 12/22/2004 12:51:54 PM by Hallonquist, Nora E.
2005 SROU/SROI Question No. 67 Exam Bank Question No.: 3596 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-283 Objective: CRO 7 Question Level: Comprehension Select the correct answer:
Following a large break LOCA, RPV water level recovers to 2/3 core height.
The following information regarding Core Spray status is available on ERFIS ECCS Status screen:
Core Spray A Flow 3725 gpm, displayed in purple Core Spray B Flow 4100 gpm, displayed in green From this it can be determined that:
0 2.1.19 Ability to use plant computer to obtain and evaluate 3.0 3.0 parametric information on system or component status both Core Spray pumps are providing adeauate core cooling.
neither Core Spray pump is providing adequate core cooling.
the A Core Spray pump is providing adequate core cooling, B Core Spray flow is auestionable.
the B Core Spray pump is providing adequate core cooling, A Core Spray flow is auestionable.
References:
EOP-1 Study Guide Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Incorrect - B flow > 3250,gpm reliable Incorrect - A flow is unreliable Correct Response - B flow > 3250 gpm reliable Know1edg.e and Abilities Associations
I (CFR 45.12)
Static Simulator Exams: None Last Revised: 12/22/2004 12:52: 11 PM by Hallonquist, Nora E.
c
L-2005 SROU/SROI 0
2.1.32 Ability to explain and apply system limits and precautions 3.4 3.8 (CFR 41.10,43.2,45.12)
Ouestion No. 68 Exam Bank Question No.: 5959 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-206 Objective: CRO 7 Question Level: Comprehension Select the correct answer:
During the HPCI quarterly surveillance, the following conditions exist:
Steam Supply pressure - 1000 psig Discharge Pressure - 1050 psig Turbine Speed - 1900 rpm Suction Pressure - 10 psig System Flow - 2400 gpm Prolonged HPCI operation with these conditions will:
I d. I challenge NPSH limits.
I Incorrect - Pump limit, not turbine
References:
OP 2120 Precaution 13 Source: Limerick 1 2002 NRC Exam Required Student
References:
None SRO
Reference:
None Task Associations i
20600<0101 Manually Initiate HPCI Static Simulator Exams: None Last Revised: 12/22/2004 1:15:32 PM by Hallonquist, Nora E.
2005 SROU/SROI 0
.............................................................................. /
Ouestion No. 69 Exam Bank Question No.: 5961 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-413 Objective: CRO 9 Question Level: Fundamental KnowledgeMemory Select the correct answer:
2.2.13 Knowledge of tagging and clearance procedures (CFR 3.6 3.8 41.10,45.13)
Changes to a Tagging Order boundary are required and the TagoutNork Order Holder is off-site and cannot be reached.
Which one of the following is correct regarding the requirements for the changes to be accomplished?
- d. The Tagout Holder Supervisor and the Tagout Holder Manager must double authorize the changes.
References:
EN-OP-102 Section 5.14 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Incorrect - Tagout Holder Supervisor alone is insufficient. SM also rewired.
Incorrect - SM alone is insufficient.
Tagout Holder Supervisor also required.
Correct Response - EN-OP-102 Section 5.14, Alternate Release Authorization, requires both the Tagout Holder Supervisor and the Shift Manager.
Incorrect - Tagout Holder Manager is not required or a substitute for the SM.
J
'U Static Simulator Exams: None
Last Revised: 12/22/2004 12:54:06 PM by Hallonquist, Nora E.
L
2005 SROU/SROI 0
Ouestion No. 70 Exam Bank Question No.: 5962 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-215 Objective: CRO 5 Question Level: Fundamental KnowledgeMemory Select the correct answer:
2.2.30 Knowledge of RO duties in the control room during fuel 3.5 3.3 handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and sutmortinE instrumentation (CFR 45.12)
Which one of the following is a responsibility of the Reactor Operator during core alterations?
- c. Perform verification of in-core coordinates Incorrect - Responsibility of refuel supervisor
- d. Observe refuel floor radiation for rising Incorrect - Responsibility not specified to radiation any individual L
References:
OP 1101 Section A.3 CRO Responsibilities Source: Clinton 2002 NRC Exam Required Student
References:
None SRO
Reference:
None Task Associations "l;r
/,/
,.
- I
~~~~~
2157160101 Monitor and Log SRM Meters During Refuel Static Simulator Exams: None Last Revised: 12/22/2004 1:13:22 PM by Hallonquist, Nora E.
2005 SROU/SROI Ouestion No. 71 Exam Bank Question No.: 5965 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-603 Objective: CRO 3 Question Level : Fundamen tal KnowledgehIemory Select the correct answer:
Accident conditions have resulted in the following:
Increasing Turbine Building ARM readings on CRP 9-1 1 Turbine Building air samples show excessive airborne contamination levels of 1.0 mrhr Which of the following describes the required actions?
from clean to contaminated and provides an elevated release. All doors leading outside or to adjacent structures are closed to prevent the spread of airborne contamination.
- b. Shutdown Turbine HVAC, and place the CONTROL ROOM W A C RECIRC MODE SELECT switch to EMER.
Incorrect - HVAC flowpath is from clean to contaminated and provides an elevated release Shutdown Turbine HVAC, and close all Incorrect - HVAC flowpath is from clean turbine building outside doors.
to contaminated and provides an elevated release Allow Turbine HVAC to operate normally, Incorrect - CONTROL ROOM HVAC and allow Control Room HVAC to operate RECIRC MODE SELECT switch is placed normally.
.to EMER.
References:
OP 2192; ON 3153 Source: New Required Student
References:
None SRO
Reference:
None Task Associations 2727150401 Respond to ARM Alarms
10 12.3.1 1 I Ability to control radiation releases (CFR 45.9,45.10) 12.7 13.2 I u
Static Simulator Exams: None Last Revised: 12/22/2004 12:55:41 PM by Hallonquist, Nora E.
b 2005 SROU/SROI Question No. 72 Exam Bank Question No.: 5966 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-404 Objective: CRO 3 Question Level: Fundamental KnowledgeMemory Select the correct answer:
Plant conditions are as follows:
A pump room has general area dose rates ranging from 1 mredhr to 3 mredhr Contamination levels are 2000 dpd100 cm2 Which one of the following lists the area posting for the pump room per AP 0503, Establishing and Posting Restricted Areas?
High Radiation Area and Contamination I a' 1 Area
- b. Radiation Area only L'
Incorrect - > 2mrem/hr makes it an RCA -1 Incorrect - > 2mem/hr makes it an RCA, <
5 mrem/hr not a radiation area, > 1000 dpd100cm2 makes it a contamination area Correct Response - > 2mredhr makes it an RCA, < 5 mredhr not a radiation area,
> 1000 dpd100cm2 makes it a contamination area Incorrect - e 5 m e d h r not a radiation I
area, > 1000 dpd100cm2 makes it a I
contamination area
References:
AP 0503 Definition Section 2.8,2.9,2.3 Source: Limerick1 2002 NRC Exam Required Student
References:
None SRO
Reference:
None Task Associations 2990100301 Apply Radiation and Contamination Safety Procedures Knowledge and Abilities Associations
I control reauirements (CFR 41.12.43.4.45.9.45.10)
Static Simulator Exams: None Last Revised: 12/22/2004 1:24:01 PM by Hallonquist, Nora E.
c 2005 SROU/SROI Question No. 73 Exam Bank Question No.: 3668 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-610 Objective: CRO 1 Question Level: Fundamental KnowledgeMemory Select the correct answer:
The plant is operating at power when a spurious Group I isolation occurs.
All control rods remain at their original positions.
APRMs indicate approximately 96% power.
All 4 SRVs have opened automatically and RPV pressure is >1200 psig.
Core flow is 45 mlbhr.
The CRO attempts a manual scram which fails to insert control rods and scram air header pressure remains at 75 psig.
Without direction the Control Board operators must immediately:
initiate ARIRPT and inhibit=
initiate ARIRPT and lower RPV water level by depressing PB 1 on master F W controller.
inhibit ADS and lower RPV water level by depressing PB 1 on master FW controller.
Incorrect - Inhibiting HPCI is directed by Correct Response - DP 0166 requires initiation of ARIRPT without direction if reactor power is > 2% and scram signal exists @P 0166 A.2.d.l.a). Additionally, PB 1 is depressed reducing setpoint to 133 if a scram signal exists. @P 0166 B.2)
Incorrect - Inhibiting ADS is directed by CRS. Also, initiating ARI/RPT must be done as soon as possible to trip the Recirc Pump Field Breakers to lower Reactor Power.
Incorrect - Inhibiting ADS is directed by CRS. Also, initiating ARI/RPT must be done as soon as possible to trip the Recirc Pump Field Breakers to lower Reactor Power.
References:
OP 2172; DP 0166 Source: VY Exam Bank v
Required Student
References:
None
Reference:
None L,
0 Task Associations 2000200501 Respond to ATWS Event(s) 2.4.01 Knowledge of EOP entry conditions and immediate action 4.3 4.6 steps (CFR 41.10,43.5,45.13)
Static Simulator Exams: None Last Revised: 12/22/2004 1:13:08 PM by Hallonquist, Nora E.
2005 SROU/SROI L'
15 inches gssy e f;J -
- c. -30inches Incorrect - < -19"
- d. -45 inches Incorrect - < -19" Correct Response - Min steam cooling (-
19**)
Ouestion No. 74 Exam Bank Question No.: 5968 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-622 Objective: CRO la Question Level: Fundamen tal KnowledgelMemory Select the correct answer:
Given the following conditions:
A LOCA has occurred Only one RHR pump is injecting at 5500 gpm Which of the following is the MINIMUM RPV level where adequate core cooling can be assured?
I a. I + 15 inches I Incorrect - Not minimum level I
References:
EOP Study Guide (Definitions)
Source: VY Exam Bank Required Student
References:
None SRO
Reference:
None Task Associations I/
1, 3
During an Off Normal Event Knowledge and Abilities Associations Static Simulator Exams: None Last Revised: 12/22/2004 1: 1250 PM by Hallonquist, Nora E.
2005 SROU/SROI Question No. 75 Exam Bank Question No.: 5969 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-900 Objective: CRO 3 Question Level: Fundamen tal Knowledge/Memory
/**!E**
Select the correct answer:
A Site Area Emergency has been declared.
Two hours later, which one of the following Ec
Coordinator
References:
VY E-Plan Source: New Required Student
References:
None SRO
Reference:
None Incorrect - In a Site Area Emergency, the plant's emergency response facilities are manned within an hour. The SRM assumes overall responsibility when the EOF is activated.
Incorrect - In a Site Area Emergency, the plant's emergency response facilities are manned within an hour. The SRM assumes overall responsibility when the EOF is activated.
Incorrect - In a Site Area Emergency, the plant's emergency response facilities are manned within an hour. The SRM assumes overall responsibility when the EOF is activated.
Correct Response - In a Site Area Emergency, the plant's emergency response facilities are manned within an hour. The SRM assumes overall responsibility when the EOF is activated.
Task Associations 3447080302/0 Assume Duties of Plant Emergency Director
'W 3
Static Simulator Exams: None Last Revised: 12/22/2004 1: 12:29 PM by Hallonquist, Nora E.
v 2005 SROU/SROI Ouestion No. 76 Exam Bank Question No.: 5984 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-276 Objective: SRO 3,4 Question Level: Comprehension Select the correct answer:
During operation at 100% power the following conditions exist:
SERV WTR STRN A AP HI (6-A-6)
SERV WTR STRN B AP HI (6-A-7)
Service water pressure is 70 psig A 0 reports A/B service water strainer D/P are 12 and 15 psid respectively Based on the existing conditions, determine the required action.
References:
ON 3148, Step 5.b Source: New Required Student
References:
None SRO
Reference:
10CFR55.43.b.5; 1 OCF~55.43
.b.2 Task Associations t., l',T 2000300501 Respond to a Loss of Service Water L
COMPONENT COOLING WATERiCFR 41.10.43.5.
145.13): Cause for Dartial or comdete loss Static Simulator Exams: None Last Revised: 12/22/2004 12:18:42 PM by Hallonquist, Nora E.
2005 SROU/SROI Question No. 77 Exam Bank Question No.: 5881 Revision: 6 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-601 Objective: SRO 7 Question Level: Comprehension Select the correct answer:
At approximately 20% power during startup and power ascension, Control Room annunciators alarmed, including the following:
6-D-1 INST AIR HDR PRESSURE LO 5-E-2 FW VLV LOCKUP SIGNAUAIR FAIL The power ascension was immediately halted, and the following conditions have been reported:
Reactor level is slowly lowering Scram Air Header pressure is 70 psig and stable Which of the following describes the required actions and the reason for those actions?
- a. Override SA-PCV-1 closed after making an announcement over the Gai-tronics page. Service air supplies any respirators in use.
Control rods are expected to drift at this in-service FWRV has locked up.
reactor level. The in-service FWRV has locked up.
Incorrect - SA-PCV-1 begins to automatically close at 85 psig and should be fully closed at 80 psig.
Incorrect - If the Scram Air Header
~
pressure drops to less than 55 psig, then scram the reactor and enter OT 3 100.
Correct Response - If level is unexpectedly decreasing and the FRVs are locked up then insert a scram.
Incorrect - The aux FWRV will fail closed on loss of air; additionally, it is only 10%
capacity, and there is no procedural direction for this action.
References:
ON 3146 Source: VY Exam Bank Required Student
References:
None SRO
Reference:
10CFR55.43.b.5
-4 Task Associations
L 2000330501 Respond to a Reactor SCRAM Ability to explain and apply system limits and precautions (CFR 41.10,43.2,45.12)
Static Simulator Exams: None Last Revised: 12/22/2004 1:01:58 PM by Hallonquist, Nora E.
2005 SROU/SROI J"
295021 Question No. 78 Exam Bank Question No.: 5932 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-601 Objective: SRO 8 Question Level: Comprehension Select the correct answer:
AA2.06 Ability to determine andor interpret the following as they 3.2 3.3 apply to LOSS OF SHUTDOWN COOLING:(CFR 41.10, 43.5,45.13): Reactor pressure With the Rx Shutdown and a cooldown in progress for a Refueling Outage, shutdown cooling was established on the "A" Loop of RHR. Shortly after shutdown cooling was established, Rx Pressure spiked at 170 psig and returned to 80 psig.
For these conditions, state required action(s):
I c. I CRD and RWCU should be used to Incorrect - A feed and bleed is used after head on. Rx Vessel Head is in place
References:
ON 3156 Part B Source: New Required Student
References:
None SRO
Reference:
lOCmR55.43.b.5 Task Associations 2000150501 Respond to a Loss of Shutdown Cooling Static Simulator Exams: None Last Revised: 12/22/2004 1:22:45 PM by Hallonquist, Nora E.
L L
- d.
2005 SROU/SROI MSIV 86A can be reopened.
Core Thermal Limits are suspect & MSIV Question No. 79 Exam Bank Question No.: 5992 Revision: 5 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-604 Objective: SRO 6 Question Level: Fundamental Knowledge/Memory Select the correct answer:
During a Rx Startup at = 60% power, a spurious MSIV closure (MSIV 86A) causes a high pressure condition.
The current plant conditions are:
Rx pressure 990 psig Steam flow 4.7 x lo6 lbs/hr At this point:
indefinite period of time.
and MSIV 86A must be reopened within 2 power must be reduced to < 25% before 86A should be reopened within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or power shall be reduced to < 25% in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Correct Response - The old standard called for a power reduction or MSIVs must be reopened within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. A recent analysis at the end of 2004 allows us to maintain Dower.
Incorrect - Thermal Limits are valid indefinitely if < 4.8 x 10E6 lbshr Incorrect - MSIVs may be reopened at current power level Incorrect - An old standard that no longer applies
References:
OT 31 15, Note after Step 4a Source: New Required Student
References:
None SRO
Reference:
10CFR55.43.b.5 Task Associations 2000180501 Respond to High Reactor Pressure
295025 Static Simulator Exams: None Last Revised: 12/22/2004 1:23:11 PM by Hallonquist, Nora E.
EA2.01 Ability to determine and/or interpret the following as they 4.3 4.3 apply to HIGH REACTOR PRESSURE:(CFFt 41.10,43.5, 45.13).: Reactor pressure
J
- b.
- c.
2005 SROU/SROI Minor Modification (MM); six Temporary Modification (TM); twelve Incorrect - TM is correct per AP 0020 Incorrect - TM is correct but review must
- d.
Question No. 80 Exam Bank Question No.: 5690 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-402 Objective: SRO 2, 3 Question Level: Fundamental KnowledgeMemory Select the correct answer:
Minor Modification (MM); twelve Incorrect - Minor Mod is not appropriate per definition of Temp Mod in AP 0020 Due to a temperature switch that has failed high, the Torus Trouble annunciator (5-F-5) is in constant alarm and has been disabled. It is anticipated the annunciator will remain disabled for 15 months until the next refueling outage.
This will require a to be written and also require the first PORC review after months.
I I
I be comdete within 6 months I
References:
AP 0020; OP 3 140 Discussion Section Source: 2003 VY NRC Exam Required Student
References:
None SRO
Reference:
-Pkisu
\\ O C W ~ S,
y3,5, 3 Task Associations 34101 10302/0 Approve Temporary Modifications 3
Knowledge of the process used to track inoperable alarms (CFR 41.10.43.5.45.13)
Static Simulator Exams: None Last Revised: 12/22/2004 1:23:25 PM by Hallonquist, Nora E.
2005 SROU/SROI
/.
Question No. 81 Exam Bank Question No.: 5935 Revision: 4 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-900 Objective: SRO 4,5 Question Level: Comprehension Select the correct answer:
A plant transient has occurred resulting in Rx Water Level < -48" for a sustained period of time.
Select the answer which correctly describes the requirements and methods for notifying on-shift and off-shift plant personnel.
L All on-shift and off-shift personnel will receive initial notification of the event via the Emergency Plan pagers.
All on-shift personnel will be notified via plant Gaitronics, no Emergency Plan pager activation for off-shift personnel is necessary.
All on-shift personnel are notified via plant paging system, only the DCO is notified via Emergency Plan pagers.
All on-shift personnel are notified via Gaitronics announcement, all Emergency Plan responders are notified via Emergency Plan pagers.
Incorrect - On-shift personnel will receive initial notification via plant pager system.
Incorrect - Pager activation is required f o r declaration fo SAE.
Incorrect - Full E-Plan activation will occur for SAE.
Correct Response - OP 3504 & OP 3540 outline the initial plant page for on-shift personnel and then directs Security to activate E-Plan Dagers.
References:
OP 3531; OP 3540; OP 3547; EAL Bases Source: New Required Student
References:
Reference:
10CFR55.43.b.5 Task Associations t, 4 3447080302/0 Assume Duties of Plant Emergency Director 3
Knowledge and Abilities Associations I notification of plant personnel (CFR 43.5,45.i2) rri
Static Simulator Exams: None Last Revised: 12/22/2004 1:21:47 PM by Hallonquist, Nora E.
c
2005 SROU/SROI 600000 Ouestion No. 82 Exam Bank Question No.: 5998 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-602 Objective: SRO 10 Question Level: Comprehension Select the correct answer:
AA2.13 Ability to determine and/or interpret the following as they 3.2 3.8 apply to PLANT FIRE ON SITE:: Need for emergency dant shutdown During 100% power operations a spill of flamable liquids in the RB causes a severe fire in the Southeast Comer room.
At 1200, Fire Brigade commander responds to the scene and reports heavy fire and smoke throughout RB 213 and 232 Southeast.
At 1215, Fire Brigade commander reports fire crews are entering the area to attempt fire suppression.
Based on the above scenario, the required actions are:
- a. Commence normal Reactor Shutdown and commence a cooldown at 80-100"Fhr
- b. Insert a Rx Scram and RPV-ED
\\/
Reduce power to < 25% and transfer cooldown at 80-100"Fhr
References:
OP 3020 Source: New nun scram require Incorrect - RPV-ED criteria not reached Incorrect - > 10 min scram required I
Correct Response - > 10 min Required Student
References:
OP 3020 Flow Chart SRO
Reference:
10CFR55.43.b.5 Task Associations 3440 140302/0 Coordinate Response to a Fire Emergency 3
L Static Simulator Exams: None Last Revised: 12/22/2004 2: 19:49 PM by Hallonquist, Nora E.
2005 SROU/SROI
- a.
- b.
Question No. 83 Exam Bank Question No.: 5937 Revision: 4 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-402 Objective: SRO 1 Question Level: Fundamental KnowledgeMemory Select the correct answer:
a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> reportable event ONLY.
Incorrect - A valid actuation of ECCS systems meets criteria for an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> report Incorrect - Declaration of an emergency class of the Emergency Plan meets criteria
[50.72(b)(3)(iv)(A)I an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reportable event ONLY.
During startup from a refueling outage, the plant experiences a LOCA and a loss of normal power resulting in the following conditions:
- c.
Drywell pressure is 4 psig and steady Reactor pressure is being maintained between 800 and 1000 psig using SRVs The lowest reactor level obtained was 95 inches RCIC and HPCI did not start automatically RCIC was manually started for level control and level has been stabilized for a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> notification [50.72(a)(l)(I)]
Incorrect - Event should have resulted in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reportable events only.
Concerning notification to the NRC Operations Center, this event meets the conditions for ECCS discharge into the reactor coolant system (HPCI), meeting criteria for a 4
References:
EAL Bases Source: New Required Student
References:
Reference:
10CFR55.43.b.5 Task Associations c 3440390302/0 Perform Required Notifications of On Site and Off Site Personnel for Off
3 Normal Events d
(CFR 43.5.45.11)
Static Simulator Exams: None Last Revised: 12/22/2004 1:23:37 PM by Hallonquist, Nora E.
W 2005 SROU/SROI Question No. 84 Exam Bank Question No.: 5999 Revision: 0 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-610 Objective: SRO 3 Question Level: Comprehension Select the correct answer:
During single loop operations, the Running Recirc pump controller fails high and the pump subsequently trips. The Reactor Operator reports a failure of a Manual Reactor Scram and the following plant conditions:
All Rods not inserted Reactor power oscillating between 10% and 45% power Reactor pressure 950#, controlled by Turbine Bypass Valves Torus temp 85°F and steady Scram Air Header pressure O#
Reactor water level is 88" and steady Based on the above conditions, identify the required action(s):
.A and maintain until level irrespective of Torus water temDerature Insert Control Rods with Appendix D of IC* I OE 3107
< 20%
References:
EOP-2 Source: New Required Student
References:
Reference:
10CFR55.43. b.5 Correct Response - Boron required for Dower swings > 25%
Incorrect - Scram air header @ 0 psig Incorrect - No criteria for T & P Task Associations 3 101090502/0 Direct Boron Injection IAW EOP-2 3
u
I 295014 12.1.06 I Ability to supervise and assume a management role during 12.1 14.3 I plant transients and-upset conditions (CFR 43.5,45.12, 145.13, l
l Static Simulator Exams: None Last Revised: 12/22/2004 1:20:52 PM by Hallonquist, Nora E.
2005 SROU/SROI J
Ouestion No. 85 Exam Bank Question No.: 5987 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-611 Objective: SRO 3 Question Level: Comprehension Select the correct answer:
- b.
A Torus rupture occurs resulting in the following conditions:
Enter EOP-1, initiate an RPV-ED 13 inches of water in the RCIC Room 14 inches of water in Torus Area 5 inches of water in HPCI Room Determine the required action after entering EOP-4.
- c. I Enter EOP-1, initiate action to anticipate Incorrect - No scram or RPV-ED is required Incorrect - No scram or RPV-ED is required Correct Response - Per EOP-4, since it is not a primary system but there are 2 areas affected. a shutdown is reauired
References:
EOP-4 Source: VY Exam Bank Required Student
References:
Reference:
10CFR55.43.b.5 Changed from an RO question to an SRO question Task Associations 3 105050502/0 Direct the Response to Unexpected area Water Level above 1 Inch 3
I 295036 I EA2.02 I Ability to determine and/or interpret the following as they I 3.1 I 3.1 I
i/
Static Simulator Exams: None Last Revised: 12/22/2004 1: 19:35 PM by Hallonquist, Nora E.
apply to SECONDARY CONTAINMENT HIGH SUMP /
AREA WATER LEVEL:(CFR 41.10,43.5,45.13).: Water level in the affected area
c 2005 SROU/SROI J
Question No, 86 Exam Bank Question No.: 2524 Revision: 4 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-607 Objective: SRO 2,3 Question Level: Comprehension The following plant conditions exist:
RPV level is -10 inches (steady)
RPV Press is 850 (steady)
Torus level is 6.8 ft (decreasing)
Rx Power is on Range 4 of IRMs Torus Temp is 155°F HPCI is injecting RCIC is injecting SLC is injecting SLC tank level is 70%
Identify the required action(s)?
- a. -
- b.
RPVED only Initiate a cooldown Anticipate an RPV-ED RPV-ED. CSB not injected. C/D not permitted Incorrect - Anticipate an RPV-ED not C.
References:
EOP-3, Steps PC/L-7,8 Source: VY Exam Bank Required Student
Reference:
Reference:
10CFR55.43.b.5 Task Associations 2000240501 Respond to Low Torus Water Level u I 206000 12.4.06 I Knowledge symptom based EOP mitigation strategies 13.1 14.0 I
Static Simulator Exams: None Last Revised: 12/22/2004 1:18:37 PM by Hallonquist, Nora E.
2005 SROU/SROI Question No. 87 Exam Bank Question No.: 5982 Revision: 4 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-610 Objective: SRO 3 Question Level: Comprehension Select the correct answer:
An ATWS condition exists and EOP-2 is being implemented with the following conditions:
Bus 8 tripped due to bus fault
.A' CRD pump is tagged out Torus temperature is 108°F and rising Reactor power is 3%
RPV Level is +5" When the CRO attempted to inject SLC:
'A' SLC pump did not start
'A' squib valve light remained lit throughout the SLC switch manipulation What procedure direction should be implemented to inject SLC?
Direct Appendix I, Alternate SLC Initiation, bypassing the SLC Initiation Direct Appendix I, Alternate SLC Initiation, fire 'A' squib and start 'A' pump from the control room.
Direct Appendix J, Boron Injection Using RWCU.
Direct Appendix K, Boron Injection Using CRD System from SLC Tank.
3107 Appendix I
References:
None SRO
Reference:
10CFR55.43.b.5 Task Associations Correct Response - Switch failed, 'A' pump available from Bus 9 malfunction Incorrect - Equipment referenced is inappropriate due to loss of Bus 8 Incorrect - No CRD pumps available. 'A' CRD tagged out, 'B' CRD pump powered from Bus 8.
3 102080502/0 Direct Alternate Injection Using SLC Test Tank L
3 Knowledge and Abilities Associations 41.10.43.5.45.13)
Static Simulator Exams: None Last Revised: 12/22/2004 1:18:20 PM by Hallonquist, Nora E.
L-2005 SROU/SROI u
- d**********************************************************
215005 A2.06 Ability to (a) predict the impacts of the following on the 3.4 3.5 AVERAGE POWER RANGE MONITORLOCAL Question No. 88 Exam Bank Question No.: 5994 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-05-215 Objective: SRO 1 Question Level: Comprehension Select the correct answer:
Given the following conditions:
9 Rx Power at 100%
"B" APRM bypassed for maintenance APRM Flow Bias Off Normal Alarm (5-M-5) is alarming Flow signals for APRM A, C, E all read 125%
Red light for Hi Flow or Recirc Flow Converter "A" is lib Select the required action(s):
Insert a 1/2 scram on RPS "A" only
- d. Insert a 1/2 scram on RPS "A" and reduce power to the IRM range in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
References:
ARS 5-M-5 Source: New Required Student
References:
T.S. Table 3.1.1 SRO
Reference:
10CFR55.43.b.2 Task Associations Incorrect - 1/2 scram is correct but no shutdown is required per T.S. 3.1 Incorrect - Must insert 112 scram, no power reduction necessary Correct Response - T.S. 3.1.1 specifies actions necessarv Incorrect - 1/2 scram required, but no power reduction necessary 34 10320302/0 Evaluate Plant System Performance and Coordinate Appropriate Actions 3
per Technical Specifications/TRWODCM in the Event A Limiting Condition for Operation is Entered or not Satisfied
L' L POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR 41.5 / 45.6): Recirculation flow channels upscale Static Simulator Exams: None Last Revised: 12/22/2004 1:17:20 PM by Hallonquist, Nora E.
J 2005 SROU/SROI Question No. 89 Exam Bank Question No.: 3901 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-601 Objective: SRO 10 Question Level: Comprehension Select the correct answer:
The following plant conditions exist:
Group 1 isolation and reactor scram occurred RPV pressure is 1020 psig and rising During cycling of the SRVs, predict the response if the SRV discharge line 10-inch vacuum breaker fails open and determine what procedures should be implemented to mitigate the transient.
rapidly. DW pressure will lead torus pressure. Enter EOP-3 and direct torus and
- b. Torus air space temperature will rise rapidly. DW pressure will lag torus pressure. Enter EOP-3 and direct torus smav onlv.
Drywell temperature will rise rapidly. DW pressure will lead torus pressure. Enter ag torus pressure.
Incorrect - Discharges to DW air space, not torus Incorrect - Discharges to DW air space, not I torus Correct Response - DW air space temp discharge. DW will lead torus like a recirc break.
Incorrect - DW pressure will lead torus pressure
References:
EOP-3, Primary Containment Control; LOT-00-218 TP la Source: New Required Student
References:
None SRO
Reference:
10CFR55.43.b.5 Task Associations 2000210501 Respond to High Drywell Temperature Knowledge and Abilities Associations
A2.01 Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, use procedures to correct, control, or mitigate the ocnsequences of those abnormal conditions or operations: (CFR 41.5 / 45.6): Stuck open vacuum breakers Static Simulator Exams: None Last Revised: 12/22/2004 1:01:36 PM by Hallonquist, Nora E.
3.O 3.3
2005 SROU/SROI 1
Question No. 90 Exam Bank Question No.: 6000 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-01-262 Objective: SRO 7 Question Level: Fundamental KnowledgeMemory Select the correct answer:
The plant is at 100% power when the following occurs:
A fault causes breaker 88 to trip open Bus 8 is cross-tied to Bus 9 The CRS must declare signal occurrs, breakers 8T9 and 9T8 diesel(s) inoperable. If an LNP coincident with a LOCA load shed.
I b. I "A" only; will not Correct Response - 8T9 and 9T8 will not load shed OP 2143 Precaution 2g. Both D/Gs are declared inoperable due to load,
analysis per OP 2143 Section N and Appendix C 1
~~~~
~
1 Incorrect - Both D/Gs are declared inoperable due to load analysis Incorrect - 8T9 and 9T8 will not load shed OP 2143 Precaution 2g Incorrect - 8T9 and 9T8 will not load shed OP 2143 Precaution 2g
- c. both; will
- d. "A" only; will
References:
OP 2143 Source: New Required Student
References:
None SRO
Reference:
10CFR55.43.b.2 Task Associations 3410330302/0 Evaluate Plant Conditions and Coordinate Appropriate Actions per Plant 3
Technical Specifications/TRM/ODCM in the Event a Limiting Safety System Setting is reached and/or exceeded
EMERGENCY GENERATORS (DIESEUJET); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or oDerations: (CFR 41.5 / 45.6): LOCA Static Simulator Exams: None Last Revised: 12/22/2004 1:04:20 PM by Hallonquist, Nora E.
L 2005 SROU/SROI Question No. 91 Exam Bank Question No.: 5995 Revision: 4 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-601 Objective: SRO 10 Question Level: Comprehension Select the correct answer:
Upon completion of a forced outage, Control Rod Withdrawal has commenced using Control Rod Sequence A2.
When Control Rod 14-35 is being withdrawn, annunciator (5-D-6), Rod Select Block Timer Malfunction, is received.
Control Rod 14-35 position is verified stopped at position 08.
Which of the following identifies the required action(s) in response to the above condition?
Y kXz&$S 5-D-6 Re ire Stu nt
References:
None SR Refe nce: 10CFR55.43.b.6 Task Associations u
REACTOR MANUAL CONTROL SYSTEM: and cb)
L based on theose predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR 41.5 / 45.6): Select block Static Simulator Exams: None Last Revised: 12/22/2004 1:00:43 PM by Hallonquist, Nora E.
v 2005 SROU/SROI withdraw, the ball valve will close, and the automatic actions verified per DP 0166.
of power to the TIP machine. DP 0166 does direct verification of automatic ac ti ons.
Question No. 92 Exam Bank Question No.: 237 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-04-215 Objective: SRO 1 Question Level: Comprehension Select the correct answer:
The Traversing In-Core Probe (TIP) is inserted into the core for a full core Local Power Range Monitor (LPRM) calibration when the following occurs:
DW pressure is slowly increasing due to a small leak A loss of Vital AC occurs A manual scram is inserted due to the inability to restore Vital AC DW pressure is 3.2 psig The SM has determined he wants the primary containment isolated Predict the impact on the TIP system and the procedural direction that should be implemented to achieve primary containment isolation.
and they must be manually withdrawn and
References:
OP 21 15; OP 2144; OP 2145 Source: New Required Student
References:
None SRO
Reference:
10CFR55.43.b.5
Task Associations 3 100020502/0 Verify PCIS Isolations 3
L 215001 A2.07 I Ability to (a) predict the impacts of the following on the I 3.4 I 3.7 I
_L TRAVERSING IN-CORE PROBE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR 41.5/ 45.6): Failure to retract during accident conditions: Mark-I&II (Not-BWRl)
Static Simulator Exams: None Last Revised: 12/22/2004 1:16:41 PM by Hallonquist, Nora E.
L-2005 SROU/SROI Question No. 93 Exam Bank Question No.: 5956 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-400 Objective: SRO 12 Question Level: Fundamental KnowledgeMemory Select the correct answer:
The plant is operating at power. An "A" RHR LCO period is scheduled in three weeks.
The online work management process for this LCO period is on schedule.
As the Operations SRO on the Work Management Team, reviewing the schedule at T-3, all of the activities are completed EXCEPT:
I a. I Freeze work scope I b. I Initiate clearance request Incorrect - Should be completed by T-6 week Incorrect - Should be completed by T-5 week Correct Response - Completed by T-2 week uer EN-NM-101 Section 5.4 Incorrect - Should be completed by T-12 week
References:
EN-NM-101 Section 5.4 Source: New Required Student
References:
None SRO
Reference:
10CFR55.43.b.3 Task Associations 3420080302/0 Authorize Performance of Maintenance on Shift (Including Preventive 3
Maintenance) 226001 12.2.17 I Knowledge of the process for managing maintenance activities during Dower ouerations (CFR 43.5.45.13)
Static Simulator Exams: None Last Revised: 12/22/2004 12:49:30 PM by Hallonquist, Nora E.
2005 SROU/SROI 0
Question No. 94 Exam Bank Question No.: 5997 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-01-400 Objective: SRO 1 Question Level: Fundamental KnowledgeMemory 2.1.13 Knowledge of facility requirements for controlling vital /
2.0 2.9 controlled access (CFR 41.10,43.5,45.9,45.10)
Select the correct answer:
An RO normally assigned to your shift has been temporarily assigned to Training to complete a Task Analysis. His last plant access was 35 days ago.
What is required to restore site access and stand watch?
disclosure statement
References:
EN-NS-101 Source: New Required Student
References:
None SRO
Reference:
10CFR55.43.b.l Task Associations 1 Tag 3430060302/0 Call in Additional Personnel, as Necessary 3
Static Simulator Exams: None Last Revised: 12/22/2004 1:15:20 PM by Hallonquist, Nora E.
2005 SROU/SROI Question No. 95 Exam Bank Question No.: 5960 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-308 Objective: SRO 1 Question Level: Comprehension Select the correct answer:
It is 0200 during normal full power operation. The Control Room Supervisor's (CRS's) wife calls to tell him that she has gone into labor and that she must get to the hospital.
- At 0205 the CRS departs as directed by the Shift Manager (SM).
- At 0210 the SM calls the Operations Manager to inform him of the reduction in crew composition.
- At 0220 the SM reaches a relief for the CRS and directs him to come to work.
- At 0415 the CRS relief arrives and completes a turnover with the SM.
Which of the following is correct concerning the operating crew's compliance with the shift crew composition requirements?
The CRS position should have been manned by a relief within two hours of the CRS's departure.
The operating crew has complied fully with shift manning reauirements.
The CRS is not allowed to leave until the Operation Manager's permission is obtained.
The CRS is not allowed to leave until his relief has arrived and has been briefed.
Correct Response - T.S. 6.2.B.4 allows a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> window for emergency Incorrect - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> were exceeded Incorrect - Operation Manager needs to be notified only Incorrect - T.S. allow 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> window
References:
T.S. 6.2.B.4 Source: Monticello 2002 NRC Exam Required Student
References:
None SRO
Reference:
10CFR55.43.b.2 Task Associations 3430060302/0 Call in Additional Personnel, as Necessary 3
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Knowledge and Abilities Associations
L, I 2.1.04 I Knowledge of shift staffing requirements (CFR 41.10, I 2.3 I 3.4 I
143.2)
Static Simulator Exams: None Last Revised: 12/22/2004 1:15:05 PM by Hallonquist, Nora E.
2005 SROU/SROI Ouestion No. 96 Exam Bank Question No.: 5963 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-402 Objective: SRO 15 Question Level: Comprehension Select the correct answer:
During the performance of the Core Spray Pump Operability Quarterly Surveillance OP 4123, the system engineer wants to perform a test to assess the minimum flow valve.
The test will involve cycling the MINIMUM FLOW CS-5B with FULL FLOW TEST CS-26B OPEN, and talung some readings on discharge pressure and system flow.
The surveillance is scheduled for next week.
A LPC should be used with 10CFR50.59 screening/evaluation performed
- b. preapproved; within 14 days of imdementation of the LPC provisional; before the test implementation of the LPC Correct Response - Sufficient time exists and the change is an intent change.
Preapproved LPCs require 50.59 screening/evaluation before implementation (AP 0097 4.1.1 VYAPF 0097.0 1)
Incorrect - 50.59 screening/evaluation before imtAementation Incorrect - Intent change, sufficient time exists Incorrect - Intent change, sufficient time exists, 50.59 screening/evaluation before implementation
References:
AP 0097, Section 4.1.1 and 4.1.2; ENN-LI-100; ENN-LI-101 Source: New Required Student
References:
None SRO
Reference:
1 OCFR55.43.b.3 Task Associations 3437030302/0 Submit Partial Change to Plant Procedures
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3
experiments not described in the safety analysis report (CFR 43.3.45.13)
Static Simulator Exams: None Last Revised: 12/22/2004 12:54:40 PM by Hallonquist, Nora E.
2005 SROU/SROI
- a.
- b.
Question No. 97 Exam Bank Question No.: 5964 Revision: 4 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-402 Objective: SRO 5e Question Level: Comprehension Select the correct answer:
stop work and recommence after a barrier breach permit is completed and approved.
continue work, activities governed by a T/S WO do not require a barrier breach Demit.
During implementation of an approved troubleshooting work order (T/S WO) it becomes evident that it is necessary to breach the secondary containment. The required course of action is to:
0 2.2.20 Knowledge of the process for managing troubleshooting 2.2 3.3 activities (CFR 43.5,45.13) stop work and generate a planned Work Order or rescope the T/S WO including
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barrier breach permit.
complete a barrier breach permit in parallel with the T/S WO activitv.
Incorrect - Work that requires a barrier breach permit can not be done under a trouble shooting work order.
Incorrect - Any work that breaches Secondary Containment requires a barrier breach permit.
Correct Response - Work that requires a barrier breach permit will need to be done as a planned work order. Breaching the Secondary Containment requires a barrier breach permit.
Incorrect - Work that requires a barrier breach permit can not be done under a trouble shooting work order.
References:
AP 0050 Source: New Required Student
References:
None SRO
Reference:
10CFR55.43.b.3 Task Associations I
3420070302/0 Review Work Order Requests 3
L, Static Simulator Exams: None
Last Revised: 12/22/2004 1255: 14 PM by Hallonquist, Nora E.
2005 SROUISROI v
Question No. 98 Exam Bank Question No.: 5967 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-404 Objective: SRO 5 Question Level: Fundamental Knowledgeklemory Select the correct answer:
During a refuel outage, what are the ALARA related restrictions placed on Drywell access while fuel movements are underway?
elevations, direct communications must be to upper elevations established between refuel floor and DW Checkpoint.
Direct communications must be established between refuel floor and DW Checkpoint and all access to DW is prohibited.
Drywell upper elevations must be barricaded to prevent access above upper elevations and an RP tech MUST accompany any personnel entering in the drywell.
Incorrect - Access is restricted to upper elevations only Incorrect - RP escort not required for DW entry
References:
AP 0518, Prereq 2, Step e Source: New Required Student
References:
None SRO
Reference:
10CFR55.43.b.4; 10CFR55.43.b.7 Task Associations 3410290302/0 Supervise Refueling Operations as SRO on Refuel Floor 3
Knowledge and Abilities Associations
145.9.45.10)
Static Simulator Exams: None Last Revised: 12/22/2004 125651 PM by Hallonquist, Nora E.
I
2005 SROU/SROI Ouestion No. 99 Exam Bank Question No.: 6001 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-03-400 Objective: SRO 1 Question Level: Fundamental Knowledge/Memory Select the correct answer:
While operating at power, a service water rupture in the reactor building has occurred. During implementation of procedures, the following directions conflict:
OP 2181 - secure all SW pumps ON 3 148 - manually scram the reactor, reduce SW pumps operating to two EOP complete Reactor Shutdown per OP 0105 ARS (6-A-5) SERV WTR HDR PRESS LO - start all SW pumps, perform Reactor Shutdown What action should be implemented? Why?
References:
ON 3 148; EOP-4 Source: New Required Student
References:
None SRO
Reference:
10CFR55.43.b.5 Task Associations 3430410302/0 Evaluate the Adequacy of Procedures to Ensure Safe Operations 3
0 Knowledge of the organization of the operating procedures 2.9 network for normal, abnormal, and emergency evolutions (CFR 41.10,43.5,45.13) 2.4.05 3.6 Static Simulator Exams: None Last Revised: 12/22/2004 12:58:45 PM by Hallonquist, Nora E.
L 2005 SROU/SROI Question No. 100 Exam Bank Question No.: 5970 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-900 Objective: SRO 2 Question Level: Comprehension Select the correct answer:
During a REFUELING OUTAGE with refueling in progress, the plant experiences an electrical transient with the following conditions:
LOSS of DC-3A Loss of annunciators on 9-3,9-4,9-5,9-6,9-7,9-8 Loss of ERFISDAS Conditions have existed for 15 minutes What is the correct classification per AP 3 125?
No emergency classification exist transient also to be correct for Modes 1,2,
References:
AP 3 125 Source: New Required Student
References:
Reference:
10CFR55.43.b.5 Task Associations 3447040302/0 Implement Reporting Requirements of Emergency Plan as Directed 3
3447080302/0 Assume Duties of Plant Emergency Director 3
L-Static Simulator Exams: None Last Revised: 12/22/2004 1: 12: 11 PM by Hallonquist, Nora E.
0 2.4.32 Knowledge of operator response to loss of all annunciators 3.3 3.5 (CFR 41.10,43.5,45.13)