ML093240204
| ML093240204 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/19/2009 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| 2009-302, ES-401 | |
| Download: ML093240204 (91) | |
Text
ES-401 Site-Specific RO Written Examination Cover Sheet Form ES-401-7 U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date: November 12th, 2009 Facility/Unit: Plant E. I. Hatch Region:
I D II X III D IV D Reactor Type: W D CE D BW D GE X Start Time:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent ES-401 Site-Specific RO Written Examination Cover Sheet Form ES-401-7 U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date: November 12th, 2009 Facility/Unit: Plant E. I. Hatch Region:
I 0 II X III 0 IV 0 Reactor Type: W D CE D BW D GE X Start Time:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent
for Plant Hatch HLT 5 (2009-302) NRC RO Test Test Form: 0 Answers ID 1
201001K5.02 1 D
2 202001A3.04 1 B
3 202002K2.021 C
4 203000G2.1.31 1 B
5 204000G2.4.46 1 D
6 205000K5.03 1 D
7 206000K5.051 B
8 209001K1.09 1 D
9 209001K1.13 1 B
10 211000K4.03 1 C
11 212000A2.161 B
12 212000A2.191 A
13 214000K1.04 1 B
14 215003A1.04 1 A
15 215004K6.04 1 C
16 215005A1.04 1 B
17 215005A1.05 1 B
18 216000A2.10 1 B
19 217000K2.031 B
20 218000K1.06 1 D
21 223002K3.21 1 B
22 233000K4.06 1 A
23 234000K3.04 1 C
24 239002A3.051 D
25 241000A1.24 1 A
26 259002A4.03 1 B
27 259002K6.04 1 C
28 261000K3.01 1 B
29 261000K3.061 C
30 262001G2.2.44 1 D
31 262002A3.01 1 B
32 263000A2.01 1 C
33 264000K4.04 1 B
34 286000A4.051 C
35 290002K6.08 1 D
36 290003A1.04 1 D
37 295001K2.07 1 D
38 295003K1.04 1 B
39 295004G2.4.09 1 A
40 295005K3.07 1 C
41 295006A1.02 1 A
42 29501OA1.05 1 D
43 295013G2.4.01 1 B
44 295015A1.02 1 B
45 295016A2.061 B
46 295018K3.06 1 C
47 295019A2.02 1 A
48 295020A2.03 1 B
Wednesday, November 11,20092:26:33 PM 1
for Plant Hatch HLT 5 (2009-302) NRC RO Test Test Form: 0 Answers ID 0
1 201001K5.02 1 D
2 202001A3.04 1 B
3 202002K2.02 1 C
4 203000G2.1.311 B
5 204000G2.4.46 1 D
6 205000K5.03 1 D
7 206000K5.051 B
8 209001K1.09 1 D
9 209001K1.13 1 B
10 211000K4.03 1 C
11 212000A2.161 B
12 212000A2.191 A
13 214000K1.04 1 B
14 215003A1.04 1 A
15 215004K6.04 1 C
16 215005A1.04 1 B
17 215005A1.05 1 B
18 216000A2.1O 1 B
19 217000K2.03 1 B
20 218000K1.06 1 D
21 223002K3.21 1 B
22 233000K4.06 1 A
23 234000K3.04 1 C
24 239002A3.05 1 D
25 241000A1.241 A
26 259002A4.03 1 B
27 259002K6.04 1 C
28 261000K3.01 1 B
29 261000K3.06 1 C
30 262001G2.2.44 1 D
31 262002A3.01 1 B
32 263000A2.01 1 C
33 264000K4.04 1 B
34 286000A4.05 1 C
35 290002K6.081 D
36 290003A1.04 1 D
37 295001K2.07 1 D
38 295003K1.04 1 B
39 295004G2.4.09 1 A
40 295005K3.07 1 C
41 295006A1.02 1 A
42 295010A1.05 1 D
43 295013G2.4.01 1 B
44 295015A1.02 1 B
45 295016A2.06 1 B
46 295018K3.06 1 C
47 295019A2.02 1 A
48 295020A2.03 1 B
Wednesday, November 11,20092:26:33 PM 1
for Plant Hatch HLT 5 (2009-302) NRC RO Test Test Form: 0 Answers ID 49 295021G2.2.40 1 D
50 295023A1.04 1 D
51 295024A2.02 1 D
52 295025G2.1.23 1 B
53 295026K3.01 1 A
54 295028Al.03 1 C
55 295030K1.02 1 D
56 295031Al.05 1 C
57 295032Kl.02 1 A
58 295035K3.02 1 C
59 295037K2.07 1 B
60 295038K1.03 1 B
61 300000K6.07 1 D
62 400000K2.02 1 C
63 500000K2.06 1 D
64 600000K1.02 1 C
65 700000K2.07 1 A
66 G2.1.061 C
67 G2.1.081 B
68 G2.1.171 A
69 G2.2.011 D
70 G2.2.371 C
71 G2.2.441 B
72 G2.3.051 B
73 G2.3.131 B
74 G2.4.261 D
75 G2.4.491 C
Wednesday, November 11,20092:26:35 PM 2
for Plant Hatch HLT 5 (2009-302) NRC RO Test Test Form: 0 Answers ID 0
49 295021G2.2,40 1 D
50 295023A1.04 1 D
51 295024A2.02 1 D
52 295025G2.1.23 1 B
53 295026K3.01 1 A
54 295028A1.03 1 C
55 295030Kl.02 1 D
56 295031Al.05 1 C
57 295032Kl.02 1 A
58 295035K3.021 C
59 295037K2.07 1 B
60 295038K1.03 1 B
61 300000K6.07 1 D
62 400000K2.02 1 C
63 500000K2.06 1 D
64 600000K1.02 1 C
65 700000K2.07 1 A
66 G2.1.061 C
67 G2.1.081 B
68 G2.1.171 A
69 G2.2.011 D
70 G2.2.371 C
71 G2.2,441 B
72 G2.3.051 B
73 G2.3.13 1 B
74 G2.4.261 D
75 G2,4,491 C
Wednesday, November 11,20092:26:35 PM 2
RO Candidate List of Handouts for Written Exam Handout
- 1.
34AB-R42-001-0S, Page 2 (Section 4.0 Subsequent Operator Actions) and.
- 2.
Unit 2 EOP Graph 1, "RPV Saturation Temperature" and Graph 8 "Drywell Spray Initiation Limit"
- 3.
Unit 2 EOP Graph 17A, HPCI Pump NPSH Limit (Torus Water Level At or Above 146") Unit 2 EOP Graph 17B, HPCI Pump NPSH Limit (Torus Water Level Below 146")
- 4.
Unit 2, top section of 31 EO-PCG-001-2, PCGC.
RO Candidate List of Handouts for Written Exam Handout
- 1.
34AB-R42-001-0S, Page 2 (Section 4.0 Subsequent Operator Actions) and.
- 2.
Unit 2 EOP Graph 1, "RPV Saturation Temperature" and Graph 8 "Orywell Spray Initiation Limit"
- 3.
Unit 2 EOP Graph 17A, HPCI Pump NPSH Limit (Torus Water Level At or Above 146") Unit 2 EOP Graph 17B, HPCI Pump NPSH Limit (Torus Water Level Below 146")
- 4.
Unit 2, top section of 31 EO-PCG-001-2, PCGC.
SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
4.0 SUBSEQUENT OPERATOR ACTIONS PAGE 2 OF 11 DOCUMENT NUMBER: REVISION NO:
34AB-R42-001-0S 1 ED 2 4.1
!E ground is indicated on the Station Service batteries, determine the significance of the ground as follows:
4.1.1 Determine the magnitude of the ground using meter indication and Attachment 2.
125'250 VDC bus grounds are indicated on 112H11-P655 on Battery Grou nd Detection System meters (1/2R42-R613A and 1/2R42-R613B). Portion of battery bus with ground can be determined as follows:
Ground ON Switch Direction Of Section Position Meter Deflection P
1 Negative (-)
Page 6 2
Negative (-)
PN 1
Positive (+)
Page 8 2
Negative (-)
N 1
Positive (+)
Page 10 2
Positive (+)
4.1.2 IF ground is greater than 19000 ohms, PLACE the Ground Detection Sys Battery meter switch in the position which clears the alarm, AND exit this procedure.
A ground is determined by a resistance of $;19,0000 which is equivalent to current value outside of the range of +1.98 mA to -1.98 mA as determined on Attachment 2.
4.1.3
!E ground is less than 19000 ohms:
4.1.3.1
!E possible, PLACE the Ground Detection Sys Battery meter switch in the position which clears the alarm.
4.1.3.2 Locate the ground per the following subsections.
MGR-0001 Rev 2 SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
4.0 SUBSEQUENT OPERATOR ACTIONS PAGE 2 OF 11 DOCUMENT NUMBER: REVISION NO:
34AB-R42-001-0S 1 ED 2 4.1
!E ground is indicated on the Station Service batteries, determine the significance of the ground as follows:
4.1.1 Determine the magnitude of the ground using meter indication and Attachment 2.
125'250VDC bus grounds are indicated on 1t2H11-P655on Battery Ground Detection System meters (1/2R42-R613A and 1/2R42-R613B). Portion of battery bus with ground can be determined as follows:
Ground ON Switch Direction Of Section Position Meter Deflection P
1 NeQative (-)
Page 6 2
Negative (-)
PN 1
Positive (+)
Page 8 2
Negative (-)
N 1
Positive (+)
Page 10 2
Positive (+)
4.1.2 IF ground is greater than 19000 ohms, PLACE the Ground Detection Sys Battery meter switch in the position which clears the alarm, AND exit this procedure.
A ground is determined by a resistance of $;19,0000 which is equivalent to current value outside of the range of +1.98 rnA to -1.98 rnA as determined on Attachment 2.
4.1.3
!E ground is less than 19000 ohms:
4.1.3.1
!E possible, PLACE the Ground Detection Sys Battery meter switch in the position which clears the alarm.
4.1.3.2 Locate the ground per the following subsections.
MGR-0001 Rev 2
SOUTHERN NUCLEAR PLANT E.!. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT 2.
TITLE: GROUND FAULT DETERMINATION TABLE DOCUMENT NUMBER:
34AB-R42-001-0S PAGE 6 OF 11 REVISION NO:
1 ED 2 ATTACHMENT PAGE:
1 OF 6 The correlation's on this table correspond to readings expected for a single ground on the system. IF multiple grounds occur on the system, THEN the meter readings may not correspond to table values.
GROUND FAULT ON BUS P POTENTIOMETER RESISTANCE = 25,000 GROUND RESISTANCE IN OHMS o
1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 16000 17000 18000 19000 20000 21000 22000 23000 24000 25000 26000 27000 28000 29000 30000 MGR-0009 Rev 2 SWITCH POSITION 1 IG IN MILLIAMPS
-5.00
-4.63
-4.31
-4.03
-3.79
-3.57
-3.38
-3.21
-3.05
-2.91
-2.78
-2.66
-2.55
-2.45
-2.36
-2.27
-2.19
-2.12
-2.05
-1.98
-1.92
-1.87
-1.81
-1.76
-1.71
-1.67
-1.62
-1.58
-1.54
-1.51
-1.47 SWITCH POSITION 2 IG IN MILLIAMPS
-15.00
-13.89
-12.93
-12.10
-11.36
-10.71
-10.14
- 9.62
- 9.15
- 8.72
- 8.33
-7.98
-7.65
- 7.35
-7.08
- 6.82
- 6.58
- 6.36
- 6.15
- 5.95
- 5.77
- 5.60
-5.43
- 5.28
- 5.14
- 5.00
- 4.87
- 4.75
-4.63
- 4.52
- 4.41 SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT.1...
TITLE: GROUND FAULT DETERMINATION TABLE DOCUMENT NUMBER:
34AB-R42-001-0S PAGE 6 OF 11 REVISION NO:
1 ED 2 ATTACHMENT PAGE:
1 OF 6 The correlation's on this table correspond to readings expected for a single ground on the system. IF multiple grounds occur on the system, THEN the meter readings may not correspond to table values.
GROUND FAULT ON BUS P POTENTIOMETER RESISTANCE = 25,000 GROUND RESISTANCE IN OHMS o
1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 16000 17000 18000 19000 20000 21000 22000 23000 24000 25000 26000 27000 28000 29000 30000 MGR-0009 Rev 2 SWITCH POSITION 1 IG IN MILLIAMPS
-5.00
-4.63
-4.31
-4.03
-3.79
-3.57
-3.38
-3.21
-3.05
-2.91
-2.78
-2.66
-2.55
-2.45
-2.36
-2.27
-2.19
-2.12
-2.05
-1.98
-1.92
-1.87
-1.81
-1.76
-1.71
-1.67
-1.62
-1.58
-1.54
-1.51
-1.47 SWITCH POSITION 2 IG IN MILLIAMPS
-15.00
-13.89
-12.93
-12.10
-11.36
-10.71
-10.14
- 9.62
- 9.15
- 8.72
- 8.33
- 7.98
- 7.65
- 7.35
- 7.08
- 6.82
- 6.58
- 6.36
- 6.15
- 5.95
- 5.77
- 5.60
-5.43
- 5.28
- 5.14
- 5.00
- 4.87
- 4.75
- 4.63
- 4.52
- 4.41
SOUTHERN NUCLEAR PLANT E.!. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT 2..
DOCUMENT NUMBER:
34AB-R42-001-0S TITLE: GROUND FAULT DETERMINATION TABLE GROUND FAULT ON BUS P POTENTIOMETER RESISTANCE = 25,000 PAGE 7 OF 11 REVISION NO:
1 ED 2 ATTACHMENT PAGE:
20F6 GROUND RESISTANCE IN OHMS SWITCH POSITION 1 SWITCH POSITION 2 MGR-0009 Rev 2 31000 32000 33000 34000 35000 36000 37000 38000 39000 40000 41000 42000 43000 44000 45000 46000 47000 48000 49000 50000 IG IN MILLIAMPS
-1.44
-1.40
-1.37
-1.34
-1.32
-1.29
-1.26
-1.24
-1.21
-1.19
-1.17
-1.15
-1.13
-1.11
-1.09
-1.07
-1.05
-1.03
-1.02
-1.00 IG IN MILLIAMPS
-4.31
-4.21
-4.12
-4.03
-3.95
-3.87
-3.79
-3.71
-3.64
-3.57
-3.50
-3.44
-3.38
-3.32
-3.26
-3.21
-3.15
-3.10
-3.05
-3.00 SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT 2..
DOCUMENT NUMBER:
34AB-R42-001-0S TITLE: GROUND FAULT DETERMINATION TABLE GROUND FAULT ON BUS P POTENTIOMETER RESISTANCE = 25,000 PAGE 7 OF 11 REVISION NO:
1 ED 2 ATTACHMENT PAGE:
20F6 GROUND RESISTANCE IN OHMS SWITCH POSITION 1 SWITCH POSITION 2 MGR-0009 Rev 2 31000 32000 33000 34000 35000 36000 37000 38000 39000 40000 41000 42000 43000 44000 45000 46000 47000 48000 49000 50000 IG IN MILLIAMPS
-1.44
-1.40
-1.37
-1.34
-1.32
-1.29
-1.26
-1.24
-1.21
-1.19
-1.17
-1.15
-1.13
-1.11
-1.09
-1.07
-1.05
-1.03
-1.02
-1.00 IG IN MILLIAMPS
-4.31
-4.21
-4.12
-4.03
-3.95
-3.87
-3.79
-3.71
-3.64
-3.57
-3.50
-3.44
-3.38
-3.32
-3.26
-3.21
-3.15
-3.10
-3.05
-3.00
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT.£ DOCUMENT NUMBER:
34AB-R42-001-0S TITLE: GROUND FAULT DETERMINATION TABLE GROUND FAULT ON BUS PN POTENTIOMETER RESISTANCE = 25,000 PAGE 8 OF 11 REVISION NO:
1 ED 2 ATTACHMENT PAGE:
30F6 GROUND RESISTANCE IN OHMS SWITCH POSITION 1 SWITCH POSITION 2 IG IN MILLIAMPS IG IN MILLIAMPS o
+5.00
-5.00 1000
+4.63
-4.63 2000
+4.31
-4.31 3000
+4.03
-4.03 4000
+3.79
-3.79 5000
+3.57
-3.57 6000
+3.38
-3.38 7000
+3.21
-3.21 8000
+3.05
-3.05 9000
+2.91
-2.91 10000
+2.78
-2.78 11000
+2.66
-2.66 12000
+2.55
-2.55 13000
+2.45
-2.45 14000
+2.36
-2.36 15000
+2.27
-2.27 16000
+2.19
-2.19 17000
+2.12
-2.12 18000
+2.05
-2.05 19000
+1.98
-1.98 20000
+1.92
-1.92 21000
+1.87
-1.87 22000
+1.81
-1.81 23000
+1.76
-1.76 24000
+1.71
-1.71 25000
+1.67
-1.67 26000
+1.62
-1.62 27000
+1.58
-1.58 28000
+1.54
-1.54 29000
+1.51
-1.51 30000
+1.47
-1.47 31000
+1.44
-1.44 32000
+1.40
-1.40 33000
+1.37
-1.37 34000
+1.34
-1.34 35000
+1.32
-1.32 36000
+1.29
-1.29 37000
+1.26
-1.26 38000
+1.24
-1.24 39000
+1.21
-1.21 40000
+1.19
-1.19 MGR-0009 Rev 2 SOUTHERN NUCLEAR PLANT E.!. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT..£.
DOCUMENT NUMBER:
34AB-R42-001-0S TITLE: GROUND FAULT DETERMINATION TABLE GROUND FAULT ON BUS PN POTENTIOMETER RESISTANCE = 25,000 PAGE 8 OF 11 REVISION NO:
1 ED 2 ATTACHMENT PAGE:
30F6 GROUND RESISTANCE IN OHMS SWITCH POSITION 1 SWITCH POSITION 2 IG IN MILLIAMPS IG IN MILLIAMPS o
+5.00
-5.00 1000
+4.63
-4.63 2000
+4.31
-4.31 3000
+4.03
-4.03 4000
+3.79
-3.79 5000
+3.57
-3.57 6000
+3.38
-3.38 7000
+3.21
-3.21 8000
+3.05
-3.05 9000
+2.91
-2.91 10000
+2.78
-2.78 11000
+2.66
-2.66 12000
+2.55
-2.55 13000
+2.45
-2.45 14000
+2.36
-2.36 15000
+2.27
-2.27 16000
+2.19
-2.19 17000
+2.12
-2.12 18000
+2.05
-2.05 19000
+1.98
-1.98 20000
+1.92
-1.92 21000
+1.87
-1.87 22000
+1.81
-1.81 23000
+1.76
-1.76 24000
+1.71
-1.71 25000
+1.67
-1.67 26000
+1.62
-1.62 27000
+1.58
-1.58 28000
+1.54
-1.54 29000
+1.51
-1.51 30000
+1.47
-1.47 31000
+1.44
-1.44 32000
+1.40
-1.40 33000
+1.37
-1.37 34000
+1.34
-1.34 35000
+1.32
-1.32 36000
+1.29
-1.29 37000
+1.26
-1.26 38000
+1.24
-1.24 39000
+1.21
-1.21 40000
+1.19
-1.19 MGR-0009 Rev 2
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT.£ DOCUMENT NUMBER:
34AB-R42-001-0S TITLE: GROUND FAULT DETERMINATION TABLE GROUND FAULT ON BUS PN POTENTIOMETER RESISTANCE = 25,000 PAGE 9 OF 11 REVISION NO:
1 ED2 ATTACHMENT PAGE:
40F6 GROUND RESISTANCE IN OHMS SWITCH POSITION 1 SWITCH POSITION 2 MGR-0009 Rev 2 41000 42000 43000 44000 45000 46000 47000 48000 49000 50000 IG IN MILLIAMPS
+1.17
+1.15
+1.13
+1.11
+1.09
+1.07
+1.05
+1.03
+1.02
+1.00 IG IN MILLIAMPS
-1.17
-1.15
-1.13
-1.11
-1.09
-1.07
-1.05
-1.03
-1.02
-1.00 SOUTHERN NUCLEAR PLANT E.!. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT.l..
DOCUMENT NUMBER:
34AB-R42-001-0S TITLE: GROUND FAULT DETERMINATION TABLE GROUND FAULT ON BUS PN POTENTIOMETER RESISTANCE = 25,000 PAGE 9 OF 11 REVISION NO:
1 ED 2 ATTACHMENT PAGE:
40F6 GROUND RESISTANCE IN OHMS SWITCH POSITION 1 IG IN MILLIAMPS SWITCH POSITION 2 MGR-0009 Rev 2 41000 42000 43000 44000 45000 46000 47000 48000 49000 50000
+1.17
+1.15
+1.13
+1.11
+1.09
+1.07
+1.05
+1.03
+1.02
+1.00 IG IN MILLIAMPS
-1.17
-1.15
-1.13
-1.11
-1.09
-1.07
-1.05
-1.03
-1.02
-1.00
SOUTHERN NUCLEAR PLANT E.!. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT 2.
DOCUMENT NUMBER:
34AB-R42-00 i-OS TITLE: GROUND FAULT DETERMINATION TABLE GROUND FAULT ON BUS N POTENTIOMETER RESISTANCE = 25,000 PAGE 10 OF 11 REVISION NO:
1 ED 2 ATTACHMENT PAGE:
5 OF 6 GROUND RESISTANCE IN OHMS SWITCH POSITION 1 SWITCH POSITION 2 o
1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 16000 17000 18000 19000 20000 21000 22000 23000 24000 25000 26000 27000 28000 29000 30000 31000 32000 33000 34000 35000 36000 37000 38000 39000 MGR-0009 Rev 2 IG IN MILLIAMPS
+15.00
+13.89
+12.93
+12.10
+11.36
+10.71
+10.14
+ 9.62
+ 9.15
+ 8.72
+ 8.33
+ 7.98
+ 7.65
+ 7.35
+ 7.08
+ 6.82
+ 6.58
+ 6.36
+ 6.15
+ 5.95
+ 5.77
+ 5.60
+ 5.43
+ 5.28
+ 5.14
+ 5.00
+ 4.87
+ 4.75
+4.63
+ 4.52
+ 4.41
+ 4.31
+ 4.21
+ 4.12
+ 4.03
+ 3.95
+ 3.87
+ 3.79
+ 3.71
+ 3.64 IG IN MILLIAMPS
+5.00
+4.63
+4.31
+4.03
+3.79
+3.57
+3.38
+3.21
+3.05
+2.91
+2.78
+2.66
+2.55
+2.45
+2.36
+2.27
+2.19
+2.12
+2.05
+1.98
+1.92
+1.87
+1.81
+1.76
+1.71
+1.67
+1.62
+1.58
+1.54
+1.51
+1.47
+1.44
+1.40
+1.37
+1.34
+1.32
+1.29
+1.26
+1.24
+1.21 SOUTHERN NUCLEAR PLANT E.!. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT 2.
DOCUMENT NUMBER:
34AB-R42-001-0S TITLE: GROUND FAULT DETERMINATION TABLE GROUND FAULT ON BUS N POTENTIOMETER RESISTANCE = 25,000 PAGE 10 OF 11 REVISION NO:
1 ED 2 ATTACHMENT PAGE:
50F6 GROUND RESISTANCE IN OHMS SWITCH POSITION 1 SWITCH POSITION 2 o
1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 16000 17000 18000 19000 20000 21000 22000 23000 24000 25000 26000 27000 28000 29000 30000 31000 32000 33000 34000 35000 36000 37000 38000 39000 MGR-0009 Rev 2 IG IN MILLIAMPS
+15.00
+13.89
+12.93
+12.10
+11.36
+10.71
+10.14
+ 9.62
+ 9.15
+ 8.72
+ 8.33
+ 7.98
+ 7.65
+ 7.35
+ 7.08
+ 6.82
+ 6.58
+ 6.36
+ 6.15
+ 5.95
+ 5.77
+ 5.60
+ 5.43
+ 5.28
+ 5.14
+ 5.00
+ 4.87
+ 4.75
+ 4.63
+ 4.52
+ 4.41
+ 4.31
+ 4.21
+ 4.12
+ 4.03
+ 3.95
+ 3.87
+ 3.79
+ 3.71
+ 3.64 IG IN MILLIAMPS
+5.00
+4.63
+4.31
+4.03
+3.79
+3.57
+3.38
+3.21
+3.05
+2.91
+2.78
+2.66
+2.55
+2.45
+2.36
+2.27
+2.19
+2.12
+2.05
+1.98
+1.92
+1.87
+1.81
+1.76
+1.71
+1.67
+1.62
+1.58
+1.54
+1.51
+1.47
+1.44
+1.40
+1.37
+1.34
+1.32
+1.29
+1.26
+1.24
+1.21
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT 2.
DOCUMENT NUMBER:
34AB-R42-001-0S TITLE: GROUND FAULT DETERMINATION TABLE GROUND FAULT ON BUS N POTENTIOMETER RESISTANCE = 25,000 PAGE110F11 REVISION NO:
1 ED 2 ATTACHMENT PAGE:
60F6 GROUND RESISTANCE IN OHMS SWITCH POSITION 1 SWITCH POSITION 2 40000 41000 42000 43000 44000 45000 46000 47000 48000 49000 50000 MGR-0009 Rev 2 IG IN MILLIAMPS
+ 3.57
+ 3.50
+ 3.44
+ 3.38
+ 3.32
+ 3.26
+ 3.21
+ 3.15
+ 3.10
+ 3.05
+ 3.00 IG IN MILLIAMPS
+1.19
+1.17
+1.15
+1.13
+1.11
+1.09
+1.07
+1.05
+1.03
+1.02
+1.00 SOUTHERN NUCLEAR PLANT E.1. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT.1...
DOCUMENT NUMBER:
34AB-R42-001-0S TITLE: GROUND FAULT DETERMINATION TABLE GROUND FAULT ON BUS N POTENTIOMETER RESISTANCE = 25,000 PAGE110F11 REVISION NO:
1 ED 2 ATTACHMENT PAGE:
60F6 GROUND RESISTANCE IN OHMS SWITCH POSITION 1 SWITCH POSITION 2 40000 41000 42000 43000 44000 45000 46000 47000 48000 49000 50000 MGR-0009 Rev 2 IG IN MILLIAMPS
+ 3.57
+ 3.50
+ 3.44
+ 3.38
+ 3.32
+ 3.26
+ 3.21
+ 3.15
+ 3.10
+ 3.05
+ 3.00 IG IN MILLIAMPS
+1.19
+1.17
+1.15
+1.13
+1.11
+1.09
+1.07
+1.05
+1.03
+1.02
+1.00
UNIT 2 RPV SATURATION TEMPERATURE 450 v777Y777Y777l7777777l'l'77Y777Y777V77X777A777Y777Y777V7Z1777P77/?,777X1777777Y7/J 400
~'l###/,.r/A TEMP NEAR INSTRUMENT RUNS I
COF) 350 19~*¥#"/-"'
L- -
- + - - - - -
-~-I I
I
--~--------~-------~I-S-AF--E~~-
I 300
~~'WN~
~il I
250 -m - - - - - - -. - - - - - - - - r - - - - - - - - - - - - - -
200--~~~~~~~~~~~~~~~~~~~~
o 100 200 300 400 RPV PRESSURE (psig)
NOTE: May use SPDS Emergency Displays in place of this Graph.
lGRAPH 1 UNITl RPV SATURATION TEMPERATURE 450--~~~~~~~~~~~~~~~~~~~~~~~
400 ~17"/>,,/
TEMP NEAR INSTRUMENT RUNS (OP) 350-1"T..
300--w:
250-~
I o I
I
_____ L. ___ -
- + - _____
~~I I
I
=1 I
I
=1 I
I I
I
- - ~ - - - - - - - - ~ - - - - - - -I'-SA-F-E---;~ - - -I I
I I
I I
=1 I
,--------r-------I------~~
100 200 300 400 RPV PRESSURE (psig)
NOTE: May use SPDS Emergency Displays in place of this Graph.
UNIT 2 DRYWELL SPRAY INITIATION LIMIT 500 1~..:;~.z":;~~":;l'jjql \\$~":;":;":;~'I,.1;":;%":;~":;":;/7":;~?oY97A~%/7%~~~~~1 400 I~~W/%#
~hW'~.A7>>Y~~~1 DW TEMP (OF) 300 104..;,t;,;;~,(....;,..;,t;,;;i7','1 200 IWAo4'S'S'S4£A1 100 I.... UUE.,
o I SAFE I 10 20 DRYWELL PRESSURE (psig)
NOTE: May use SPDS Emergency Displays in place of this Graph.
30 40
!GRAPH 8 !
DRYWELL SPRAY INITIATION LIMIT 400~~~~~~--r-----~~~~~~~~~~~~~~~~~
DW TEMP COF) 300~~~~~~--~----~------+------+------r------r----~
ISAFEl L
I 200~M4~~~----~----~------+------+------~-----r----~
100~~~--~----~----~------+-----~------~----~----~
o 10 20 30 40 DRYWELL PRESSURE (psig)
NOTE: May use SPDS Emergency Displays in place of this Graph.
~;~f ::~ I II Bfl0W 1:0 PSig~ ~ I I Et I Below 5 psig*
19u 1 1."....
1811 1
"'=1 17(JJ,----J----+----~--~--_4----t_--_t--~----t_--~
UNIT 2 o
500 1000 1500 2000 2500 3000 3500 4000 4500 5000 HPCI FLOW (gpm)
NOTE: May use SPDS Emergency Displays in place of this Graph.
- Suppression Chamber Pressure.
- Safe operating region is below the applicable pressure line.
iGRAPH 17AI I
24 23 23 Torus 22 Temp eF) 21 20 19 18 17 HPCI PUMP NPSH LIMIT (Torus Water Level At or Above 146")
At or Above 10 psig !-----l-Below 10 psig*
Below 5 psig*
UNITZ 0
500 1000 1500 2000 2500 3000 3500 4000 4500 5000 HPCI FLOW (gpm)
NOTE: May use SPDS Emergency Displays in place of this Graph.
- Suppression Chamber Pressure.
- Safe operating region is below the applicable pressure line.
HPCI PUMP NPSH LIMIT (Torus Water Level Below 146")
UNIT 2 241) f77777777777777777777777y7777777v7777777v77777770777777A7777777A7777777A7777777A 23IT:r~~~~~~~~~v.
22 At or Above 10 psig I-+---+----t--+----=~~,..c".tj Torus Temp 21Jt===r==:j==::t:::j:~~~~--~L--1--J--J (OF)
Below 10 psig*
200 I 1-""""""
190 l I I I I,1 I L I I I J Below 5 psig*
180 I 'I I
I
' I I """= I
'I
"'" I 170 I
-=
1611~1----~----~----+-----r---~-----+-----r----~----~----4 500 1000 1500 2000 2500 3000 3500 4000 4500 5000 HPCI FLOW (gpm)
NOTE: May use SPDS Emergency Displays in place of this Graph.
- Suppression Chamber Pressure.
- Safe operating region is below the applicable pressure line.
!GRAPH 17B HPCI PUMP NPSH LIMIT (Torus Water Level Below 146")
lJNIT l 23IT::r~~~~~~~~~",~~~*
22 1-1----+-1 At or Above 10 psig 1-t-------1f___--l----+----=:::3~~~
Torus Temp 21Jt===l====t===:t:::+/-::~~~J-~~--L--l--J (OF)
Below 10 psig*
200*_l_-_+----+----r--~----+_--_+----r_--_l_--_+~~
Below 5 psig*
18W-~~~~~~F===~--+---~--~---+~~--~
- SAFE 161-1--~---l----+--+---+---~-~--f------l--~
5 0 1000 1500 2000 2500 3000 3500 4000 4500 5000 HPCI FLOW (gpm)
NOTE: May use SPDS Emergency Displays in place of this Graph.
- Suppression Chamber Pressure.
- Safe operating region is below the applicable pressure line.
WHILE PERFORMING lHE FOLLOWING lE. dryweH and torus gas concentrations I
THEN perfonn the adion specified are within a range specified I
in the table in the table below I
HYDROGEN Drywell OR torus H2 (whichever is higher)
None detected 1.5% or higher 6% or higher OR (below 1.5%)
AND less than 6% cannot be determined to be less than 6%
0 Drywell AND torus 02 no adion required perfonn path G-1 perfonn path G-1 X
less than 5%
)90 to point Q) )90 to pOint~) )90 to pOint R) y on this sheet on this sheet on this sheet G
E Drywell OR torus 02 no adion required perfonn path G-2 perfonn path G-3 N
5% or higher OR
)gotoPointQ) >gotoPointS) >
go to point T cannot be determined on this sheet on this sheet on this sheet to be less than 5%
WHILE PERFORMING lHE FOLLOWING IE drywell and torus gas concentrations I
THEN perform the action specified are within a range specified I
in the table in the table below I
HYDROGEN Dryvvell OR torus H2 (whichever is higher)
None detecte d 1.5% or higher 6% or higher OR (below 1.5%)
AND less than 6% cannot be determined to be less than 6%
0 Drywell AND torus 02 no action required perform path G-1 perform path G-1 X
less than 5%
)90 to point Q) >
go to point R) )90 to point R)
Y on this sheet on this sheet on this sheet G
E Drywell OR torus 02 no action required perform path G-2 perform path G-3 N
5% or higher OR
)goto pOintQ) )90 to point S) >
go to point T cannot be determined on this sheet on this sheet on this sheet to be less than 5%
- 1.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 was operating at 100% power when the reactor was manually scrammed.
Which ONE of the following choices completes the following statement?
The Control Rod Drive (CRD) Flow Controller (2CII-R600) flow indication IMMEDIATELY following the manual scram is (1)
- consequently, there is a potential for (2) to occur until the reactor scram is reset.
A. (1) greater than the setpoint; (2) CRD pump ronout B. (1) less than the setpoint; (2) low drive water differential pressure (dp)
C. (1) less than the setpoint; (2) elevated CRDM temperatures D. (1) greater than the setpoint; (2) excessive reactor vessel bottom head cooldown 1 of 75
- 1.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 was operating at 100% power when the reactor was manually scrammed.
Which ONE of the following choices completes the following statement?
The Control Rod Drive (CRD) Flow Controller (2Cll-R600) flow indication IMMEDIATELY following the manual scram is (1)
- consequently, there is a potential for (2) to occur until the reactor scram is reset.
A. (1) greater than the setpoint; (2) CRD pump runout B. (1) less than the setpoint; (2) low drive water differential pressure (dp)
- c. (1) less than the setpoint; (2) elevated CRDM temperatures D. (1) greater than the setpoint; (2) excessive reactor vessel bottom head cooldown 1 of 75
Plant Hatch HLT 5 (2009-302) NRC RO Test
- 2.
Unit 2 is operating at 90% power when the RFPT 2A trips.
Which ONE of the following choices completes BOTH of the statements below?
After the RFPT 2A trips, the Red Recife A AND B Runback lights will be (I)
The alarms 602-134 "RECIRC A FLOW LIMIT" AND 602-234 "RECIRC B FLOW LIMIT" will (2)
A. (l) extinguished (2) be alarming B. (l) illuminated (2) be alarming C. (l) extinguished (2) NOT be alarming D. (I) illuminated (2) NOT be alarming 2 of 75 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 2.
Unit 2 is operating at 90% power when the RFPT 2A trips.
Which ONE of the following choices completes BOrn of the statements below?
After the RFPT 2A trips, the Red Recirc A AND B Runback lights will be (I)
The alarms 602-134 "RECIRC A FLOW LIMIT" AND 602-234 "RECIRC B FLOW LIMIT" will (2)
A. (1) extinguished (2) be alarming B. (1) illuminated (2) be alarming C. (1) extinguished (2) NOT be alarming D. (1) illuminated (2) NOT be alarming 2 of 75
- 3.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is at 100% power when a loss of 4160 Bus 2C occurs.
Which ONE of the choices below completes the following statement?
The Reactor Recirc System ____ runback and the Reactor Recirc Pumps ____ _
A. will NOT; will NOT trip B. will NOT; will eventually trip, but not immediately
- c. will; will eventually trip, but not immediately D. will; will NOT trip 3 of 75
- 3.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is at 100% power when a loss of 4160 Bus 2C occurs.
Which ONE of the choices below completes the following statement?
The Reactor Recirc System ____ runback and the Reactor Recirc Pumps ____ _
A. will NOT; will NOT trip B. will NOT; will eventually trip, but not immediately C. will; will eventually trip, but not immediately D. will; will NOT trip 3 of 75
- 4.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 was operating at 100% when a LOCA occurred and the following conditions currently exist:
o Drywell pressure at 3 psig o RPV pressure at 500 psig o RPV level at -45 inches o RHR "A" and "D" pumps are turned OFF o RHR "c" pump running in LPCI mode o RHR "B" pump running in Torus Cooling mode Which ONE of the following identifies the control room panel that provides flow indicators for BOTH RHR loops and the expected flow indication on these flow indicators?
A. 2Hll-P601; Both loops flow indicators will have flow B. 2HII-P601; ONLY one loop's flow indicator will have flow C. 2HII-P602; Both loops flow indicators will have flow D. 2HII-P602; ONLY one loop's flow indicator will have flow 4 of 75
- 4.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 was operating at 100% when a LOCA occurred and the following conditions currently exist:
o Drywell pressure at 3 psig o RPV pressure at 500 psig o RPV level at -45 inches o RHR "A" and "D" pumps are turned OFF o RHR "C" pump running in LPCI mode o RHR "B" pump running in Torus Cooling mode Which ONE of the following identifies the control room panel that provides flow indicators for BOTH RHR loops and the expected flow indication on these flow indicators?
A. 2Hll-P601; Both loops flow indicators will have flow B. 2Hll-P601; ONLY one loop's flow indicator will have flow C. 2Hll-P602; Both loops flow indicators will have flow D. 2HII-P602; ONLY one loop's flow indicator will have flow 4 of 75
- 5.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 1 was operating at 100% power with the following RWCU indications:
o RWCU Inlet Flow Indicator R609: 245 gpm o RWCU Demin "A" & "B" Flow Ind R605 AlB: 115 gpm each Subsequently, the following alarm is received, RWCU SYS LEAK (602-421).
Which ONE of the following flow indications at the IG31-R615 Cleanup Leak Detection Indicator on PanellHII-P613 is the LOWEST value consistent with these plant conditions?
A. 0 gpm B. 15 gpm C. 45 gpm D. 60gpm 5 of 75
- 5.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 was operating at 100% power with the following RWCU indications:
o RWCU Inlet Flow Indicator R609: 245 gpm o RWCU Demin "A" & "B" Flow Ind R605 AlB: 115 gpm each Subsequently, the following alarm is received, RWCU SYS LEAK (602-421).
Which ONE of the following flow indications at the 1G31-R615 Cleanup Leak Detection Indicator on Panel1H11-P613 is the LOWEST value consistent with these plant conditions?
A. 0 gpm B. 15 gpm C. 45 gpm D. 60 gpm 5 of 75
- 6.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 1 is in Mode 4 with Shutdown Cooling in service. The following conditions exist:
o Recirculation Pumps................... Secured o RHR B Pump flow..................... 5500 gpm o All other RHR Pumps................ Standby lAW 34S0-EII-0l 0-1, "Residual Heat Removal System", which ONE of the following identifies the MINIMUM corrected reactor water level that must be maintained by the OATC?
A. +32" B. +34 C. +42" D. +54" 6 of 75
- 6.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is in Mode 4 with Shutdown Cooling in service. The following conditions exist:
o Recirculation Pumps................... Secured o RHR B Pump flow..................... 5500 gpm o All other RHR Pumps................ Standby IAW 34S0-Ell-01O-1, "Residual Heat Removal System", which ONE of the following identifies the MINIMUM corrected reactor water level that must be maintained by the OATC?
A. +32" B. +34 C. +42" D. +54" 6 of 75
- 7.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 was at 100% power when the following occurred:
o DW pressure increased to 12 psig o HCPI started, injected and tripped on high reactor water level o Reactor level lowered to + 1 0" o The Shift Supervisor directed HPCI be restarted o The Operator depressed the "HPCI High Water Level" Reset pushbutton o No other operator actions are taken Which ONE of the choices below completes the following statement?
When the HPCI High Water Level Reset pushbutton is depressed, the ____ will open and the ramp generator control turbine speed.
A. 2E41-FOOl Turb Steam Supply Valve; will B. HPCI Turbine Stop Valve; will C. 2E41-FOOl Turb Steam Supply Valve; will NOT D. HPCI Turbine Stop Valve; will NOT 7 of 75
- 7.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 was at 100% power when the following occurred:
o DW pressure increased to 12 psig o HCPI started, injected and tripped on high reactor water level o Reactor level lowered to + 10" o The Shift Supervisor directed HPCI be restarted o The Operator depressed the "HPCI High Water Level" Reset pushbutton o No other operator actions are taken Which ONE of the choices below completes the following statement?
When the HPCI High Water Level Reset pushbutton is depressed, the ____ will open and the ramp generator control turbine speed.
A. 2E41-FOOl Turb Stearn Supply Valve; will B. HPCI Turbine Stop Valve; will C. 2E41-FOOl Turb Stearn Supply Valve; will NOT D. HPCI Turbine Stop Valve; will NOT 7 of 75
- 8.
Plant Hatch HL T 5 (2009-302) NRC RD Test Unit 1 is at 100% power. Core Spray lE21-F004A has been stroked closed for a timing test when the following occurred:
o An unisolable Main Steam Line break occurs o Reactor leveL.............................. -105", decreasing o Reactor pressure.......................... 800 psig, decreasing Which ONE of the choices below completes the following statement?
The lE21-F004A "Outbd Discharge Valve" will FIRST receive the auto open signal when Reactor Pressure decreases to psig as sensed by a pressure instrument tap from the A. 425 psig; Reactor Recirc System B. 425 psig; Vessel Steam Dome C. 449 psig; Reactor Recirc System D. 449 psig; Vessel Steam Dome 8 of 75
- 8.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is at 100% power. Core Spray lE21-F004A has been stroked closed for a timing test when the following occurred:
o An unisolable Main Steam Line break occurs o Reactor leveL.............................. -105", decreasing o Reactor pressure.......................... 800 psig, decreasing Which ONE of the choices below completes the following statement?
The lE21-F004A "Outbd Discharge Valve" will FIRST receive the auto open signal when Reactor Pressure decreases to psig as sensed by a pressure instrument tap from the A. 425 psig; Reactor Recirc System B. 425 psig; Vessel Steam Dome C. 449 psig; Reactor Recirc System D. 449 psig; Vessel Steam Dome 8 of 75
Plant Hatch HLT 5 (2009-302) NRC RO Test
- 9.
Unit 2 is operating at 30% RTP with the following annunciator illuminated:
Local investigation of the alarm indicates a value on 2E21-N004A of -0.33 psid.
Which ONE of the following choices completes both the following statements?
IA W 34AR-601-322, the dP indication on 2E21-N004A ____ valid for determining Core Spray piping integrity at 30% power.
As reactor power and recirc flow is increased, 2E21-N004A indication is expected to move toward psid.
A. is
-5.0 B. is NOT
-5.0 C. is NOT
+5.0 D. is
+5.0 9 of 75 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 9.
Unit 2 is operating at 30% RTP with the following annunciator illuminated:
Local investigation of the alarm indicates a value on 2E21-N004A of -0.33 psid.
Which ONE of the following choices completes both the following statements?
IA W 34AR-60l-322, the dP indication on 2E21-N004A ____ valid for determining Core Spray piping integrity at 30% power.
As reactor power and recirc flow is increased, 2E21-N004A indication is expected to move toward psid.
A. is
-5.0 B. is NOT
-5.0 C. is NOT
+5.0 D. is
+5.0 9 of 75
- 10.
Plant Hatch HLT 5 (2009-302) NRC RO Test Concerning the Unit 2 Standby Liquid Control (SBLC) system:
TANK LEVEL 2C41-R601 Figure A TANK LEVEL 2C41-R601 Figure B Which ONE of the following completes both of these statements?
During normal operation, the means by which Sodium Pentaborate is CONTINUOUSLY maintained in solution inside the SBLC tank is by the use of __ _
Given the two figures shown above, and that SBLC has been initiated during an A TWS,
___ indicates the HIGHEST SBLC tank level which ensures that Cold Shutdown Boron Weight has been injected into the RPV.
A. tank heaters Figure A B. an air sparger Figure A C. tank heaters Figure B D. an air sparger Figure B 10 of 75
- 10.
Plant Hatch HLT 5 (2009-302) NRC RD Test Concerning the Unit 2 Standby Liquid Control (SBLC) system:
TANK LEVEL 2C41-R601 0-1 P
E R
C E
N T
r> *1 Figure A
,--~-------
TANK LEVEL 2C41-R601 P
E R
C E
N T
Figure B Which ONE of the following completes both of these statements?
During normal operation, the means by which Sodium Pentaborate is CONTINUOUSLY maintained in solution inside the SBLC tank is by the use of __ _
Given the two figures shown above, and that SBLC has been initiated during an ATWS,
___ indicates the HIGHEST SBLC tank level which ensures that Cold Shutdown Boron Weight has been injected into the RPV.
A. tank heaters Figure A B. an air sparger Figure A C. tank heaters Figure B D. an air sparger Figure B 10 of 75
- 11.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is in Mode 1 shutting down for a planned maintenance outage IA W 34GO-OPS-013-2, Plant Shutdown, with the following conditions present:
IRM..... ReadinglRange A...... 38/R9 B..... 33/R9 C...... 30/R9 D...... 38/R9 E...... 28/R9 F...... 37/R9 G...... 37/R9 H...... 26/R9 Which ONE of the choices below completes the following statements?
Placing the Reactor Mode Switch in the "START & HOT STBY" position __ cause an automatic scram signaL After the mode switch has been placed to the "START & HOT STBY" position, the operator is required to _______ _
A. will; transfer to and lock the Reactor Mode Switch in Shutdown IA W 34AB-C71-001-2, Scram Procedure B. will; confirm Hydrogen injection is shutdown IA W 34AB-C71-001-2, Scram Procedure C. will NOT; fully insert the SRMs prior to IRMs going below Range 2 IA W 34GO-OPS-013-2, Plant Shutdown D. will NOT; confirm power is turned on to the Refueling Bridge IA W 34GO-OPS-013-2, Plant Shutdown 11 of 75
- 11.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is in Mode 1 shutting down for a planned maintenance outage IA W 34GO-OPS-013-2, Plant Shutdown, with the following conditions present:
IRM..... Reading/Range A...... 38/R9 B..... 33 I R9 C...... 30/R9 D...... 38/R9 E...... 28/R9 F...... 37/R9 G...... 37 I R9 H...... 26/R9 Which ONE of the choices below completes the following statements?
Placing the Reactor Mode Switch in the "START & HOT STBY" position __ cause an automatic scram signal.
After the mode switch has been placed to the "START & HOT STBY" position, the operator is required to ________ _
A. will; transfer to and lock the Reactor Mode Switch in Shutdown IA W 34AB-C71-001-2, Scram Procedure B. will; confirm Hydrogen injection is shutdown IA W 34AB-C71-001-2, Scram Procedure C. will NOT; fully insert the SRMs prior to IRMs going below Range 2 IA W 34GO-OPS-013-2, Plant Shutdown D. will NOT; confirm power is turned on to the Refueling Bridge IA W 34GO-OPS-013-2, Plant Shutdown 11 of 75
- 12.
Plant Hatch HL T 5 (2009-302) NRC RD Test Unit 2 is operating at 100% power when the 2A RPS MG Set trips.
Which one of the following predicts the status of 2G31-F001, Rx Water Cleanup Valve, AND identifies the PREFERRED source of Alternate Power to 2A RPS Bus IA W 34S0-C71-001-2, 120 V AC RPS Supply System?
A. closed; Essential Cab 2A B. closed; Essential Cab 2B C. remains open; Essential Cab 2A D. remains open; Essential Cab 2B 12 of 75
- 12.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is operating at 100% power when the 2A RPS MG Set trips.
Which one of the following predicts the status of 2G31-F001, Rx Water Cleanup Valve, AND identifies the PREFERRED source of Alternate Power to 2A RPS Bus IA W 34S0-C71-001-2, 120 VAC RPS Supply System?
A. closed; Essential Cab 2A B. closed; Essential Cab 2B C. remains open; Essential Cab 2A D. remains open; Essential Cab 2B 12 of 75
Plant Hatch HLT 5 (2009-302) NRC RO Test
- 13.
Unit 1 is at 5% power and the following alarms are received:
o RMCS/RWM Rod Block or Sys. Trouble (603-239) o Process computer alarm typer: RPIS INOPERATIVE Which ONE of the choices completes the following statements?
With the above alarms Reactor Manual Control System (RMCS) allow a rod to be selected/latched and the Full-in and Full-out lights on the full core display available.
A. will NOT; are still B. will NOT; are NOT C. will still; are still D. will still; are NOT 13 of 75 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 13.
Unit 1 is at 5% power and the following alarms are received:
o RMCS/RWM Rod Block or Sys. Trouble (603-239) o Process computer alarm typer: RPIS INOPERATIVE Which ONE of the choices completes the following statements?
With the above alarms Reactor Manual Control System (RMCS) allow a rod to be selectedllatched and the Full-in and Full-out lights on the full core display available.
A. will NOT; are still B. will NOT; are NOT C. will still; are still D. will still; are NOT 13 of 75
- 14.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is in a reactor startup with the following conditions:
o Mode Switch in START & HOT STBY o All SRMs and IRMs fully inserted o Control Rods are being withdrawn o All IRMs are reading mid-scale on ranges 1 or 2 except:
- IRM "c" is on range 1 and reading 32
- IRM "D" is on range 2 and reading 12
- IRM "H" is failed downscale and bypassed o Annunciator "Rod Out Block" (603-238) is in alarm Which ONE of the choices below answers the following statement?
The "Rod Out Block" annunciator will clear if the operator ranges ___ OR if the operator __ _
A. IRM "c" to range 2; bypasses IRM "c" B. IRM "c" to range 2; places the mode switch in RUN C. IRM "D" to range 1; bypasses IRM "D" D. IRM "D" to range 1; places the mode switch in RUN 14 of 75
- 14.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is in a reactor startup with the following conditions:
o Mode Switch in START & HOT STBY o All SRMs and IRMs fully inserted o Control Rods are being withdrawn o All IRMs are reading mid-scale on ranges 1 or 2 except:
- IRM "C" is on range 1 and reading 32
- IRM "D" is on range 2 and reading 12
- IRM "H" is failed downscale and bypassed o Annunciator "Rod Out Block" (603-238) is in alann Which ONE of the choices below answers the following statement?
The "Rod Out Block" annunciator will clear if the operator ranges ____ OR if the operator ___ _
A. IRM "c" to range 2; bypasses IRM "c" B. IRM "c" to range 2; places the mode switch in RUN C. IRM "D" to range 1; bypasses IRM "D" D. IRM "D" to range 1; places the mode switch in RUN 14 of 75
Plant Hatch HL T 5 (2009-302) NRC RO Test
- 15.
Unit 2 is in a refueling outage.
Plant conditions:
o Reactor Protection System (RPS) Shorting Links have been REMOVED o Due to a detector malfunction, the SRM "A" count rate begins to rise Which ONE of the choices below completes the following statement?
When SRM "A" count rate increases to 4 x 105 cps, THEN a ____ will exist.
A. control rod block (ONLY)
B. control rod block AND a trip in RPS Channel "A" (ONLY)
C. control rod block AND a trip in BOTH RPS Channels D. "SRM Upscale OR Inoperative" (603-204) alarm (ONLY) 15 of 75 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 15.
Unit 2 is in a refueling outage.
Plant conditions:
o Reactor Protection System (RPS) Shorting Links have been REMOVED o Due to a detector malfunction, the SRM "A" count rate begins to rise Which ONE of the choices below completes the following statement?
When SRM "A" count rate increases to 4 x 105 cps, lliEN a ____ will exist.
A. control rod block (ONLY)
B. control rod block AND a trip in RPS Channel "A" (ONLY)
C. control rod block AND a trip in BOlli RPS Channels D. "SRM Upscale OR Inoperative" (603-204) alarm (ONLY) 15 of 75
- 16.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is operating at 90% power and 90% core flow A malfunction occurs on Recirc ASDs which causes core flow to increase to 100%.
Which ONE of the following will be the new ACTUAL Simulated Thermal Power trip setpoint for the APRMs lAW 34AR-603-21O-2, "APRMlOPRM TRIP"?
A. 104%
B. 110%
C. 112.5%
D. 113.8%
16 of 75
- 16.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is operating at 90% power and 90% core flow A malfunction occurs on Recirc ASDs which causes core flow to increase to 100%.
Which ONE of the following will be the new ACTUAL Simulated Thermal Power trip setpoint for the APRMs lAW 34AR-603-210-2, "APRM/OPRM TRIP"?
A. 104%
B. 110%
C. 112.5%
D. 113.8%
16 of 75
- 17.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is starting up with the Reactor Mode Switch in the START & HOT STBY position when the following occurs:
o I&C has determined a GE SIL (Service Information Letter) causes several APRM "D" LPRMs to be inoperable.
o Operations bypasses the inop LPRMS The following is the present status of APRM "D":
o Indicated Power Level................... 9%
o Number of Level D LPRM Inputs.. 5 o Number of Level C LPRM Inputs... 4 o Number of Level B LPRM Inputs... 4 o Number of Level A LPRM Inputs... 3 Which ONE of the following identifies the ROD OUT BLOCK (603-238) alarm status based on the current status of APRM "D"?
A. APRM "D" is causing a ROD OUT BLOCK alarm because there are too few LPRM inputs per leveL B. APRM "D" is causing a ROD OUT BLOCK alarm because there are too few total LPRM inputs.
C. APRM "D" is causing a ROD OUT BLOCK alarm because power is too high.
D. APRM "D" is NOT causing a ROD OUT BLOCK alarm.
17 of 75
- 17.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is starting up with the Reactor Mode Switch in the START & HOT STBY position when the following occurs:
o I&C has determined a GE SIL (Service Information Letter) causes several APRM "D" LPRMs to be inoperable.
o Operations bypasses the inop LPRMS The following is the present status of APRM "D":
o Indicated Power Level................... 9%
o Number of Level D LPRM Inputs.. 5 o Number of Level C LPRM Inputs... 4 o Number of Level B LPRM Inputs... 4 o Number of Level A LPRM Inputs... 3 Which ONE of the following identifies the ROD OUT BLOCK (603-238) alarm status based on the current status of APRM "D"?
A. APRM "D" is causing a ROD OUT BLOCK alarm because there are too few LPRM inputs per leveL B. APRM "D" is causing a ROD OUT BLOCK alarm because there are too few total LPRM inputs.
C. APRM "D" is causing a ROD OUT BLOCK alarm because power is too high.
D. APRM "D" is NOT causing a ROD OUT BLOCK alarm.
17 of 75
- 18.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is at 100% power when the following occurs:
o A Loss of DW chillers occurs o DW Pressure (peak)....................................... 2.1 psig o DW Bulk Average Temperature (peak).......... 155°F o Reactor Pressure............................................... Controlled by LLS o A Torus leak develops and Emergency Depressurization is required o When 7 SRVs are initially opened, level swell causes level to rise to +55" o When the RHR injection valves automatically open, level is at minus 20" IAW 34AB-B21-002-2 "RPV Water Level Corrections," which ONE of the choices below completes the following statements?
When the 7 SRVs are initially opened, the recommended reactor water level (RWL) instrument to monitor level is (1)
- 1.
- J deTe(tr',ne When the RHR injection valves automatically open, RWL may be fHOHitofel with (2)
RWL instruments.
Jt4 A. (1) Floodup Range; (2) Fuel Zone and Wide Range B. (1) Narrow Range (2) Fuel Zone ONLY C. (1) Floodup Range; (2) Fuel Zone ONLY D. (1) Narrow Range; (2) Fuel Zone and Wide Range 18 of 75
- 18.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is at 100% power when the following occurs:
o A Loss of DW chillers occurs o DW Pressure (peak)....................................... 2.1 psig o DW Bulk Average Temperature (peak).......... 155°F o Reactor Pressure............................................... Controlled by LLS o A Torus leak develops and Emergency Depressurization is required o When 7 SRVs are initially opened, level swell causes level to rise to +55" o When the RHR injection valves automatically open, level is at minus 20" IA W 34AB-B21-002-2 "RPV Water Level Corrections," which ONE of the choices below completes the following statements?
When the 7 SRVs are initially opened, the recommended reactor water level (RWL) instrument to monitor level is
- 0) 1
\\
deTe(""ne d When the RHR injection valves automatically open, RWL may be ffiOBitofel with (2)
RWL instruments.
JtI A. (1) Floodup Range; (2) Fuel Zone and Wide Range B. (1) Narrow Range (2) Fuel Zone ONLY
- c. (1) Floodup Range; (2) Fuel Zone ONLY D. (1) Narrow Range; (2) Fuel Zone and Wide Range 18 of 75
Plant Hatch HL T 5 (2009-302) NRC RO Test
- 19.
Which ONE of the following is the power supply to the Unit 2 RCIC flow controller?
B. DC Cabinet "2A" (2R25-S001)
C. Instrument Bus "2A" (2R25-S064)
D. DC Cabinet "2B" (2R25-S002) 19 of 75 Plant Hatch HL T 5 (2009-302) NRC RO Test
- 19.
Which ONE of the following is the power supply to the Unit 2 RCIC flow controller?
B. DC Cabinet "2A" (2R25-S00l)
C. Instrument Bus "2A" (2R25-S064)
D. DC Cabinet "2B" (2R25-S002) 19 of 75
- 20.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 has experienced a Loss of Offsite Power (LOSP).
The following conditions existed at 15:00:
o Reactor........................ All rods in o RPV Pressure...................... 860 psig controlled by LLS o RWL............................ -93 inches, decreasing at 2 inches/minute o Drywell Pressure............... 0.6 psig, increasing at 0.05 psi/minute o ADS Inhibit Switches.......... "Normal" position Given these trends, which ONE of the following predicts the EARLIEST time that the ADS valves will automatically open?
A. 15:04 B. 15:06 C. 15:15 D. 15:17 20 of 75
- 20.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 has experienced a Loss of Offsite Power CLOSP).
The following conditions existed at 15:00:
o Reactor........................ All rods in o RPV Pressure...................... 860 psig controlled by LLS o RWL............................ -93 inches, decreasing at 2 inches/minute o Drywell Pressure............... 0.6 psig, increasing at 0.05 psi/minute o ADS Inhibit Switches.......... "Normal" position Given these trends, which ONE of the following predicts the EARLIEST time that the ADS valves will automatically open?
A. 15:04 B. 15:06 C. 15:15 D. 15:17 20 of 75
- 21.
Plant Hatch HL T 5 (2009-302) NRC RD Test Unit 2 is at 100% power and the STA is running the "D" TIP machine with the probe in the mid-core region. All other TIP machines have their associated detectors at the PARKED position. During TIP operation the following occurs:
o Power is subsequently lost to ONLY the "D" TIP Machine and all "D" TIP movement stops o DW pressure is 2.2 psig and increasing o TIP area rad monitor 2D21-K601F is reading 700 mrthr and increasing o An SO reports steam coming from the TIP room The status of the TIP machines is that ____ and the operator is required to ___ IA W 34AB-C71-001-2, Scram Procedure.
A. ALL TIP ball valves are open; immediately flre all shear valves B. ONLY the "D" TIP ball valve is open; immediately flre TIP "D" shear valve ONLY C. ALL TIP ball valves are open; flre all TIP shear valves ONLY after radiation levels reach 1,000 mrthr D. ONLY the "D" TIP ball valve is open; flre "D" TIP shear valve ONLY after radiation levels reach 1,000 mrlhr 21 of 75
- 21.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is at 100% power and the STA is running the "D" TIP machine with the probe in the mid-core region. All other TIP machines have their associated detectors at the PARKED position. During TIP operation the following occurs:
o Power is subsequently lost to ONLY the "D" TIP Machine and all "D" TIP movement stops o DW pressure is 2.2 psig and increasing o TIP area rad monitor 2D21-K601F is reading 700 mrlhr and increasing o An SO reports steam coming from the TIP room The status of the TIP machines is that ____ and the operator is required to ___ IA W 34AB-C71-001-2, Scram Procedure.
A. ALL TIP ball valves are open; immediately fire all shear valves B. ONLY the "D" TIP ball valve is open; immediately fire TIP "D" shear valve ONLY C. ALL TIP ball valves are open; fire all TIP shear valves ONLY after radiation levels reach 1,000 mrlhr D. ONLY the "D" TIP ball valve is open; fire "D" TIP shear valve ONLY after radiation levels reach 1,000 mr/hr 21 of 75
Plant Hatch HL T 5 (2009-302) NRC RO Test
- 22.
- d. ~
UniVis in a refueling outage when a rupture of the Fuel Pool Cooling and Cleanup (FPCC) return line to the fuel pool occurs.
Which ONE of the following identifies the low suction pressure trip setpoint and a design feature which will minimize the inventory loss from the Fuel Pool?
A. 8 psig; The Anti-Siphon check valves on the return lines re-position.
B. 18 psig; The Anti-Siphon check valves on the return lines re-position.
C. 8 psig; The Diffusers on the return lines become uncovered.
D. 18 psig; The Diffusers on the return lines become uncovered.
22 of 75 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 22.
~ ~
Uni~is in a refueling outage when a rupture of the Fuel Pool Cooling and Cleanup (FPCC) return line to the fuel pool occurs.
Which ONE of the following identifies the low suction pressure trip setpoint and a design feature which will minimize the inventory loss from the Fuel Pool?
A. 8 psig; The Anti-Siphon check valves on the return lines re-position.
B. 18 psig; The Anti-Siphon check valves on the return lines re-position.
C. 8 psig; The Diffusers on the return lines become uncovered.
D. 18 psig; The Diffusers on the return lines become uncovered.
22 of 75
- 23.
Plant Hatch HLT 5 (2009-302) NRC RD Test Unit 2 is in a refueling outage with the following conditions:
o Refueling grapple has latched a seated bundle in the core o Refueling platform air compressor line breaks o Refueling platform air pressure is 0 psig Which ONE of the choices below identifies how the malfunction will affect the main grapple?
The latched bundle be unlatched.
The grapple be raised.
A. can still; can still B. can still; canNOT C. canNOT; can still D. canNOT; canNOT 23 of 75
- 23.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is in a refueling outage with the following conditions:
o Refueling grapple has latched a seated bundle in the core o Refueling platfonn air compressor line breaks o Refueling platfonn air pressure is 0 psig Which ONE of the choices below identifies how the malfunction will affect the main grapple?
The latched bundle be unlatched.
The grapple be raised.
A. can still; can still B. can still; canNOT C. canNOT; can still D. canNOT; canNOT 23 of 75
Plant Hatch HL T 5 (2009-302) NRC RO Test
- 24.
Unit 2 is in an A TWS with the following conditions:
o Reactor Power................................................. 20%
o Reactor Pressure.............................................. 1125 psig, (highest reached) o MSN s............................................................. Closed o Torus temp...................................................... l05°P, rising Which ONE of the choices below completes BOTH the following statements?
With no operator action, the MAXIMUM number of SRV's that will be open is __ _
IA W EOP PC flowchart, 31EO-EOP-OI2-2, the MINIMUM number ofloop(s) ofRHR required to be placed in Torus Cooling is ___ _
A. 8; 1
B. 8; 2
C. 4',
1 D. 4',
2 24 of 75 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 24.
Unit 2 is in an A TWS with the following conditions:
o Reactor Power................................................. 20%
o Reactor Pressure.............................................. 1125 psig, (highest reached) o MSIVs............................................................. Closed o Torus temp...................................................... 105°P, rising Which ONE of the choices below completes BOTH the following statements?
With no operator action, the MAXIMUM number of SRV's that will be open is __ _
IA W EOP PC flowchart, 31EO-EOP-012-2, the MINIMUM number of loop(s) of RHR required to be placed in Torus Cooling is ___ _
A. 8*,
1 B. 8; 2
C. 4*,
1 D. 4*,
2 24 of 75
- 25.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is operating at 23% reactor power. Operators are in the process of starting up the Main Turbine. The Main Turbine is on turning gear.
Which ONE of the choices below completes the following statements?
lAW 34S0-N30-001-2, "Main Turbine Operation" section 7.1.5, "Turbine Roll And Initial Loading", the is required to be used for monitoring Eccentricity on the Main Turbine.
The first speed selected for the Initial Turbine walkdown is "Speed Cmd RPM" __ _
A. Human Machine Interface (HMI) Screen; LOW (100)
B. Human Machine Interface (HMI) Screen; MED (800)
C. 2N32-R609, "TURBINE METAL EXPANSIONffEMP" recorder; MED (800)
D. 2N32-R609, "TURBINE METAL EXPANSIONffEMP" recorder; LOW (100) 25 of 75
- 25.
Plant Hatch HL T 5 (2009-302) NRC RD Test Unit 2 is operating at 23% reactor power. Operators are in the process of starting up the Main Turbine. The Main Turbine is on turning gear.
Which ONE of the choices below completes the following statements?
lAW 34S0-N30-001-2, "Main Turbine Operation" section 7.1.5, "Turbine Roll And Initial Loading", the is required to be used for monitoring Eccentricity on the Main Turbine.
The first speed selected for the Initial Turbine walkdown is "Speed Cmd RPM" __ _
A. Human Machine Interface (HMI) Screen; LOW (100)
B. Human Machine Interface (HMI) Screen; MED (800)
C. 2N32-R609, "TURBINE METAL EXPANSIONfTEMP" recorder; MED (800)
D. 2N32-R609, "TURBINE METAL EXPANSIONfTEMP" recorder; LOW (100) 25 of 75
- 26.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is at 60% power with the following conditions:
o "A" RFPT is in Auto, controlled from the FW Master Controller lC32-R600 o "B" RFPT is in Manual, controlled from MIA station lC32-R601B, as indicated below Which one of the choices below completes the following two statements lAW 34S0-N2l-007-l "Condensate & Feedwater System"?
Prior to placing the "B" RFPT controller in "Auto", its OUTPUT signal is required to be matched with its INPUT signal (from Master Controller) using the __ _
When the "B" RFPT controller is in "Auto", then the ___ will be used to balance flows between the RFPTs.
A. output lever output lever B. output lever set point keys C. set point keys output lever D. set point keys set point keys 26 of 75
- 26.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is at 60% power with the following conditions:
o "A" RFPT is in Auto, controlled from the FW Master Controller lC32-R600 o "B" RFPT is in Manual, controlled from MIA station lC32-R601B, as indicated below Which one of the choices below completes the following two statements IA W 34S0-N21-007-1 "Condensate & Feedwater System"?
Prior to placing the "B" RFPT controller in "Auto", its OUTPUT signal is required to be matched with its INPUT signal (from Master Controller) using the ___ _
When the "B" RFPT controller is in "Auto", then the ___ will be used to balance flows between the RFPTs.
A. output lever output lever B. output lever set point keys C. set point keys output lever D. set point keys set point keys 26 of 75
Plant Hatch HLT 5 (2009-302) NRC RO Test
- 27.
Unit 2 is operating at 100% rated power with the following conditions:
o Feedwater Level Control is in three element automatic control o Reactor level is 36" o The "A" Feedwater Flow signal to the Feedwater Control System suddenly fails downscale Which one of the choices below completes the following statement?
After the system stabilizes, reactor water level will be ____ and the Master Feedwater Level Controller will be in __ _
A. higher; single element control B. higher; 3 element control C. the same; single element control D. the same; 3 element control 27 of 75 Plant Hatch HL T 5 (2009-302) NRC RO Test
- 27.
Unit 2 is operating at 100% rated power with the following conditions:
o Feedwater Level Control is in three element automatic control o Reactor level is 36" o The "A" Feedwater Flow signal to the Feedwater Control System suddenly fails downscale Which one of the choices below completes the following statement?
After the system stabilizes, reactor water level will be ____ and the Master Feedwater Level Controller will be in __ _
A. higher; single element control B. higher; 3 element control C. the same; single element control D. the same; 3 element control 27 of 75
- 28.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 1 is at 100% power with the Unit 1 refueling equipment hatch installed, when a loss of all feedwater occurs.
Subsequently, the following conditions exist:
o HPCI and RCIC auto start on low level o SBGT suction valves from the Reactor Building are CLOSED Which ONE of the choices below completes the following statements?
Rx Bldg DP will __ _
SBGT system suction valves __ _
A. approach 0";
responded correctly B. approach 0";
failed to reposition C. remain the same; responded correctly D. remain the same; failed to reposition 28 of 75
- 28.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is at 100% power with the Unit 1 refueling equipment hatch installed, when a loss of all feedwater occurs.
Subsequently, the following conditions exist:
o HPCI and RCIC auto start on low level o SBGT suction valves from the Reactor Building are CLOSED Which ONE of the choices below completes the following statements?
Rx Bldg DP will __ _
SBGT system suction valves __ _
A. approach 0";
responded correctly B. approach 0";
failed to reposition C. remain the same; responded correctly D. remain the same; failed to reposition 28 of 75
- 29.
Plant Hatch HL T 5 (2009-302) NRC RD Test Unit 2 is inerting the primary containment IA W Containment Atmospheric Control & Dilution, 34S0-T48-002-2, Section 7.1.1, Primary Containment Inerting.
The following conditions currently exist:
o SBGT 2A running o DW 02 concentration is 4.2%, slowly lowering Assuming no operator action, which ONE of the following choices predicts how the oxygen concentration and DW venting are affected if the 2A SBGT fan trips?
DW 02 concentration will ___ _
The current DW venting lineup ___ allowed without SBGT in service IA W 34S0-T48-002-2.
A. remain at 4.2%;
is NOT B. remain at 4.2%
is C. continue to lower; is NOT D. continue to lower; is 29 of 75
- 29.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is inerting the primary containment IA W Containment Atmospheric Control & Dilution, 34S0-T48-002-2, Section 7.l.1, Primary Containment Inerting.
The following conditions currently exist:
o SBGT 2A running o DW 02 concentration is 4.2%, slowly lowering Assuming no operator action, which ONE of the following choices predicts how the oxygen concentration and DW venting are affected if the 2A SBGT fan trips?
DW 02 concentration will ___ _
The current DW venting lineup ___ allowed without SBGT in service IA W 34S 0-T 48-002-2.
A. remain at 4.2%;
is NOT B. remain at 4.2%
is C. continue to lower; is NOT D. continue to lower; is 29 of 75
- 30.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is operating at 50% RTP and a CRD pump rotation is planned when a number of annunciators alarm, including:
o ARI OUT OF SERVICE (603-305) o LOSS OF OFF SITE POWER (652-102)
A subsequent check indicates that ARI is out of service but Off Site Power has NOT been lost.
Which ONE of the choices below completes the following statements?
The annunciators indicate that there has been a loss of __ _
The Control Room operator ___ be able to operate the breaker for CRD Pump 2A from the Control Room.
A. DC Cabinet 2E, 2R25-S005; will still B. DC Cabinet 2E, 2R25-S005; will NOT C. DC Cabinet 2D, 2R25-S004; will still D. DC Cabinet 2D, 2R25-S004; will NOT 30 of 75
- 30.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is operating at 50% RTP and a CRD pump rotation is planned when a number of annunciators alarm, including:
o ARI OUT OF SERVICE (603-305) o LOSS OF OFF SITE POWER (652-102)
A subsequent check indicates that ARI is out of service but Off Site Power has NOT been lost.
Which ONE of the choices below completes the following statements?
The annunciators indicate that there has been a loss of __ _
The Control Room operator ____ be able to operate the breaker for CRD Pump 2A from the Control Room.
A. DC Cabinet 2E, 2R25-S005; will still B. DC Cabinet 2E, 2R25-S005; will NOT C. DC Cabinet 2D, 2R25-S004; will still D. DC Cabinet 2D, 2R25-S004; will NOT 30 of 75
- 31.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is at 100% power when a Loss of Off-Site Power occurs and the "2C" EDG fails to start Which ONE of the below choices completes the following statements?
The Vital AC Bus is currently receiving its power from __ _
The Vital AC Bus will transfer to its Alternate source ONLY after the non-essential loads from
___ have been re-energized.
A. the Vital AC batteries; 600 V Bus 2D B. the Vital AC batteries; 600 V Bus 2C C. 600 V Bus 2C; 600 V Bus 2D D. 600 V Bus 2D; 600 V Bus 2C 31 of 75
- 31.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is at 100% power when a Loss of Off-Site Power occurs and the "2C" EDG fails to start Which ONE of the below choices completes the following statements?
The Vital AC Bus is currently receiving its power from ___ _
The Vital AC Bus will transfer to its Alternate source ONLY after the non-essential loads from
____ have been re-energized.
A. the Vital AC batteries; 600 V Bus 2D B. the Vital AC batteries; 600 V Bus 2C C. 600 V Bus 2C; 600 V Bus 2D D. 600 V Bus 2D; 600 V Bus 2C 31 of 75
- 32.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is operating at full power when the following occurs:
o 125/250V BATTERY GND FAULT 651-141 alarms o 34AB-R42-00l-0, "Location Of Grounds" is entered o On 1H11-P655, the Battery Ground Detection System meter 1R42-R613B indicates the following when placed to Position 1 and then Position 2:
Switch Position 1 I Switch Position 2 I Which ONE of the choices below completes BOTH of the following statements?
If the cause of the deflections is a single ground, then spurious component actuations due to the ground are __ _
Based on the resistance value of the ground, the operator ___ remain in 34AB-R42-001-0S, Location Of Grounds.
REFERENCE PROVIDED A. possible; is NOT required to B. possible; is required to C. NOT possible; is required to D. NOT possible; is NOT required to 32 of 75
- 32.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is operating at full power when the following occurs:
o 1251250V BATTERY GND FAULT 651-141 alarms o 34AB-R42-001-0, "Location Of Grounds" is entered o On 1Hll-P655, the Battery Ground Detection System meter 1R42-R613B indicates the following when placed to Position 1 and then Position 2:
/. 10
"'/:
" +20
/
Switch Position 1 Switch Position 2 Which ONE of the choices below completes BOTH of the following statements?
If the cause of the deflections is a single ground, then spurious component actuations due to the ground are __ _
Based on the resistance value of the ground, the operator ___ remain in 34AB-R42-001-0S, Location Of Grounds.
REFERENCE PROVIDED A. possible; is NOT required to B. possible; is required to C. NOT possible; is required to D. NOT possible; is NOT required to 32 of 75
- 33.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is at 100% power and EDG 2A is to be run locally for post maintenence testing per 34S0-R43-001-2, "Diesel Generator Standby AC System".
The local operator must place the "At Engine-Remote Switch" to the ___ position to start the diesel and the switch position to flash the field.
A. "At Engine";
will remain in the "At Engine" B. "At Engine'"
must be placed to the "Remote" C. "Remote";
will remain in the "Remote" D. "Remote";
must be placed to the "At Engine" 33 of 75
- 33.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is at 100% power and EDG 2A is to be run locally for post maintenence testing per 34S0-R43-001-2, "Diesel Generator Standby AC System".
The local operator must place the "At Engine-Remote Switch" to the ___ position to start the diesel and the switch position to flash the field.
A. "At Engine";
will remain in the "At Engine" B. "At Engine'"
must be placed to the "Remote" C. "Remote";
will remain in the "Remote" D. "Remote";
must be placed to the" At Engine" 33 of 75
- 34.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 1 experiences a Loss of Offsite Power when the following occurs:
o Annunciator "FIRE ALARM" (651-160) alarms o A Fire on "IE" Emergency Bus is reported o The Fire Brigade requests that "IE" Emergency Bus be de-energized.
To IMMEDIATELY de-energize the bus from the Control Room, the operator is required to (1)
IA W 34S0-R43-00l-l, "Diesel Generator Standby AC System".
o After the bus is de-energized, water is sprayed on the fire.
In order to verify automatic actions occur, the operator is required to send a Systems Operator to the (2) fire pump to verify it automatically starts.
A. (1) trip EDG "lA" (2) # 1 Diesel B. (1) trip EDG "lA" (2) Electric C. (1) open EDG "lA" output breaker (2) # 1 Diesel D. (1) open EDG "lA" output breaker (2) Electric 34 of 75
- 34.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 1 experiences a Loss of Offsite Power when the following occurs:
o Annunciator "FIRE ALARM" (651-160) alarms o A Fire on "IE" Emergency Bus is reported o The Fire Brigade requests that "IE" Emergency Bus be de-energized.
To IMMEDIA TEL Y de-energize the bus from the Control Room, the operator is required to (1)
IA W 34S0-R43-001-1, "Diesel Generator Standby AC System".
o After the bus is de-energized, water is sprayed on the fire.
In order to verify automatic actions occur, the operator is required to send a Systems Operator to the (2) fire pump to verify it automatically starts.
A. (1) trip EDG "IA" (2) # 1 Diesel B. (1) trip EDG "IA" (2) Electric
- c. (1) open EDG "IA" output breaker (2) # 1 Diesel D. (1) open EDG "IA" output breaker (2) Electric 34 of 75
Plant Hatch HL T 5 (2009-302) NRC RO Test
- 35.
Unit 1 is at 100% power with the following conditions:
o Reactor Level Mode Select - Manual o Reactor Water Level Select - "B" o FW Control Mode Select - 3 Element o "B" GEMAC level transmitter starts slowly drifting upscale Which ONE of the choices below completes the following statement?
Initially the drifting level transmitter causes the steam dryer/separators to allow more __ _
and the recirc/jet pumps will see a in their available NPSH.
A. carryover; increase B. carryover; decrease C. carryunder; increase D. carryunder; decrease 35 of 75 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 35.
Unit 1 is at 100% power with the following conditions:
o Reactor Level Mode Select - Manual o Reactor Water Level Select _ "B" o FW Control Mode Select - 3 Element o "B" GEMAC level transmitter starts slowly drifting upscale Which ONE of the choices below completes the following statement?
Initially the drifting level transmitter causes the steam dryer/separators to allow more __ _
and the recire/jet pumps will see a in their available NPSH.
A. carryover; increase B. carryover; decrease C. carryunder; increase D. carryunder; decrease 35 of 75
- 36.
Plant Hatch HL T 5 (2009-302) NRC RD Test Which ONE of the following Unit 2 plant conditions will cause Control Room pressure to automatically INCREASE relative to Turbine Building pressure?
A. Rx Bldg Pot Contaminated Area, 2DII-K609 A-D 18 mr/hr B. High Drywell Pressure of 1.2 psig C. Main Steam Line Radiation, 2DII-K603 A-D HI-HI (3 times normal),
D. Reactor Water Level of -110 inches 36 of 75
- 36.
Plant Hatch HLT 5 (2009-302) NRC RO Test Which ONE of the following Unit 2 plant conditions will cause Control Room pressure to automatically INCREASE relative to Turbine Building pressure?
A. Rx Bldg Pot Contaminated Area, 2DII-K609 A-D 18 mr/hr B. High Drywell Pressure of 1.2 psig C. Main Steam Line Radiation, 2DII-K603 A-D HI-HI (3 times normal),
D. Reactor Water Level of -110 inches 36 of 75
- 37.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is operating at 50% power when the 2B Recirc pump trips resulting in the following plant conditions:
o 2B31-R661A, "2A Recirc Percent Speed"......................................................... 32% speed.
o Jet Pump Flow 2B21-R611A, "Total A Flow".................................................. 21 Mlbmlhr.
o Jet Pump Flow 2B21-R611B, "Total B Flow".................................................... 6 Mlbrnlhr.
o 2B21-R613, "Core Plate dp / Rx. Core Flow" recorder...................................... 19 percent Which ONE of the following identifies BOTH the accuracy of 2B21-R613 and actual Rx. core flow in Mlbmlhr?
The 2B21-R613 recorder __ accurate and actual core flow is A. Is; 15 B. Is; 27 C. Is NOT; 15 D. Is NOT; 27 37 of 75 Mlbmlhr.
- 37.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is operating at 50% power when the 2B Recirc pump trips resulting in the following plant conditions:
o 2B31-R661A, "2A Recirc Percent Speed"......................................................... 32% speed.
o Jet Pump Flow 2B21-R611A, "Total A Flow".................................................. 21 Mlbmlhr.
o Jet Pump Flow 2B21-R611B, "Total B Flow".................................................... 6 Mlbmlhr.
o 2B21-R613, "Core Plate dp / Rx Core Flow" recorder...................................... 19 percent Which ONE of the following identifies BOTH the accuracy of 2B21-R613 and actual Rx core flow in Mlbmlhr?
The 2B21-R613 recorder __ accurate and actual core flow is A. Is; 15 B. Is; 27 C. Is NOT; 15 D. Is NOT; 27 37 of 75 Mlbmlhr.
- 38.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 was at power when, due to required RFPT repairs, a controlled shutdown is completed and plant conditons are:
o Control Rods.................................... inserted to 00 o MSNs.............................................. Closed o Reactor Pressure............................... 900 psig with HPCI o Reactor Level................................... +30" with RCIC Subsequently, a Loss of Off-Site Power occurs with the following conditions:
o EDG "2A" fails to start o EDG "IB" is suppling "2F" 4160 VAC Bus o It is desired to power "2C" 600 V AC Bus from the "2CD" 600 V AC Transformer o NO EOPs have been entered Which ONE of the choices below completes the following statment?
In order to power "2C" 600 V AC Bus from "2CD" 600 V AC Transformer, an electrical jumper
___ required to jumper out the breaker closure interlock.
IA W 34AB-R23-00l-2 "Loss Of 600 Volt Emergency Bus" the 2C 600 VAC bus __
allowed to be powered from the 2CD Transformer.
A. is; is B. is NOT; is NOT C. is; is NOT D. is NOT; is 38 of 75
- 38.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 was at power when, due to required RFPT repairs, a controlled shutdown is completed and plant conditons are:
o Control Rods.................................... inserted to 00 o MSIVs.............................................. Closed o Reactor Pressure............................... 900 psig with HPCI o Reactor Level................................... +30" with RCIC Subsequently, a Loss of Off-Site Power occurs with the following conditions:
o EDG "2A" fails to start o EDG "IB" is suppling "2P" 4160 VAC Bus o It is desired to power "2C" 600 V AC Bus from the "2CD" 600 V AC Transformer o NO EOPs have been entered Which ONE of the choices below completes the following statment?
In order to power "2C" 600 V AC Bus from "2CD" 600 V AC Transformer, an electrical jumper
____ required to jumper out the breaker closure interlock.
IAW 34AB-R23-00I-2 "Loss Of 600 Volt Emergency Bus" the 2C 600 VAC bus __
allowed to be powered from the 2CD Transformer.
A. is; is B. is NOT; is NOT C. is; is NOT D. is NOT; is 38 of 75
Plant Hatch HLT 5 (2009-302) NRC RO Test
- 39.
Unit 1 is at 10% power when a seismic event causes the following:
o 125/250 VDC Switchgear "lA" (lR22-S016) de-energizes o A Main Steam Line leak in the drywell occurs o 10 minutes elapse and reactor parameters are:
- Reactor level.................. -108"
- Reactor pressure............ 600 psig Which ONE of the following systems can be used for injection for the current plant conditions?
A. HPCI B. RHR C. Reactor Feed Pump Turbine D. Condensate Booster Pump 39 of 75 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 39.
Unit 1 is at 10% power when a seismic event causes the following:
o 125/250 VDC Switchgear "lA" (lR22-S016) de-energizes o A Main Steam Line leak in the drywell occurs o 10 minutes elapse and reactor parameters are:
- Reactor level.................. -108"
- Reactor pressure............ 600 psig Which ONE of the following systems can be used for injection for the current plant conditions?
A. HPCI B. RHR C. Reactor Feed Pump Turbine D. Condensate Booster Pump 39 of 75
- 40.
Plant Hatch HL T 5 (2009-302) NRC RO Test Which ONE of the following completes both these statements?
The Main Turbine Bypass valves OPEN following a main turbine trip from full power to prevent _____ _
The pressure transmitter inputs used to control Bypass valve position sense _____ _
A. over pressurization of the Reactor vessel.
reactor pressure B. rupture LP Turbine rupture discs.
turbine inlet main stearn (throttle) pressure C. over pressurization of the Reactor vessel.
turbine inlet main stearn (throttle) pressure D. rupture LP Turbine rupture discs.
reactor pressure 40 of 75
- 40.
Plant Hatch HLT 5 (2009-302) NRC RO Test Which ONE of the following completes both these statements?
The Main Turbine Bypass valves OPEN following a main turbine trip from full power to prevent _____ _
The pressure transmitter inputs used to control Bypass valve position sense _____ _
A. over pressurization of the Reactor vessel.
reactor pressure B. rupture LP Turbine rupture discs.
turbine inlet main steam (throttle) pressure C. over pressurization of the Reactor vessel.
turbine inlet main steam (throttle) pressure D. rupture LP Turbine rupture discs.
reactor pressure 40 of 75
- 41.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is at 100% power when the Main Turbine trips and plant conditions are:
o Steam Flow, C32-R607................................... 2 mlbmfhr o Reactor Water Level, 2B21-D003B................ -1" and starting to increase Which ONE of the choices below completes the following statements?
IF level continues to rise, THEN a FWLC set point setdown will be active when Narrow Range indicates __.
This set down will cause the FW master controller (C32-R600) setpoint to be automatically changed to ___ _
A. +3"
+9" B. +3"
+20" C. +1"
+9" D. +1"
+20" 41 of 75
- 41.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is at 100% power when the Main Turbine trips and plant conditions are:
o Steam Flow, C32-R607................................... 2 mlbmlhr o Reactor Water Level, 2B2I-D003B................ -I" and starting to increase Which ONE of the choices below completes the following statements?
IF level continues to rise, THEN a FWLC set point setdown will be active when Narrow Range indicates __
This set down will cause the FW master controller (C32-R600) setpoint to be automatically changed to ___ _
A. +3"
+9" B. +3"
+20" C. +1"
+9" D. +1"
+20" 41 of 75
- 42.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is operating at 23% power when a leak develops in the Drywell. The following conditions exist at Time 13 :00:
o Drywell pressure is 1.1 psig and increasing @ 0.1 psi/minute o Drywell venting is underway per 34S0-T48-002-2" Containment Atmospheric Control And Dilution Systems" per section 7.1.3 "Primary Containment Venting" with both CAD Loops in service.
Which ONE of the following identifies; (1) The ADDmONAL vent path that is available AND (2) The EARLIEST time the operator is REQUIRED to close/confirm closed the Primary Containment vent valves assuming the additional vent path is NOT used?
A. (1) 2T48-F334A and 2T48-F335A, Drywell Vent Isolation valves (2) 13:02 B. (1) 2T48-F320 and 2T48-F319, Drywell Vent valves (2) 13:02 C. (1) 2T48-F334A and 2T48-F335A, Drywell Vent Isolation valves (2) 13:09 D. (1) 2T48-F320 and 2T48-F319, Drywell Vent valves (2) 13:09 42 of 75
- 42.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is operating at 23% power when a leak develops in the Drywell. The following conditions exist at Time l3:00:
o Drywell pressure is 1.1 psig and increasing @ 0.1 psi/minute o Drywell venting is underway per 34S0-T48-002-2" Containment Atmospheric Control And Dilution Systems" per section 7.1.3 "Primary Containment Venting" with both CAD Loops in service.
Which ONE of the following identifies; (1) The ADDITIONAL vent path that is available AND (2) The EARLIEST time the operator is REQUIRED to close!confirm closed the Primary Containment vent valves assuming the additional vent path is NOT used?
A. (1) 2T48-F334A and 2T48-F335A, Drywell Vent Isolation valves (2) l3:02 B. (1) 2T48-F320 and 2T48-F3l9, Drywell Vent valves (2) l3:02
- c. (1) 2T48-F334A and 2T48-F335A, Drywell Vent Isolation valves (2) l3:09 D. (1) 2T48-F320 and 2T48-F3l9, Drywell Vent valves (2) l3:09 42 of 75
Plant Hatch HL T 5 (2009-302) NRC RO Test
- 43.
Unit 1 is operating at 75% with the following conditions:
o Safety Relief Valve (SRV) "G" leaking past its seat o Suppression Pool temperature 102°P, (1 T47-R626) and increasing slowly Which ONE of the following choices completes BOTH statements?
Immediate entry into the EOP PC flowchart ___ required.
The LOWEST Torus temperature which requires placing the Rx Mode Switch in Shutdown occurs at a torus temperature of __
A. is 1200P B. is 1l0op C. is NOT 1200P D. is NOT 1l0op 43 of 75 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 43.
Unit 1 is operating at 75% with the following conditions:
o Safety Relief Valve (SRV) "G" leaking past its seat o Suppression Pool temperature 102°P, (1 T47-R626) and increasing slowly Which ONE of the following choices completes BOTH statements?
Immediate entry into the EOP PC flowchart ____ required.
The LOWEST Torus temperature which requires placing the Rx Mode Switch in Shutdown occurs at a torus temperature of ___ _
A. is l200P B. is 1100P C. is NOT 1200p D. is NOT 1100P 43 of 75
- 44.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 was at 4% when an auto-scram signal was received. The reactor operator inserted a manual scram, all immediate operator actions were taken and the following conditions currently exist:
o The 8 white RPS lights on 2HII-P603 are illuminated o Full core display blue lights are all extinguished Which ONE of the following identifies the current status of "APRM Downscale" (603-228) annuciator and the required operator action IA W 34AB-Cl1-005-2, Control Rod Insertion Methods?
A. llluminated; Individually scram control rods B. llluminated; Place RPS Test Trip Logic Switches to TRIP C. Extinguished; Individually scram control rods D. Extinguished; Place RPS Test Trip Logic Switches to TRIP 44 of 75
- 44.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 was at 4% when an auto-scram signal was received. The reactor operator inserted a manual scram, all immediate operator actions were taken and the following conditions currently exist:
o The 8 white RPS lights on 2H11-P603 are illuminated o Full core display blue lights are all extinguished Which ONE of the following identifies the current status of "APRM Downscale" (603-228) annuciator and the required operator action IA W 34AB-C 11-005-2, Control Rod Insertion Methods?
A. llluminated; Individually scram control rods B. llluminated; Place RPS Test Trip Logic Switches to TRIP C. Extinguished; Individually scram control rods D. Extinguished; Place RPS Test Trip Logic Switches to TRIP 44 of 75
- 45.
Plant Hatch HLT 5 (2009-302) NRC RD Test Unit 2 is at 100% power when the following occurs:
o A fIre starts in the Control Room o The following procedures are entered and ALL Immediate Operator actions are COMPLETE:
- 31RS-OPS-001-2, "Shutdown from Outside the Control Room"
- 34AB-C71-001-2, "Scram Procedure"
- 34AB-X43-001-2, "Fire Procedure" IA W 31RS-OPS-001-2, which ONE of the following conditions would REQUIRE closing the MSIVs?
A. Reactor water level decreases from +30" to -30" over 30 minutes B. Reactor pressure decreases from 1000 psig to 350 psig over 30 minutes C. Turbine Building steam line area temperatures at 175°F D. Main Steam line pressure 850 psig 45 of 75
- 45.
Plant Hatch HLT 5 (2009-302) NRC RD Test Dnit 2 is at 100% power when the following occurs:
o A fIre starts in the Control Room o The following procedures are entered and ALL Immediate Operator actions are COMPLETE:
- 3IRS-OPS-001-2, "Shutdown from Outside the Control Room"
- 34AB-C71-00l-2, "Scram Procedure"
- 34AB-X43-00l-2, "Fire Procedure" IA W 3IRS-OPS-001-2, which ONE of the following conditions would REQUIRE closing the MSIVs?
A. Reactor water level decreases from +30" to -30" over 30 minutes B. Reactor pressure decreases from 1000 psig to 350 psig over 30 minutes C. Turbine Building steam line area temperatures at 175°F D. Main Steam line pressure 850 psig 45 of 75
- 46.
Plant Hatch HLT 5 (2009-302) NRC RD Test Unit 1 is operating at 5% power and the following conditions exist:
o Reactor Water Cleanup (RWCU) is being used for reactor water level control o RBCCW Heat Exchanger outlet temperature has risen to 95°F o The Shift Supervisor directs PSW flow through the heat exchanger (Hx) to be increased by opening the IP41-F206A, RBCCW Hx PSW discharge valve Which ONE of the following completes this statement?
During RWCU blowdown operations, opening IP41-F206A will and this will
___ the differential pressure (delta P) between PSW and RBCCW.
A. raise the RWCU return temperature to the vessel in the Regenerative Heat Exchanger; decrease (less dP).
B. raise the RWCU return temperature to the vessel in the Regenerative Heat Exchanger; increase (more dP)
C. lower the RWCU Non-Regenerative Heat Exchanger outlet temperature; decrease (less dP)
D. lower the RWCU Non-Regenerative Heat Exchanger outlet temperature; increase (more dP) 46 of 75
- 46.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is operating at 5% power and the following conditions exist:
o Reactor Water Cleanup (RWCU) is being used for reactor water level control o RBCCW Heat Exchanger outlet temperature has risen to 95°F o The Shift Supervisor directs PSW flow through the heat exchanger (Hx) to be increased by opening the lP41-F206A, RBCCW Hx PSW discharge valve Which ONE of the following completes this statement?
During RWCU blowdown operations, opening IP41-F206A will ____ and this will
___ the differential pressure (delta P) between PSW and RBCCW.
A. raise the RWCU return temperature to the vessel in the Regenerative Heat Exchanger; decrease (less dP).
B. raise the RWCU return temperature to the vessel in the Regenerative Heat Exchanger; increase (more dP)
C. lower the RWCU Non-Regenerative Heat Exchanger outlet temperature; decrease (less dP)
D. lower the RWCU Non-Regenerative Heat Exchanger outlet temperature; increase (more dP) 46 of 75
- 47.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is operating at 100% power when a total loss of Instrument Air occurs.
With no operator actions, which ONE of the following identifies how the Reactor Building differential pressure (dP) and the SBGT Filter Inlet dampers from the Reactor Building will be affected by the loss of Instrument Air?
The Reactor Building differential pressure (delta P) will trend towards ____ and the SBGT Inlet Dampers from the Reactor Building will fail __ _
A. 0 inches water (less negative);
open B. 0 inches water (less negative);
closed
- c. -0.6 inches water (more negative);
open D. -0.6 inches water (more negative);
closed 47 of 75
- 47.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is operating at 100% power when a total loss of Instrument Air occurs.
With no operator actions, which ONE of the following identifies how the Reactor Building differential pressure (dP) and the SBGT Filter Inlet dampers from the Reactor Building will be affected by the loss of Instrument Air?
The Reactor Building differential pressure (delta P) will trend towards ____ and the SBGT Inlet Dampers from the Reactor Building will fail __ _
A. 0 inches water (less negative);
open B. 0 inches water (less negative);
closed C. -0.6 inches water (more negative);
open D. -0.6 inches water (more negative);
closed 47 of 75
- 48.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is at 60% power when Inboard MSIV 2B21-F022A and Outboard MSIV 2B21-F028A inadvertently fail closed.
Which ONE of the choices below completes the following statement?
INITIALLY, reactor power will ____ and a RPS half scram signal ____ be generated.
A. increase; will B. increase; will NOT
- c. remain the same; will D. remain the same; will NOT 48 of 75
- 48.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is at 60% power when Inboard MSIV 2B21-F022A and Outboard MSIV 2B21-F028A inadvertently fail closed.
Which ONE of the choices below completes the following statement?
INITIALLY, reactor power will ____ and a RPS half scram signal ____ be generated.
A. increase; will B. increase; will NOT
- c. remain the same; will D. remain the same; will NOT 48 of 75
- 49.
Plant Hatch HL T 5 (2009-302) NRC RD Test Unit 2 is shutdown with the following conditons o Rx pressure............................... 134 psig o "2A" Rx Recirculation pump...... Running o "2B" Rx Recirculation pump...... Off Which ONE of the choices below completes BOTH the following statement?
IA W Tech Spec 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown" the MINMUM number of RHR Shutdown Cooling (SDC) subsystems required to be operable, (without requiring entry into a Required Action Statement) (RAS), is __ _
Also, IA W with Tech Spec 3.4.7 and with current plant conditions, ___ RHR SDC subsystem is required to be in operation.
A. one; one B. one; neither C. two; one D. two; neither 49 of 75
- 49.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is shutdown with the following conditons o Rx pressure............................... 134 psig o "2A" Rx Recirculation pump...... Running o "2B" Rx Recirculation pump...... Off Which ONE of the choices below completes BOTH the following statement?
IA W Tech Spec 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown" the MINMUM number of RHR Shutdown Cooling (SDC) subsystems required to be operable, (without requiring entry into a Required Action Statement) (RAS), is __ _
Also, IA W with Tech Spec 3.4.7 and with current plant conditions, ____ RHR SDC subsystem is required to be in operation.
A. one; one B. one; neither C. two; one D. two; neither 49 of 75
- 50.
Plant Hatch HLT 5 (2009-302) NRC RO Test An irradiated fuel bundle is in the "FULL-UP" position on the Unit 2 Refueling Bridge Main Grapple and is being moved from the Unit 1 to the Unit 2 Fuel Pool. An equipment malfunction prevents Bridge movement and the bundle CANNOT be lowered.
o The Fuel Pool Transfer Canal seals deflate which causes Fuel Pool water level to decrease to its lowest possible level o The 2D21-K601A and 2D21-K601M Area Radiation Monitors (ARM) red TRIP lights illuminate and the local alarm horn sounds Which ONE of the following completes both of the following statements?
Fuel Pool Water level will ___ the top of the Fuel Bundle.
When local radiation levels drop below the ARM trip setpoint, the ARM local horn alarm A. remain above will automatically silence (reset)
B. remain above must be manually silenced (reset) at 2D21-P600 ARM Panel C. go below will automatically silence (reset)
D. go below must be manually silenced (reset) at 2D21-P600 ARM Panel 50 of 75
- 50.
Plant Hatch HL T 5 (2009-302) NRC RO Test An irradiated fuel bundle is in the "FULL-UP" position on the Unit 2 Refueling Bridge Main Grapple and is being moved from the Unit 1 to the Unit 2 Fuel Pool. An equipment malfunction prevents Bridge movement and the bundle CANNOT be lowered.
o The Fuel Pool Transfer Canal seals deflate which causes Fuel Pool water level to decrease to its lowest possible level o The 2D21-K601A and 2D21-K601M Area Radiation Monitors (ARM) red TRIP lights illuminate and the local alarm hom sounds Which ONE of the following completes both of the following statements?
Fuel Pool Water level will ___ the top of the Fuel Bundle.
When local radiation levels drop below the ARM trip setpoint, the ARM local hom alarm A. remain above will automatically silence (reset)
B. remain above must be manually silenced (reset) at 2D21-P600 ARM Panel C. go below will automatically silence (reset)
D. go below must be manually silenced (reset) at 2D21-P600 ARM Panel 50 of 75
- 51.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 was at 100% power when a LOCA occurred and the Narrow Range and Floodup Range instruments trended a lowering RWL until they all went downscale.
Current plant conditions are:
o Reactor pressure.............................. 60 psig o Reactor Level indications
- Narrow Range.............................. downscale
- Floodup........................................ downscale
- Wide Range.................................. -50", erratic
- Fuel Zone...................................... -60", erratic o Drywell pressure.............................. 5 psig o Drywell average ternperature............ at RPV Saturation Temperature Which ONE of the choices below completes the following statement?
Drywell sprays ____ be initiated and entry into BOP CP-2, "RPV Flooding" __ _
required.
REFERENCE PROVIDED A. can; is NOT B. can; is C. canNOT; is NOT D. canNOT; is 51 of 75
- 51.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 was at 100% power when a LOCA occurred and the Narrow Range and Floodup Range instruments trended a lowering RWL until they all went downscale.
Current plant conditions are:
o Reactor pressure.............................. 60 psig o Reactor Level indications
- Narrow Range.............................. downscale
- Floodup........................................ downscale
- Wide Range.................................. -50", erratic
- Fuel Zone...................................... -60", erratic o Drywell pressure.............................. 5 psig o Drywell average temperature............ at RPV Saturation Temperature Which ONE of the choices below completes the following statement?
Drywell sprays ____ be initiated and entry into EOP CP-2, "RPV Flooding" __ _
required.
REFERENCE PROVIDED A. can; is NOT B. can; is C. canNOT; is NOT D. canNOT; is 51 of 75
- 52.
Plant Hatch HL T 5 (2009-302) NRC RO Test 31EO-EOP-107-2, "ALTERNATE RPV PRESSURE CONTROL" is in progress.
o The RCIC system is being used to control reactor pressure.
o The 2E51-R612, "RCIC flow controller," is in automatic, with the setpoint at 300 gpm.
Which ONE of the following completes the statement below in accordance with 31EO-EOP-107-2?
To DECREASE the reactor cooldown rate (CDR), the operator is required to use __ _
and ---
A. 2E51-R612, "RCIC flow controller,"
RAISE the setpoint B. 2E51-R612, "RCIC flow controller,"
LOWER the setpoint C. 2E41-FOll, "Test to CST VLV,"
throttle it in the CLOSE direction D. 2E41-FOll, "Test to CST VLV,"
throttle it in the OPEN direction 52 of 75
- 52.
Plant Hatch HL T 5 (2009-302) NRC RO Test 31EO-EOP-107-2, "ALTERNATE RPV PRESSURE CONTROL" is in progress.
o The RCIC system is being used to control reactor pressure.
o The 2E51-R612, "RCIC flow controller," is in automatic, with the setpoint at 300 gpm.
Which ONE of the following completes the statement below in accordance with 31EO-EOP-107-2?
To DECREASE the reactor cooldown rate (CDR), the operator is required to use __ _
and __ _
A. 2E51-R612, "RCIC flow controller,"
RAISE the setpoint B. 2E51-R612, "RCIC flow controller,"
LOWER the setpoint C. 2E41-FOll, "Test to CST VLV,"
throttle it in the CLOSE direction D. 2E41-FOll, "Test to CST VLV,"
throttle it in the OPEN direction 52 of 75
- 53.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is at 100% power when the following occurs:
o SRV "C" has failed open o Torus temperature reaches 180°F Which ONE of the choices below identifies the reason that emergency depressurization is required when torus temperature can not be maintained below the Heat Capacity Temperature Limit Curve IA W the Hatch EOP "Plant Specific Technical Guideline, Appendix A"?
A. Ensures that the suppression chamber and its equipment do not fail when required to operate during an emergency depressurization (blowdown).
B. Ensures that ECCS pumps maintain adequate net positive suction head and available for adequate core cooling.
C. Ensures that suppression chamber torus temperature is maintained less then the Boron Injection Initiation Temperature.
D. Ensures that chugging in the downcomers does not occur which could cause failure of the downcomer vents.
53 of 75
- 53.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is at 100% power when the following occurs:
o SRV "C" has failed open o Torus temperature reaches 180°F Which ONE of the choices below identifies the reason that emergency depressurization is required when torus temperature can not be maintained below the Heat Capacity Temperature Limit Curve IA W the Hatch EOP "Plant Specific Technical Guideline, Appendix A"?
A. Ensures that the suppression chamber and its equipment do not fail when required to operate during an emergency depressurization (blowdown).
B. Ensures that ECCS pumps maintain adequate net positive suction head and available for adequate core cooling.
C. Ensures that suppression chamber torus temperature is maintained less then the Boron Injection Initiation Temperature.
D. Ensures that chugging in the downcomers does not occur which could cause failure of the downcomer vents.
53 of 75
- 54.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is operating at 100% power with the 2B Drywell (DW) Chiller tagged out when a loss of the 2A DW Chiller occurs.
When repair of the 2A DW Chiller is complete, the following conditions exist:
o Drywell Pressure:.................................. 2.2 psig o Bulk Average Drywell Temperature:.... 275°P Which ONE of the following completes the following statement?
lAW 31EO-EOP-100-2, "Miscellaneous Emergency Overrides", the"2A" DW Chiller __ _
A. is NOT allowed to be restarted because at this DW temperature the potential for a rupture in the DW cooler OUTLET piping exists.
B. is NOT allowed to be restarted because at this DW temperature the potential for a rupture in the DW cooler INLET piping exists.
C. is allowed to be restarted. The operator must first place the LOCA override switch to "BYPASS" and then reset the 86 Lockout relay at the DW Chiller breaker.
D. is allowed to be restarted. The operator must first reset the 86 Lockout relay at the DW Chiller breaker and then place the LOCA override switch to "BYPASS".
54 of 75
- 54.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is operating at 100% power with the 2B Drywell (DW) Chiller tagged out when a loss of the 2A DW Chiller occurs.
When repair of the 2A DW Chiller is complete, the following conditions exist:
o Drywell Pressure:.................................. 2.2 psig o Bulk Average Drywell Temperature:.... 275°F Which ONE of the following completes the following statement?
IA W 31EO-EOP-100-2, "Miscellaneous Emergency Overrides", the"2A" DW Chiller __ _
A. is NOT allowed to be restarted because at this DW temperature the potential for a rupture in the DW cooler OUTLET piping exists.
B. is NOT allowed to be restarted because at this DW temperature the potential for a rupture in the DW cooler INLET piping exists.
C. is allowed to be restarted. The operator must first place the LOCA override switch to "BYPASS" and then reset the 86 Lockout relay at the DW Chiller breaker.
D. is allowed to be restarted. The operator must first reset the 86 Lockout relay at the DW Chiller breaker and then place the LOCA override switch to "B YP ASS".
54 of 75
- 55.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is operating at 100% power when a Loss of Coolant Accident occurs. The High Pressure Coolant Injection (HPCI) system is being used to control RPV water level.
o HPCI flow rate............................... 3,500 gpm o RWL.............................................. -80" and increasing at 1" per minute o RHR Loop "A" is in Suppression Pool Cooling o Torus level..................................... 135 inches o Torus temperature.......................... 2100 P o Suppression Chamber Pressure...... 6 psig Which ONE of the following choices completes this statement?
AI>
HPCI pump operation is acceptable NPSH afta Vertex LiB3.its-and REFERENCE PROVIDED A. within; flow is required to be increased B. within; flow must be maintained at or below its current flow rate C. outside of; reducing flow to 3,000 gpm will NOT restore acceptable operation for NPSH aBa Vel1s1( liHlits AI>
D. outside of; reducing flow to 3,000 gpm will restore acceptable operation for NPSH~
'lel1M limi~'"
55 of 75
- 55.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is operating at 100% power when a Loss of Coolant Accident occurs. The High Pressure Coolant Injection (HPCI) system is being used to control RPV water level.
o HPCI flow rate............................... 3,500 gpm o RWL.............................................. -80 1t and increasing at lit per minute o RHR Loop ItAIt is in Suppression Pool Cooling o Torus level..................................... 135 inches o Torus temperature.......................... 21 oop o Suppression Chamber Pressure...... 6 psig Which ONE of the following choices completes this statement?
A&
HPCI pump operation is acceptable NPSH ana Voncx Limits and REFERENCE PROVIDED A. within; flow is required to be increased B. within; flow must be maintained at or below its current flow rate C. outside of; reducing flow to 3,000 gpm will NOT restore acceptable operation for NPSH aad Vorteu limits A6 D. outside of; reducing flow to 3,000 gpm will restore acceptable operation for NPSH~
Vort~ limiffi-~
55 of 75
- 56.
Plant Hatch HL T 5 (2009-302) NRC RD Test Unit 1 is at 100% power when the following occurs:
o All normal feedwater is lost o Reactor Scram o Rx Pressure................................. 985 psig o Reactor Water LeveL................. -45" o RCIC Flow Controller (E51-R612) Indications:
- Flow Indication.................................................... 500 GPM
- Auto Green LED................................................... llluminated
- Demand Output.................................................... 0 o RCIC Turb Speed (E51-R61O)................................ 300 RPM o RCIC Pump Disch Press (E51-R601)...................... 50 psig Which ONE of the choices below completes the following statement?
RCIC flow controller is required to be ___ _
A. left in Automatic, and RCIC injection flow will start increasing reactor vessel level B. left in Automatic, but RCIC should be tripped because it is pumping 500 gpm through a feedwater line break C. placed in Manual, and the controller output should be increased until discharge pressure is greater than 985 psig D. placed in Manual, but the controller output should be decreased until RCIC flow is 400 gpm.
56 of 75
- 56.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is at 100% power when the following occurs:
o All normal feedwater is lost o Reactor Scram o Rx Pressure................................. 985 psig o Reactor Water LeveL................. -45" o RCIC Flow Controller (E51-R612) Indications:
- Flow Indication.................................................... 500 GPM
- Auto Green LED................................................... lllurninated
- Demand Output.................................................... 0 o RCIC Turb Speed (E51-R61O)................................ 300 RPM o RCIC Pump Disch Press (E51-R601)...................... 50 psig Which ONE of the choices below completes the following statement?
RCIC flow controller is required to be ___ _
A. left in Automatic, and RCIC injection flow will start increasing reactor vessel level B. left in Automatic, but RCIC should be tripped because it is pumping 500 gpm through a feedwater line break C. placed in Manual, and the controller output should be increased until discharge pressure is greater than 985 psig D. placed in Manual, but the controller output should be decreased until RCIC flow is 400 gpm.
56 of 75
- 57.
Plant Hatch HL T 5 (2009-302) NRC RO Test Both Unit 1 and Unit 2 are at 100% power when the following occurs on Unit 2:
o HPCI Steam Line................................................. break occurs in the HPCI room o Reactor Building HV AC......................................isolated o SBGTs.................................................................. auto start on high radiation o HPCI Pump Room Area Temp (2E41-N024)...... 145°P, rising lOOP/min Which ONE of the choices below completes both of the following statements?
IA W 34S0-T46-00l-2 "Standby Gas Treatment System", the operator is required to ___ _
to limit the release of radioactive material.
IA W the 31EO-EOP-0l4-2, SC flowchart, the Unit 2 Reactor Building HV AC is required to be A. place one SBGT in standby; left isolated B. place one SBGT in standby; restarted C. operate both SBGTs; left isolated D. operate both SBGTs; restarted 57 of 75
- 57.
Plant Hatch HLT 5 (2009-302) NRC RO Test Both Unit 1 and Unit 2 are at 100% power when the following occurs on Unit 2:
o HPCI Steam Line................................................. break: occurs in the HPCI room o Reactor Building HV AC......................................isolated o SBGTs.................................................................. auto start on high radiation o HPCI Pump Room Area Temp (2E41-N024)...... 145°P, rising lOOP/min Which ONE of the choices below completes both of the following statements?
lAW 34S0-T46-001-2 "Standby Gas Treatment System", the operator is required to ___ _
to limit the release of radioactive material.
lAW the 31EO-EOP-014-2, SC flowchart, the Unit 2 Reactor Building HVAC is required to be A. place one SBGT in standby; left isolated B. place one SBGT in standby; restarted C. operate both SBGTs; left isolated D. operate both SBGTs; restarted 57 of 75
- 58.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 1 is in a startup with the following conditions:
o lT4l-C004A, Rx Bldg Vent Accessible Area Exh Fan.......... Running o 1 T4l-C007 A, Rx Bldg Vent Inaccessible Area Exh Fan........ Running o lT4l-COOlA, Rx Bldg Vent Supply Fan................................. Running o lT4l-COOlB, Rx Bldg Vent Supply Fan................................. Tagged Out Which ONE of the choices below completes the following statement?
If 1 T4l-COO lA, Rx Bldg Vent Supply Fan trips, the two running Reactor Building Area Exhaust Fans ___ _
A. will automatically trip to prevent opening of the tornado vents B. will automatically trip because there are no running supply fans C. will remain running and are required to be tripped to prevent excessive negative dP on the building D. will remain running and are required to continue running to ensure monitoring of potential off-site releases 58 of 75
- 58.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is in a startup with the following conditions:
o 1 T4l-C004A, Rx Bldg Vent Accessible Area Exh Fan.......... Running o I T4l-C007 A, Rx Bldg Vent Inaccessible Area Exh Fan........ Running o I T41-COO lA, Rx Bldg Vent Supply Fan................................. Running o I T4l-COO IB, Rx Bldg Vent Supply Fan................................. Tagged Out Which ONE of the choices below completes the following statement?
If I T41-COO lA, Rx Bldg Vent Supply Fan trips, the two running Reactor Building Area Exhaust Fans ___ _
A. will automatically trip to prevent opening of the tornado vents B. will automatically trip because there are no running supply fans C. will remain running and are required to be tripped to prevent excessive negative dP on the building D. will remain running and are required to continue running to ensure monitoring of potential off-site releases 58 of 75
- 59.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 1 was at 100% power when the following occurs:
o A scram occurs o Not all rods inserted Which ONE of the below choices completes the following statements lAW 3 1 EO-EOP-O 11-1,
RCA flowchart?
The HIGHEST APRM power indication which allows the operator to use 34AB-C11-005-1, Control Rod Insertion Methods, to insert rods is __ _
Boron injection is required when APRMs exceed a MINIMUM peak to peak oscillation of A. 4%
10%
B. 4%
25%
C. 13%
10%
D. 13%
25%
59 of 75
- 59.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 was at 100% power when the following occurs:
o A scram occurs o Not all rods inserted Which ONE of the below choices completes the following statements IA W 3 I EO-EOP-Ol 1-1, RCA flowchart?
The HIGHEST APRM power indication which allows the operator to use 34AB-CII-005-1, Control Rod Insertion Methods, to insert rods is ___ _
Boron injection is required when APRMs exceed a MINIMUM peak to peak oscillation of A. 4%
10%
B. 4%
25%
C. 13%
10%
D. 13%
25%
59 of 75
- 60.
Plant Hatch HLT 5 (2009-302) NRC RO Test A General emergency has been declared on Unit 2.
The control room operator is performing a prompt offsite dose assessment in accordance with 73EP-EIP-005-0, On Shift Operations Personnel Emergency Duties and 73 EP-EIP-O I 8-0, Prompt Offsite Dose Assessment (PODA).
Which ONE of the below choices completes the following statements?
fu order to obtain release assessment information for an ELEV A TED release, the operator will use the value from 1 Y33-R603, 100 Meter Wind Speed recorder on IHll-P690 panel.
A wind direction of 90 degrees means that the wind is blowing _____ the East.
A. 15 minute average to B. 15 minute average from C. instantaneous from D. instantaneous to 60 of 75
- 60.
Plant Hatch HLT 5 (2009-302) NRC RO Test A General emergency has been declared on Unit 2.
The control room operator is performing a prompt offsite dose assessment in accordance with 73EP-EIP-005-0, On Shift Operations Personnel Emergency Duties and 73EP-EIP-018-0, Prompt Offsite Dose Assessment (PODA).
Which ONE of the below choices completes the following statements?
ill order to obtain release assessment information for an ELEV A TED release, the operator will use the value from 1 Y33-R603, 100 Meter Wind Speed recorder on IHII-P690 paneL A wind direction of 90 degrees means that the wind is blowing _____ the East.
A. 15 minute average to B. 15 minute average from C. instantaneous from D. instantaneous to 60 of 75
- 61.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is at 100% power with the following conditions:
o A Service Air Header break has occured o The break is greater than the capacity of the Service Air Compressors Which ONE of the choices below completes the following two statements?
A.
B.
C.
D.
As air pressure decreases, 2P51-FOI7, Turbine Building Service Air Isolation Valve, will isolate at If 2P51-F017 fails to isolate OR pressure continues to decrease, 2P52-FOI5, Non-Essential Inst. Air Isolation Valve, will isolate at __.
80 psig; 61 psig 80 psig; 50 psig 70 psig; 61 psig 70 psig; 50 psig 61 of 75
- 61.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is at 100% power with the following conditions:
o A Service Air Header break has occured o The break is greater than the capacity of the Service Air Compressors Which ONE of the choices below completes the following two statements?
A.
B.
C.
D.
As air pressure decreases, 2P51-FO 17, Turbine Building Service Air Isolation Valve, will isolate at If 2P51-F017 fails to isolate OR pressure continues to decrease, 2P52-F015, Non-Essential Inst. Air Isolation Valve, will isolate at __.
80 psig; 61 psig 80 psig; 50 psig 70 psig; 61 psig 70 psig; 50 psig 61 of 75
Plant Hatch HLT 5 (2009-302) NRC RO Test
- 62.
Unit 1 is at 100% power when the following annunciators alarm:
o 600V BUS ID BREAKER TRIPPED, 652-318 o 600V BUS ID UNDERVOLTAGE, 652-323 Which ONE of the following lists two components that have lost power?
A. Station Service Air Compressor A; RBCCW Drywell Inlet Isolation Valve (P42-F051)
B. Station Service Air Compressor A; RWCU Inboard Suction Isolation Valve (G31-FOOl)
C. Station Service Air Compressor B; RBCCW Drywell Inlet Isolation Valve (P42-F051)
D. Station Service Air Compressor B; RWCU Inboard Suction Isolation Valve (G31-FOOl) 62 of 63 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 62.
Unit 1 is at 100% power when the following annunciators alarm:
o 600V BUS ID BREAKER TRIPPED, 652-318 o 600V BUS ID UNDERVOLTAGE, 652-323 Which ONE of the following lists two components that have lost power?
A. Station Service Air Compressor A; RBCCW Drywell Inlet Isolation Valve (P42-F05l)
B. Station Service Air Compressor A; RWCU Inboard Suction Isolation Valve (G31-FOOl)
C. Station Service Air Compressor B; RBCCW Drywell Inlet Isolation Valve (P42-F051)
D. Station Service Air Compressor B; RWCU Inboard Suction Isolation Valve (G31-FOOl) 62 of 63
- 63.
Plant Hatch HLT 5 (2009-302) NRC RO Test A LOCA occurred on Unit 2 which resulted in the following Oxygen/Hydrogen concentrations in both the Drywell and Torus spaces:
TIME OXYGEN %
HYDROGEN %
0100 4
3 0130 5
4 0200 6
5 0230 7
6 IA W 3IEO-PCG-00l-2, "Primary Containment Gas Control", which ONE of the following identifies the EARLIEST time that torus spray is required, irrespective of Adequate Core Cooling?
REFERENCE PROVIDED A. 0100 B. 0130 C. 0200 D. 0230 63 of 75
- 63.
Plant Hatch HLT 5 (2009-302) NRC RO Test A LOCA occurred on Unit 2 which resulted in the following Oxygen/Hydrogen concentrations in both the Drywell and Torus spaces:
TTIME OXYGEN %
HYDROGEN %
0100 4
3 0130 5
4 0200 6
5 0230 7
6 IA W 3 1 EO-PCG-OO 1-2, "Primary Containment Gas Control", which ONE of the following identifies the EARLIEST time that torus spray is required, irrespective of Adequate Core Cooling?
REFERENCE PROVIDED A. 0100 B. 0130 C. 0200 D. 0230 63 of 75
- 64.
Plant Hatch HL T 5 (2009-302) NRC RO Test Which ONE of the following plant fire locations requires a manual reactor scram IA W 34AB-X43-001-2, "Fire Procedure", when a major fire exists.
A. Unit Auxilary Transformer B. Turbine Building Unit 2 East Cableway C. Oil Storage Tank Room D. Intake Structure 64 of 75
- 64.
Plant Hatch HLT 5 (2009-302) NRC RO Test Which ONE of the following plant fire locations requires a manual reactor scram IA W 34AB-X43-001-2, "Fire Procedure", when a major fire exists.
A. Unit Auxilary Transformer B. Turbine Building Unit 2 East Cableway C. Oil Storage Tank Room D. Intake Structure 64 of 75
- 65.
Plant Hatch HL T 5 (2009-302) NRC RO Test Both units are operating at 100% power. On paneIIHII-P653, the 230 KV voltmeter IS40-R600 indicates 228 KV and is fluctuating +/-2 KV.
The NCC has notified the control room crews that 230 KV Bus voltage cannot be maintained above the normal minimum voltage.
Which ONE of the following identifies how reactive load can be raised AND a required action lAW 34AB-Sll-00I-0, "Operation With Degraded System Voltage"?
A. Placing the REGULATOR VOLTAGE ADJUST control switch to the RAISE position; Initiate a one hour Required Action Statement.
B. Selecting LOAD SET and then RAISE at the HMI Screen; Initiate a one hour Required Action Statement.
C. Placing the REGULATOR VOLTAGE ADJUST control switch to the RAISE position; Transfer Station Service Busses to their alternate supply.
D. Selecting LOAD SET and then RAISE at the HMI Screen; Transfer Station Service Busses to their alternate supply.
65 of 75
- 65.
Plant Hatch HLT 5 (2009-302) NRC RO Test Both units are operating at 100% power. On paneIIHII-P653, the 230 KV voltmeter IS40-R600 indicates 228 KV and is fluctuating +/-2 KV.
The NCC has notified the control room crews that 230 KV Bus voltage cannot be maintained above the normal minimum voltage.
Which ONE of the following identifies how reactive load can be raised AND a required action IA W 34AB-Sll-00I-0, "Operation With Degraded System Voltage"?
A. Placing the REGULATOR VOLTAGE ADJUST control switch to the RAISE position; Initiate a one hour Required Action Statement.
B. Selecting LOAD SET and then RAISE at the HMI Screen; Initiate a one hour Required Action Statement.
C. Placing the REGULATOR VOLTAGE ADJUST control switch to the RAISE position; Transfer Station Service Busses to their alternate supply.
D. Selecting LOAD SET and then RAISE at the HMI Screen; Transfer Station Service Busses to their alternate supply.
65 of 75
- 66.
Plant Hatch HLT 5 (2009-302) NRC RO Test Which ONE of the following identifies the required communication protocol during transients in accordance with DI-OPS-59-896, Operations Management Expectations, Attachment 5, Strategies For Successful Transient Mitigation?
A. A crew update is required to be preceded by an annunciator check. A crew update is a tool used primarily by the Shift Supervisor.
B. A crew update is required to be preceded by an annunciator check. A crew update is a short transfer of information from anyone on the crew to the rest of the crew.
C. A crew brief is required to be preceded by an annunciator check. A crew brief is a tool used primarily by the Shift Supervisor.
D. A crew brief is required to be preceded by an annunciator check. A crew brief is a short transfer of information from anyone on the crew to the rest of the crew.
66 of 75
- 66.
Plant Hatch HLT 5 (2009-302) NRC RO Test Which ONE of the following identifies the required communication protocol during transients in accordance with DI-OPS-59-896, Operations Management Expectations, Attachment 5, Strategies For Successful Transient Mitigation?
A. A crew update is required to be preceded by an annunciator check. A crew update is a tool used primarily by the Shift Supervisor.
B. A crew update is required to be preceded by an annunciator check. A crew update is a short transfer of information from anyone on the crew to the rest of the crew.
- c. A crew brief is required to be preceded by an annunciator check. A crew brief is a tool used primarily by the Shift Supervisor.
D. A crew brief is required to be preceded by an annunciator check. A crew brief is a short transfer of information from anyone on the crew to the rest of the crew.
66 of 75
- 67.
Plant Hatch HL T 5 (2009-302) NRC RD Test Unit 2 is in a plant startup with the following conditions:
o RWCU "A" pump in service o RWCU Filter Demineralizer (FID) "A" is out of service o RWCU Filter Demineralizer (FID) "B" is being placed in service Which ONE of the choices below answers both of the following statements?
IA W 34S0-G31-003-2 "Reactor Water Cleanup System":
A.
B.
C.
D.
As the Systems Operator increases flow through the "B" FID, the Control Room Operator is required to throttle closed 2G31-F044, Demin Bypass valve, with a final position of
___ when the "B" FID is fully in service.
As FID flow is increased, if annuciator "RWCU FILTER DEMIN FAILURE" (602-433) alarms, the cause can be determined by looking for additional alarms on panel ___ _
partially closed; 2HII-P602 partially closed; 2G31-POOI fully closed; 2HII-P602 fully closed; 2G31-POOI 67 of 75
- 67.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 2 is in a plant startup with the following conditions:
o RWCU "A" pump in service o RWCU Filter Demineralizer (FID) "A" is out of service o RWCU Filter Demineralizer (FID) "B" is being placed in service Which ONE of the choices below answers both of the following statements?
IA W 34S0-G31-003-2 "Reactor Water Cleanup System":
A.
B.
C.
D.
As the Systems Operator increases flow through the "B" FID, the Control Room Operator is required to throttle closed 2G31-F044, Demin Bypass valve, with a final position of
___ when the "B" FID is fully in service.
As FID flow is increased, if annuciator "RWCU FILTER DEMIN FAILURE" (602-433) alarms, the cause can be determined by looking for additional alarms on panel ___ _
partially closed; 2HII-P602 partially closed; 2G31-POOI fully closed; 2HII-P602 fully closed; 2G31-POOI 67 of 75
- 68.
Plant Hatch HL T 5 (2009-302) NRC RO Test Unit 1 has experienced a transient. HPCI has failed to start and reactor water level (RWL) is decreasing.
lAW DI-OPS-59-0896, Operations Management Expectations, which ONE of the choices below completes BOTH of the following statements?
When reporting the HPCI failure to the Shift Supervisor, the operator ___ required to use the Shift Supervisor's name or title.
If the operator provides the exact value of RWL to the Shift Supervisor, then the operator
___ required to provide the trend direction.
A. is; is still B. is; is NOT C. is NOT; is still D. is NOT; is NOT 68 of 75
- 68.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 has experienced a transient. HPCI has failed to start and reactor water level (RWL) is decreasing.
IA W DI-OPS-59-0896, Operations Management Expectations, which ONE of the choices below completes BOTH of the following statements?
When reporting the HPCI failure to the Shift Supervisor, the operator ___ required to use the Shift Supervisor's name or title.
If the operator provides the exact value of R WL to the Shift Supervisor, then the operator
___ required to provide the trend direction.
A. is; is still B. is; is NOT C. is NOT; is still D. is NOT; is NOT 68 of 75
Plant Hatch HL T 5 (2009-302) NRC RO Test
- 69.
Unit 1 is in cold shutdown with:
o Mode Switch in SHUTDOWN o Pre-startup activities underway Which ONE of the choices below completes the following statement?
IA W 34GO-OPS-OOI-I, "Plant Startup", in order to perform RWM Operability Check the refuel bridge is required to be and the mode switch is required to be placed in __ _
A. de-energized; REFUEL B. de-energized; START /HOT STBY C. energized; REFUEL D. energized; START /HOT STBY 69 of 75 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 69.
Unit 1 is in cold shutdown with:
o Mode Switch in SHUTDOWN o Pre-startup activities underway Which ONE of the choices below completes the following statement?
lAW 34GO-OPS-OOI-I, "Plant Startup", in order to perform RWM Operability Check the refuel bridge is required to be and the mode switch is required to be placed in ___ _
A. de-energized; REFUEL B. de-energized; START /HOT STBY C. energized; REFUEL D. energized; START /HOT STBY 69 of 75
- 70.
Plant Hatch HLT 5 (2009-302) NRC RO Test During performance of 34SV-R43-001-2, "Diesel Generator 2A Monthly Surveillance", in preparation for barring over Diesel Generator 2A, the Systems Operator has just placed the local switch for Diesel Generator 2A to "AT ENG" and depressed the emergency stop pushbutton.
Which ONE of the below choices completes the following statements?
The 2A Diesel Generator ____ REQUIRED to be declared inoperable.
The 2A Diesel Generator ____ automatically start.
A. is NOT; canNOT B. is NOT; can still C. is; canNOT D. is; can still 70 of 75
- 70.
Plant Hatch HLT 5 (2009-302) NRC RO Test During performance of 34SV-R43-001-2, "Diesel Generator 2A Monthly Surveillance", in preparation for barring over Diesel Generator 2A, the Systems Operator has just placed the local switch for Diesel Generator 2A to "AT ENG" and depressed the emergency stop pushbutton.
Which ONE of the below choices completes the following statements?
The 2A Diesel Generator ____ REQUIRED to be declared inoperable.
The 2A Diesel Generator ____ automatically start.
A. is NOT; canNOT B. is NOT; can still C. is; canNOT D. is; can still 70 of 75
- 71.
Plant Hatch HL T 5 (2009-302) NRC RD Test Unit 1 was at 100% power when a scram condition occurred.
o All control rods did NOT fully insert (distributed at various levels in the core) o Reactor power is 19%
o The Reactor scram has NOT been reset o The RWM indicates as follows: I o On I Cetl'\\
IJ
,Il "';;=========;;;iiiiiiiiiiiifll
- ELfI~ -=-
,=,}~
~E(~T_E~Cc:":'_'-I __ B?-'-:r,::
- IC8E ':~:_..:.-=c
=:I..G( }~:. =-_:. ~
.. :-",1;,TI-IC0' :"5,~,-
~ 2:?-,:'-::-
?C",!"~:_ :=~lC~:I; -r...:1"~?
Which ONE of the following correctly states the operation of the RWM AND identifies a REQUIRED action to insert control rods?
RWM ___ allow control rod insertion using the "Emergency-In Notch Override Switch".
IA W 3 1 EO-EOP-103-1, "Control Rod Insertion Methods", the ___ to INSERT control rods.
A. will; reactor mode switch is required to be placed in the "Shutdown" position B. will NOT; lCll-F034, Charging Water Header Isolation Valve, will be closed C. will NOT; reactor mode switch is required to be placed in the "Shutdown" position D. will; lCll-F034, Charging Water Header Isolation Valve, will be closed 71 of 75
- 71.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 was at 100% power when a scram condition occurred.
o All control rods did NOT fully insert (distributed at various levels in the core) o Reactor power is 19%
o The Reactor scram has NOT been reset o The RWM indicates as follows: I o On J Ca.1'\\
f) e
.~
SELF 1.ES T OK SEQlJENCESQ,<\\l BP\\\\B !'.'fODR OfERLI.1E BLOCK.S: JNKERT\\\\'IIHDF..A"'i S1EP:J}l.5 PO'I,\\ER: BELO\\\\'LPSP Which ONE of the following correctly states the operation of the RWM AND identifies a REQUIRED action to insert control rods?
RWM ___ allow control rod insertion using the "Emergency-In Notch Override Switch".
IA W 3 lEO-EOP-103-l, "Control Rod Insertion Methods", the ___ to INSERT control rods.
A. will; reactor mode switch is required to be placed in the "Shutdown" position B. will NOT; 1 C 11-F034, Charging Water Header Isolation Valve, will be closed C. will NOT; reactor mode switch is required to be placed in the "Shutdown" position D. will; 1 C 11-F034, Charging Water Header Isolation Valve, will be closed 71 of 75
Plant Hatch HLT 5 (2009-302) NRC RO Test
- 72.
Unit 2 has been at 100% power for 7 days.
- Steam Tunnel Normal Full Power Background (FPB) radiation is 1,000 mr/hr.
- Main Steam Tunnel radiation increases to 2,800 mr/hr.
Which ONE of the choices below completes the following statements?
The "MAIN STEAM LINE RADIATION HIGH" (601-425) annunciator ____ alarming.
If radiation levels continued to rise, the LOWEST radiation level at which the MAIN STEAM LINE RADIATION HIGH-HIGH" (603-125) annunciator will alarm is __
A. is; 3,000 mr/hr B. is; 9.9E+5 mr/hr C. is NOT; 3,000 mrlhr D. is NOT; 9.9E+5 mr/hr 72 of 75 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 72.
Unit 2 has been at 100% power for 7 days.
- Steam Tunnel Normal Full Power Background (FPB) radiation is 1,000 mr/hr.
- Main Steam Tunnel radiation increases to 2,800 mr/hr.
Which ONE of the choices below completes the following statements?
The "MAIN STEAM LINE RADIATION HIGH" (601-425) annunciator ____ alarming.
If radiation levels continued to rise, the LOWEST radiation level at which the MAIN STEAM LINE RADIATION HIGH-HIGH" (603-125) annunciator will alarm is __ _
A. is; 3,000 mr/hr B. is; 9.9E+5 mrlhr C. is NOT; 3,000 mrlhr D. is NOT; 9.9E+5 mr/hr 72 of 75
- 73.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is shutting down for a refueling outage.
o A normal "Initial" Drywell (DW) entry at power is required.
Which ONE of the choices below completes the following statement lAW 31 GO-OPS-005-0, "Primary Containment Entry."
Before a normal "Initial" DW entry is allowed, Oxygen (02) concentration must be at least
___ and reactor power must be less than or equal to __ _
A. 19.5%;
15%
B. 19.5%;
10%
C. 23.5%;
15%
D. 23.5%;
10%
73 of 75
- 73.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 1 is shutting down for a refueling outage.
o A nonnal"Initial" Drywell (DW) entry at power is required.
Which ONE of the choices below completes the following statement IA W 31 GO-OPS-005-0, "Primary Containment Entry."
Before a nonnal"Initial" DW entry is allowed, Oxygen (02) concentration must be at least
___ and reactor power must be less than or equal to __ _
A. 19.5%;
15%
B. 19.5%;
10%
C. 23.5%;
15%
D. 23.5%;
10%
73 of 75
Plant Hatch HLT 5 (2009-302) NRC RO Test
- 74.
Which ONE of the choices below completes the following two statements?
The Cable Spreading Room is equipped with a ___ fire suppression system.
The Cable Spreading Room fire suppression system ___ initiate without operator action.
A. Dry pipe sprinkler; will B. Dry pipe sprinkler; will NOT C. CO2; will D. CO2; will NOT 74 of 75 Plant Hatch HLT 5 (2009-302) NRC RO Test
- 74.
Which ONE of the choices below completes the following two statements?
The Cable Spreading Room is equipped with a ___ fire suppression system.
The Cable Spreading Room fire suppression system ___ initiate without operator action.
A. Dry pipe sprinkler; will B. Dry pipe sprinkler; will NOT C. CO2; will D. CO2; will NOT 74 of 75
- 75.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is at 100% power when a loss of feedwater heating event occurs.
Which ONE of the following completes the following statement lAW 34AB-N21-001-2, "Loss Of Feedwater Heating" Section 3.0 Immediate Operator Actions?
Maintain Reactor power BELOW using __ _
A. 60%;
recirc B. 60%;
control rods C. the steady state power level prior to the feedwater temperature reduction; recirc D. the steady state power level prior to the feedwater temperature reduction; control rods End of Exam 75 of 75
- 75.
Plant Hatch HLT 5 (2009-302) NRC RO Test Unit 2 is at 100% power when a loss of feedwater heating event occurs.
Which ONE of the following completes the following statement IA W 34AB-N21-00 1-2, "Loss Of Feedwater Heating" Section 3.0 Immediate Operator Actions?
Maintain Reactor power BELOW using __ _
A.60%;
recirc B. 60%;
control rods C. the steady state power level prior to the feedwater temperature reduction; recirc D. the steady state power level prior to the feedwater temperature reduction; control rods End of Exam 75 of 75