ML093240230
| ML093240230 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/19/2009 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML093240230 (123) | |
Text
ES-401 Site-Specific SRO Written Examination Cover Sheet Form ES-401-8 U.S. Nuclear Regulatory Commission Site-Specific SRO 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO/SRO-OnlylTotal Examination Values
/ -- / --
Points Applicant's Scores
/ -- / --
Points Applicant's Grade
/ -- / --
Percent ES-401 Site-Specific SRO Written Examination Cover Sheet Form ES-401-8 U.S. Nuclear Regulatory Commission Site-Specific SRO 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO/SRO-Only/Total Examination Values
/ -- / --
Points Applicant's Scores
/ -- / --
Points Applicant's Grade
/ -- / --
Percent
for HLT 5 NRC SRO Test Test Form: 0 Answers ID 0
1 201001K5.02 1 D
2 202001A3.04 1 B
3 202002K2.021 C
4 20300002.1.31 1 B
5 20400002.4.46 1 D
6 205000K5.03 1 D
7 206000K5.05 1 B
8 209001Kl.09 1 D
9 209001K1.13 1 B
10 211000K4.03 1 C
11 212000A2.161 B
12 212000A2.191 A
13 214000Kl.04 1 B
14 215003Al.04 1 A
15 215004K6.04 1 C
16 215005Al.04 1 B
17 215005Al.05 1 B
18 216000A2.10 1 B
19 217000K2.03 1 B
20 218000Kl.06 1 D
21 223002K3.21 1 B
22 233000K4.06 1 A
23 234000K3.04 1 C
24 239002A3.05 1 D
25 241000A1.24 1 A
26 259002A4.03 1 B
27 259002K6.04 1 C
28 261000K3.01 1 B
29 261000K3.06 1 C
30 26200102.2.44 1 D
31 262002A3.01 1 B
32 263000A2.01 1 C
33 264000K4.041 B
34 286000A4.05 1 C
35 290002K6.08 1 D
36 290003Al.04 1 D
37 295001K2.07 1 D
38 295003Kl.04 1 B
39 29500402.4.09 1 A
40 295005K3.07 1 C
41 295006Al.02 1 A
42 29501OAl.05 1 D
43 29501302.4.01 1 B
44 295015Al.02 1 B
45 295016A2.061 B
46 295018K3.06 1 C
47 295019A2.02 1 A
48 295020A2.03 1 B
Wednesday, November 11,20092:05:54 PM 1
for HLT 5 NRC SRO Test Test Form: 0 Answers ID 0
1 201001K5.02 1 D
2 202001A3.04 1 B
3 202002K2.02 1 C
4 203000G2.1.31 1 B
5 204000G2.4.46 1 D
6 205000K5.03 1 D
7 206000K5.051 B
8 209001Kl.09 1 D
9 209001Kl.13 1 B
10 211000K4.03 1 C
11 212000A2.16 1 B
12 212000A2.191 A
13 214000Kl.04 1 B
14 215003Al.04 1 A
15 215004K6.04 1 C
16 215005Al.04 1 B
17 215005Al.05 1 B
18 216000A2.1O 1 B
19 217000K2.031 B
20 218000Kl.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 259002A4.031 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 290002K6.08 1 D
36 290003Al.04 1 D
37 295001K2.07 1 D
38 295003Kl.04 1 B
39 295004G2.4.09 1 A
40 295005K3.07 1 C
41 295006Al.02 1 A
42 29501OAl.05 1 D
43 295013G2.4.01 1 B
44 295015Al.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 11,20092:05:54 PM 1
for HLT 5 NRC SRO Test Test Form: 0 Answers ID 0
49 295021G2.2.40 1 D
50 295023Al.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 295030Kl.02 1 D
56 295031Al.05 1 C
57 295032Kl.02 1 A
58 295035K3.02 1 C
59 295037K2.07 1 B
60 295038Kl.03 1 B
61 300000K6.07 1 D
62 400000K2.02 1 C
63 500000K2.06 1 D
64 600000Kl.02 1 C
65 700000K2.071 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
76 211000G2.2.44 1 C
77 215003G2.1.27 1 B
78 216000A2.141 B
79 234000G2.2.25 1 A
80 261000A2.121 D
81 264000A2.091 D
82 272000A2.11 1 B
83 295001A2.04 1 B
84 295004G2.1.23 1 D
85 295005A2.02 1 C
86 295007 A2.01 1 C
87 295012G2.4.11 1 D
88 295013A2.01 1 C
89 295019A2.02S 1 C
90 295030G2.1.20 1 D
91 295031G2.2.441 B
92 400000A2.02 1 A
93 700000A2.03 1 C
94 G2.1.281 A
95 G2.1.371 B
96 G2.2.01S 1 C
Wednesday, November 11,20092:05:56 PM 2
for HL T 5 NRC SRO 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 295030K1.02 1 D
56 295031A1.05 1 C
57 295032K1.02 1 A
58 295035K3.02 1 C
59 295037K2.07 1 B
60 295038K1.03 1 B
61 300000K6.07 1 D
62 400000K2.021 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
76 211000G2.2.44 1 C
77 215003G2.1.27 1 B
78 216000A2.141 B
79 234000G2.2.25 1 A
80 261000A2.121 D
81 264000A2.09 1 D
82 272000A2.11 1 B
83 295001A2.04 1 B
84 295004G2.1.23 1 D
85 295005A2.02 1 C
86 295007A2.01 1 C
87 295012G2.4.111 D
88 295013A2.01 1 C
89 295019A2.02S 1 C
90 295030G2.1.20 1 D
91 29503IG2.2.441 B
92 400000A2.02 1 A
93 700000A2.03 1 C
94 G2.1.28 1 A
95 G2.1.371 B
96 G2.2.01S 1 C
Wednesday, November 11,20092:05:56 PM 2
for HLT 5 NRC SRO Test Test Form: 0 97 98 99 100 G2.2.231 G2.3.13S 1 G2.4.371 G2.4.41 1 Wednesday, November 11,20092:05:57 PM
Answers----------
A B
A A
3 for HL T 5 NRC SRO Test Test Form: 0 Answers ID 0
97 G2.2.231 A
98 G2.3.13S 1 B
99 G2.4.371 A
100 G2.4.411 A
Wednesday, November 11,20092:05:57 PM 3
SRO 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.
- 5.
Unit 2, Table 6 of SC flowchart without HVAC exhaust setpoints.
- 6.
Unit 1, Table 4 of 31 EO-EOP-014-1, SC/RR Flowchart
- 7.
Unit 2, 34S0-N40-001-2, Attachment 1 "Generator Capability Curve'
- 8.
73EP-EIP-001-0, "Emergency Classifications and Initial Actions," Attachment 1 -
Fission" Product Barrier Evaluation Chart - Modes 1-2-3"
- 9.
73EP-EIP-001-0, "Emergency Classification & Initial Actions", Attachment 2 "Hot" Initiating Condition Matrix Evaluation Chart, AC Power Section.
SRO 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.
- 5.
Unit 2, Table 6 of SC flowchart without HVAC exhaust setpoints.
- 6.
Unit 1, Table 4 of 31 EO-EOP-014-1, SC/RR Flowchart
- 7.
Unit 2, 34S0-N40-001-2, Attachment 1 "Generator Capability CUNe'
- 8.
73EP-EIP-001-0, "Emergency Classifications and Initial Actions," Attachment 1 -
Fission" Product Barrier Evaluation Chart - Modes 1-2-3"
- 9.
73EP-EIP-001-0, "Emergency Classification & Initial Actions", Attachment 2 "Hot" Initiating Condition Matrix Evaluation Chart, AC Power Section.
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.
125/2ffJVDC bus grounds are indicated on 112H11-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 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 s:19,000n 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 IF 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 4.0 SUBSEQUENT OPERATOR ACTIONS PAGE 2 OF 11 DOCUMENT NUMBER: REVISION NO:
34AB-R42-001-0S 1 ED 2 4.1 I.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.
125250 VDC bus grounds are indicated on 1J2H11-P655 on 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 Negative (-)
Page 6 2
Negative (-)
PN 1
Positive (+)
Page 8 2
Negative (-)
N 1
Positive (+)
Page 10 2
Positive (+)
4.1.2 I.E 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 s:19,000n 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 IF ground is less than 19000 ohms:
4.1.3.1 I.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
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.1. 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 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:
20F 6 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.!. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT 2.
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 MGR-0009 Rev 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 40000 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
+1.19 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
-1.19
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT.£ DOCUMENT NUMBER:
34AB-R42-00 1-0S 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.1. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT 2.
DOCUMENT NUMBER:
34AB-R42-00 1-0S 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.I. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT.£ DOCUMENT NUMBER:
34AB-R42-001-0S TITLE: GROUND FAULT DETERMINATION TABLE GROUND FAULT ON BUS N POTENTIOMETER RESISTANCE = 25,000 PAGE100F11 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.!. 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./. 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./. HATCH DOCUMENT TITLE:
LOCATION OF GROUNDS I
ATTACHMENT 2.
DOCUMENT NUMBER:
34AB-R42-00 1-0S TITLE: GROUND FAULT DETERMINATION TABLE GROUND FAULT ON BUS N POTENTIOMETER RESISTANCE = 25,000 PAGE 11 OF 11 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 177771777'71772)1,777777.777117771#777177,>77,1>> 7i7>,71,;; 77177;,7>>0 >7>>,:; > 2,. I'; 7>717;,.,
400 I>9'Hh':
TEMP NEAR INSTRUMENT RUNS I
eF) 350 IS~
- __ L. ___ -
- + - - - - - ---I I
I I
I I
I 300 F5~#h'7~ __ ~ ________ ~ _______ r-I -S-AF-E-~-
I I
~I----~*
250 IS';
I 200--+-~~~~~--~~~~~~~~~~--~~~~~
o 100 200 300 400 RPV PRESSURE (psig)
NOTE: May use SPDS Emergency Displays in place of this Graph.
GRAPH 1 400-""'....
TEMP NEAR INSTRUMENT RUNS (OP) 350-~
250-~
200 1 o
RPV SATURATION TEMPERATURE I
I
__ L- -
-~~I I
I I
I I
I I
- - ~ - - - - - - -
- ~ - - - - - - - '--1 -S-A-F-E---;~ - - -I I
I i
_I
-I
--=1 1
I I
I
;--------i-------:------
I I
I I
I I
I I
-I I
I I
=,
I I
I 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 I~W/~/hII~~~~/~~~1 400 I~~h#
_~$'~ffff~~1 DW TEMP (OF) 300 IfS"7¥AI"h"7"7'Y76" 7'1 200 l:hr~'A1 100 r HUU ",
o
[SAFEi 10 20 DRYWELL PRESSURE (psig)
NOTE: May use SPDS Emergency Displays in place of this Graph.
30 40 GRAPH 8 i DRYWELL SPRAY INITIATION LIMIT 400~~~~~~-j-----j~~~~~~~~~~~~~~~~
DW TEMP (OF) 300~~~~~----~-----4------+------+------~-----r----~
ISAFEi 200~~~~~----~-----4------+------+------~-----r----~
100~~~~~----~----~------+-----~------~----~----~
o 10 20 30 40 DRYWELL PRESSURE (psig)
NOTE: May use SPDS Emergency Displays in place of this Graph.
g.;~l~~~l 23 23 Torus 22 Temp co F) 21 20 19 18 17 I
HPCI PUMP NPSH LIMIT (Torus Water Level At or Above 146")
At or Above 10 psig I I -
Below 10 psig*
Below 5 psig*
UNIT2 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.
iGRAPH 17AI 24 23 23 Torus 22 Temp (OF) 21 20 19 18 17 0
HPCI PUMP NPSH LIMIT (Torus Water Level At or Above 146")
At or Above 10 psig r-----I-~
Below 10 psig*
Below 5 psig*
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 24u r7777777Y777777777777777Y7777777Y7777777Y7777777v777777A7777777~7777777A7777777A 23~~1"::JL~~~~~~~~~~~~
I I' /7-77"TT7rTTT;rr:V ~
22 At or Above 10 psig f-+----+--+----+---.;~~~
Torus Temp 21Jt===r====t:==j::::t~zd~~l-~l----L---J--~
(OF)
Below 10 psig*
200 I I '""""=
190 [
I I I I
- I L I I I J Below 5 psig*
180 I I
I I
I I I""""" I
'I
"'" I 170 I 16(J~~I----4-----4-----+-----~--~~---+-----+----~----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.
~RAPH 17Bl HPCI PUMP NPSH LIMIT (Torus Water Level Below 146")
Below 10 psig*
200;----+----~--;----+--~r---+---~--~----~~~
Below 5 psig*
18W-~~~=4====~==~--+---~--~--~~~--~
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 THE FOLLOWING lE. drywell and torus gas concentrations I
THEN perfonn the action specified are within a range specified I
inthe 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 action required perfonn path G-1 perfonn path G-1 X
less than 5%
go to point ~> >_90 to point ~> )90 to point R>
Y on this sheet on this sheet on this sheet G
E Drywell OR torus 02 no action required perfonn path G-2 perfonn path G-3 N
5% or higher OR 2g0 to point Q> >_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%
WHILE PERFORMING lHE FOLLOWING lE. drywell and torus gas concentrations I
THEN perfonn the action specified are within a range specified I
inthe table in the table below I
HYDROGEN Drywell OR tolUS 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 action required perfonn path G-1 perfonn path G-1 X
less than 5%
)goto point 0) )90 to point R) )90 to pOintR)
Y on this sheet on this sheet on this sheet G
E Drywell OR tolUs 02 no action required perfonn path G-2 perfonn path G-3 N
5% or higher OR
)goto point 0) )gotoPointS) >
go to point T cannot be determined on this sheet on this sheet on this sheet to be less than 5%
Table 6 SECONDARY CONTAINMENT OPERATING RADIATION LEVELS HVAC EXHAUST RADIATION ANNUNCIATORS on 2H11-P601 REACTOR BU ILDING (RX}
- RB BLDG POT CONTAtvl.A.REA RADlp,TIOhl (2D11-K609.A.-D)
REFUELING FLOOR
- REFUELING FLOOR VE~H EXHAUST RADIATION (2D11-K611 A-D)
- REFUELli'-JG FLOOR VE~H EXHAUST RADIATION (2D11-K634 AD)
- REFUELING FLOOR VENT EXHAUST RADIATION (2D11-K635 A-D)
Max Normal Max Safe Operating Operating Value Value mR/hr mR/hr HI-HI Radiation
- NIP, Annunciator N/A N/A N/A N/A Table 6 SECONDARY CONTAINMENT OPERATING RADIATION LEVELS HVAC EXHAUST RADIATION ANNUNCIATORS on 2H11-P601 REACTOR BU ILDING (RX}
- RB BLDG POT CONTAtvl AREA RADIATIOr\\j (2D11-K609 A-D)
REFUELING FLOOR
- REFUELI~'-JG FLOOR VE~H EXHAUST RADIATION (2D11-K611 A-D)
- REFUELI~'-JG FLOOR VE~~T EXHAUST RADIATION (2D11-K634 A-D)
- REFUELING FLOOR VENT EXHAUST RADIATION (2D11-K635.. ll...-D)
Max Normal Max Safe Operating Operating Value Value mR/hr mR/hr HI-HI Radiation N/,ll,
,ll,n nun ciato r N/A N/A N/A Nl,ll,
~able 6 SECONDARY CONTAINMENT OPERATING RADIATION LEVELS AREA RADIATION MONITORS Max Normal Max Safe Operating Operating on 2H11-P600, 2D21-P600 Value Value mRlhr mRlhr REFUEL FLOOR AREA 1 Reactor head laydown area (2D21-K601A) 50 1000 2 Dryer seperator pool (2D21-K601 E) 50 1000 3 Spent Fuel Pool & New Fuel Storage (2D21-K601 M) 50 1000 4 Reactor Vessel Refueling Floor (2D21-K611 K) 50 1000 5 Reactor Vessel Refueling Floor (2D21-K611 L) 50 1000 203' ELEVATION AREA (EASD 6 CRD repair area (2D21-K601T) 50 1000 203' ELEVATION AREA (WEST) 7 Fuel pool demin panel (2D21-K600D) 50 100 185' ELEVATION AREA 8 Spent fuel pool passageway (2D21-K601 P) 50 1000 9 RB 185' operating floor (2D21-K601 R) 50 1000 10 RB 185' sample panel area (2D21-K601S) 50 1000 11 RB 185' RWCU control panel (2D21-K601 U) 150 1000 158' ELEVATION AREA (NORTH}
12 RB 158' area N-E (2D21-K601C) 50 1000 13 RB 158' area N-W (2D21-K601D) 50 1000 158' ELEVATION AREA (SOUTH) 14 RB 158' area S-E (2D21-K601B) 50 1000 15 Decant pump and equipment room area 158' (2D21-K601 L) 50 1000 130' ELEVATION AREA (NORTHWEST) 16 lip area (2D21-K601F) 50 1000 130' ELEVATION AREA (NORTHEAST) 17 RB 130' N-E working area (2D21-K601G) 50 1000 130' ELEVATION AREA (SOUTHEAST) 18 South CRD HCU (2D21-K601N) 50 1000 130' ELEVATION AREA (SOUTHWEST) 19 RB 130' S-W working area (2D21-K601H) 50 1000 NORTHWEST DIAGONAL AREA 20 RCIC equipment N-W diagonal (2D21-K601V) 50 1000 SOUTHWEST DIAGONAL AREA 21 CRD pump S-W diagonal (2D21-K601W) 50 1000 NORTHEASTD~GONALAREA 22 CS & RHR N-E diagonal (2D21-K601X) 50 1000 SOUTHEAST DIAGONAL AREA 23 CS & RHR S-E diagonal (2D21-K601Y) 150 1000
[Table 6 SECONDARY CONTAINMENT OPERATING RADIATION LEVELS AREA RADIATION MONITORS Max Normal Max Safe Operating Operating on 2H11-P600, 2D21-P600 Value Value mRlhr mRlhr REFUEL FLOOR AREA 1 Reactor head laydown area (2D21-K601A) 50 1000 2 Dryer seperator pool (2D21-K601 E) 50 1000 3 Spent Fuel Pool & New Fuel Storage (2D21-K601M) 50 1000 4 Reactor Vessel Refueling Floor (2D21-K611K) 50 1000 5 Reactor Vessel Refueling Floor (2D21-K611 L) 50 1000 203' ELEVATION AREA (EAST) 6 CRD repair area (2D21-K601T) 50 1000 203' ELEVATION AREA (WEST) 7 Fuel pool demin panel (2D21-K600D) 50 100 185' ELEVATION AREA 8 Spent fuel pool passageway (2D21-K601 P) 50 1000 9 RB 185' operating floor (2D21-K601 R) 50 1000 10 RB 185' sample panel area (2D21-K601S) 50 1000 11 RB 185' RWCU control panel (2D21-K601U) 150 1000 158' ELEVATION AREA (NORTH) 12 RB 158' area N-E (2D21-K601C) 50 1000 13 RB 158' area N-W (2D21-K601D) 50 1000 158' ELEVATION AREA (SOUTH) 14 RB 158' area S-E (2D21-K601B) 50 1000 15 Decant pump and equipment room area 158' (2D21-K601 L) 50 1000 130' ELEVATION AREA (NORTHWEST) 16 lip area (2D21-K601F) 50 1000 130' ELEVATION AREA (NORTHEAST) 17 RB 130' N-E working area (2D21-K601G) 50 1000 130' ELEVATION AREA (SOUTHEAST) 18 South CRD HCU (2D21-K601N) 50 1000 130' ELEVATION AREA (SOUTHWEST) 19 RB 130' S-W working area (2D21-K601H) 50 1000 NORTHWEST DIAGONAL AREA 20 RCIC equipment N-W diagonal (2D21-K601V) 50 1000 SOUTHWEST DIAGONAL AREA 21 CRD pump S-W diagonal (2D21-K601W) 50 1000 NORTHEAST DIAGONAL AREA 22 CS & RHR N-E diagonal (2D21-K601X) 50 1000 SOUTHEAST DIAGONALAREA 23 CS & RHR S-E diagonal (2D21-K601Y) 150 1000
Table 4 SECONDARY CONTAI NM ENT o PER.A.TING TEMPER.A.TURES AMBlE NT TE MP (1 821 8 -S 1/S7) on 1 H11.p614, 1 G31-R604 158' ELEVATION AREA (RoNCU) 1 Phase Sep Room (1 G31-N016A) 2 Hx Room (1 G 31-N0168) 3 A pump room (North) (1 G31-N016C) 4 8 purrp room (South) (1 G31-N016D) 5 Hx Room (1G31-N016E) 6 Phase Sep Room (1 G31-N016F)
SOUTHEAST DIA GONALAREA 7 RHRJCS A (1 E11-NOO9A)
NORTHEAST DIAGONALAREA 8 RHRJCS 8 (1 E11-N0098)
HPCI ROOM AREA 9 Pump Room (1 E41-N024) 10 Emer Area Clr (1 E41-N030A) 11 EmerArea Clr(1E41-N0308)
RCIC ROOM AREA 12 Pump Room (1 E51-N011) 13 Errer Area Clr (1 E51-N023A) 14 Errer Area Clr (1 E51-N0238)
TO RUS RO OM AREA 15 Wes: Wall (1 E51-N025A) 16 SouthtNest Wall (1 E51-N0258) 17 Southeast Wall (1 E51-N025C) 18 Northeast Wall (1 E51-N025D)
MAIN STEAM UNETUNNELAREA 19 1821-N014 HPCI PIPE PENETRATION ROOM 1 1 E41-N046A 2 1 E41-N0468 DIFF TEIVP (1821 8-S2) on 1 H11.p614, 1 G31-R60S 158' ELEVATION AREA !RoNCU) 1 Hx Room (1 G 31-N022A1N023A) 2 A pump room (1 G31-N0228/N0238) 3 8 purrp room (1 G31-N022CIN023C) 4 Hx Room (1G31-N022D1N023D) 5 Phase Sep Room (1 G31-N022EIN023E) 6 Phase Sep Room(1 G31-N022F/N023F)
SOUTHEAST DIAGONALAREA 7 RHRJCS A (1 E11-N029A/N030A)
NORTHEAST DIAGONALAREA 8 RHRJCS 8 (1 E11-N0298JN0308)
TORUS ROOM AREA 13 1 E51-N026/1.1N027 A 14 1 E51-N0268/N0278 15 1 E51-N026C/N027C 16 1 E51-N026DJN027D MAIN STEAM U NE TUNNELAREA 17 1821-N016A/N0168
~ax Nonnal Max Safe Operating Operating Value Value "F
"F 150 212.5 150 212.5 150 212.5 150 212.5 150 212.5 150 212.5 150 212.5 150 212.5 167.5 245 167.5 245 167.5 245 167.5 310 167.5 310 167.5 310 167.5 212.5 167.5 212.5 167.5 212.5 167.5 212.5 192.5 300 150 212.5 150 212.5
~ax Normal rvtaxSafe Operating Operating Value Value "F
"F 67 98 67 98 67 98 67 98 67 98 67 98 40 98 40 98 42 102 42 102 42 102 42 102 60 150 Table 4 SECOND.A.RY CONTAINM HIT o PERA.TI NG TEM PERA. TURES AMBIENT TEMP (1 B21 B-51157) on 1 H11.f'614, 1G31-R604 158' ELEVATION AREA (R.... VCU) 1 Phase Sep Room (1 G31-N016A) 2 Hx Room (1 G 31-N01 68) 3 A pump room (North) (1 G31-N016C) 4 B purrp room (South) (1 G31-N016D) 5 Hx Room (1G31-N016E) 6 Phase Sep Room (1 G31-N016F)
SOUTHE.A.ST DIA GOhlA.LAREA 7 RHRlCS A (1 E1 H.,JOO9A)
NORTHEAST DIAGONALAREA 8 RHRlCS B (1 E11-N009B)
HPCI ROOM.A.REA 9 Pump Room (1 E41-N024) 10 Emer.A.rea Clr ("1 E41-r\\J030A) 11 Emer Area Clr ("1 E41-N030B)
RCIC ROOM AREA 12 Pump Room (1 E51-N011) 13 Errer Area Clr (1 E51-N023A) 14 Errer Area Clr (1 E51-N023B)
TORUS ROOM AREA 15 \\lVeg \\lVall (1 E5*1-N025A) 16 Souttlo..... l8st \\lVall (1 E51-N025B) 17 Soutt-Ieast \\lVall (1 E5H~025C) 18 Northeast \\lVall (1 E51-N025D)
MAIN STEAM Ut'-.JETUNNELAREA 19 1 B21-N014 HPCI PIPE PENETRATION ROOM 1 1 E4H~046A 2 1 E41-N046B DIFF TEMP (1 B21 B-52) on 1 H11.f'614, 1G31-R60a 158' ELEVATI0r'-J AREA f,RVVCU) 1 Hx Room (1G31-N022NN023A) 2 A pump room (1 G31-N0228/N0238) 3 B purrp room (1 G31-N022C1r~023C) 4 Hx Room (1 G 31-t'-.J022D1N023D) 5 Phase Sep Room (1 G31-N022EIr\\l023E) 6 Phase Sep Room (1 G31-N022F IN023F)
SOUTHEAST DIA GONALAREA 7 RHRiCS A (1 E11-N029A/t'-.J030A)
NORTHEAST DI.A.G ONALAREA 8 RHRiCS B (1 E11-N029B.iN0308)
TORUS ROOM ARE.A.
13 1 E51-N026.A.lN027 A 14 1 E51-N026B/N027B 15 1 E51-N026C1N027C 16 1 E51-N026DlN027D MAIN STEAM U NETUNNELARE.A.
17 1B21-t'-.J016A/N016B Max Nonml Max Safe Operating Operating Value Value DF DF 150 2"12.5 150 212.5 150 212.5
- 150 212.5 150 212.5 150 212.5 150 212.5 150 212.5 167.5 245 167.5 245 167.5 245 167.5 310 167.5 310 167.5 310 167.5 212.5 167.5 212.5 167.5 212.5 167.5 212.5 192.5 300 150 212.5 150 212.5 Max Normal i!1ax Safe Operating Operating Value Value DF DF 67 98 67 98 67 98 67 98 67 98 67 98 40 98 40 98 42 102 42 102 42 102 42 102 60 150
SNC PLANT E. J. HATCH I DOCUMENT TITLE:
MAIN GENERATOR OPERATION ATTACHMENT J...
TITLE:
GENERATOR CAPABILITY CURVE I
DOCUMENT NUMBER:
34S0-N40-001-2 900 800 700 600 15psig t
30psig [
~-I
~I-H 45psig
-.... 500
--I
'-' 400 C/) 300
~
- 200
<< 100 (9
0 W 100
~-
-200 0-300
~
-400
~-500
-600
-700 52psig Pg 31 of 68 Version No:
12.15 60psig Att. Pg.
1 of 1 o
100 200 300 400 500 600 700 800 900 1000 1100 1200 MEGAWAllS G16.030 MGR-0009 Ver. 4 SNC PLANT E. I. HATCH I DOCUMENT TITLE:
MAIN GENERATOR OPERATION ATTACHMENT _1 TITLE:
GENERATOR CAPABILITY CURVE 900 800 700 600
-........ 500
---1
400 (f) 300 0:::
<C 200
~ 100 (9
0 W -100
~
-200 0-300 L:5 -400 2--500
-600
-700 I
15psig
~
I I
I 30psig
~
I I
I I
DOCUMENT NUMBER:
34S0-N40-001-2 45psig 52psig I
I I
I I
I I
I Pg 31 of 68 Version No:
12.15 AU. Pg.
1 of 1 60psig I
I I
I I
I I
I I
I o
100 200 300 400 500 600 700 800 900 1000 1100 1200 MEGAWAllS G16.030 MGR-0009 Ver. 4
- 3. RCS wit Rate (Pg. 39)
UlIisoJableMainSteamlli:le break lIS iDdicated by IIle &ilure ofbothMSIVs in any _Jine to close A!ltJ)
A. HighMSLFlow OR B. High Steam TUIJIlel Tempemture 3l1IllIIICiaton OR C. TmbilJe Building MSL leak aIIllIlIlciatcr
.oR D. Direct report of steam release
- 4. Dqml Radjari,. lIQuitmiag (Pg. 39)
DWRR..T\\iI greater than 138 R4Ir L Drrn'el PresSIIN (Pg. 40)
Rapid unexplained decrease ibllowing initial increase OR Dl:yweIl pressure IeSpOIISe not ~wilhLOCA mnditions TVsbasedon 1heDVlRRM (Pg.41)
Barrier is lost Consider conditions to de1e!:mine IIle &talus ofllle ConIa:inment BruDer t
TVs bamion
!heRWI. 1 IVs based on Secondmy Containment Max. Safe 0peraiiDg Values
- 3. Res Leak lUk {Pg.39)
Ullj$clable~,iain Steamline break as indicated by the fhilure of beth MSr,'s in (llW one Jille to cl<JS<!
.~'\\-n A. Hi:ili MSL Fl~w OR -
B. High Steam TlUlllel Temperatnre aJ:lllli!,ti~tm;.
OR C. Turbine BtUidiJlf! MSL Ie~.k aJlll!1l1CiatOf DR D, Threet report of steJDl relea>e
- 4. D""Jrell R(lc1iarifiU \\fuuitnriug 1'P;-, 39)
D\\.'l/RPJ",f greater tha.~ 138 F./br
- , Otller Indjf;1drmlj (Pg. ~,~n Dr
- ,well PoilS! lOCA~,'kmitDr.:!, 71E.,.(14 cpm 6 Emergency Dil't<toi',Jnd g;mellt (Pg,.j{l)
JUMwellt by the EDiliat the RCS BilIIRr io; lo,t Cmliider ~ouditioo> net adcte;<;ffi aiKt ill..1biJity IlY determine the siantsofthe RCS Bmiff l.oss
.......!<.!o"-"-"""'....... """"'" (Pg.-IO)
Rapid lU1explained aecrea;e lOlloWUlg initial mcrea'if OR Dl:}l.,*ell pre~$'l1Ie reqxr~ llOt l.:mlSi'irent \\vith lOCA conditi0l1s
- 3. Containment 15~lllru.n FlIilllr~ or B'~:\\I$ {Pz,,H)
Failure ofboili y::uyer, in am' Olle line to c\\)SE! A..,\\1) dowllStr~rou bre,;chontgide Primuy Cc-ntai!ment exi"ts OR Imemiollal venting per EOPs OR C ()]ltlinm'f'llt operating telllDemture->or l1ldiatio11leYeh (. bm'e Ma">;, Safe Opanting Ullisol,.ble prima.... y ~y;;tem le;d;age outside dr),... 'ell a~ imlkated by Secondary 1~~
Values (SC.. Secor.d;Uy C~ntru:.'1!Dent C0110:01 How.:hart - Table 4 & Table 6} -
- 6. Eme[~eu(~' Dil'HtOl' JlId~lIenl (Pg,,Ili Judgment by the ED that the Colllaimneut Barrier is 10;1. COllilder conditio;m,}
110t addre;r,ed and inability 10 determille tile.tant; of the ContUumellt Barrier n,'s based or, them\\iRP~l T'ils lxvled on d-.eR\\'.L 1*
IVs ba,ed 00 Secondary COlltainment Max. Safe Operating Valne, Cni,olable prim.'uy 'iy,temle"kage "llt>ide d.,)".,ell a, indicated by Se~()t1(lary 1'.'
Cootall'llllent operating tanpemtnRs or rJdiationlewb ~b()\\'e Max, NOllillJ Operating Value, (SC - Secoll(l~.IY Cor,trtlnment Control Flo';\\'cbart - Table -I &: Table 6:1 1",,'-===--'-'--'-'-'-'''-'= (P!,.to)
Primary containment flooding !equir~ by EOP, l, indicated lrf elltry into procedure 31EO-EOP-112-1'l mm.'U}' C<>n!liinnrent Fioodil1g.
- 1. Loss of ail AC power indicated by:
ll. Loss ofpower to or from Startup ADm.}'
TraufOllJ1f'B (SAT) lac and Il2D resuttiDg in loss of all off-site eJec.trical power to 4160 VAC Emergency Buses 112E, 112F, and l!2G for greater than 15 minutes Ai'1)
- h. FaibJre of emergency diesel generators to supply power to emetgeD.Cy busses.
AJ~l) EITHER
- 2. Restomioo of at least one 4160 VAC Emergency Bus, 1I2E, I!2F, or 112G, within 4 hotu:s of time of loss is NOT likely.
- 3. Fuel Clad Barrier Evaluation indiates 00JItimJiDg degradation (Loss or Potmtia1 Loss) of core cooling
- 1. Loss of all AC power indicated by:
ll. Loss of power to or from Startup AuxiIWy TransfOl1lleB (SAT) 1l1C and 112D rem1ting in loss of aU off-site electrical power to 4160 VAC Emergency Buses 112E, l!2F, and 1I1G for gre~ter1ban 15 minutes
.-\\i.D
- b. Failure of diesel genemors to mpplypower to emflgmcy busses.
- -\\l'i'D
- c. Restomtion of at Jeast one 4160 VAC Emergency bus, 112E, 112F, or I12G, has NOT octmred within 15 mimJtes of time ofkm of an AC power I. Loss of Vital DC power to 1251250 we Bus IflR22-S016 and 1l2R22-S017 indicated by bas voltage :indications less 1hm 1051210 VDC for greater 1m 15 minutes.
w-ACpmveccapa1ili1yto&seatial.... ~to a siaJ1epoweclOlllCeb""...tIa Umij_aJi6at; ayaMjlima1IiD1efailmrelfiJllWHSIJI.srA1mN.
BlACKOOI'. (r&'1 ofM. 4)
- 1. a. AC powet' capability to 4160 VAC Emergency Buses 1I2E, 1!2F, and 1126 reduced to a single power source for greater thm 15 minutes
.o\\i'"'O
- b. ANY additimml si:Dgle failure will restdt in slation blackout SUI-Loos of An t'lftSite Powerto Essential Busses for GREATER. THAN 15 Minutes (Pg,. 51 mAtt. 4)
- 1. II.. Loss of power to or from StmtDp Auxiliary Ttmttooners (SAl) II2C and ll2D resulting in loss of aU off-si1e eiec:bical power to 4160 VAC Emergmq Buses ltlE. lllf, and 112G for glUtet-than 15 :mir.mtes A:.,-n
- b. Emergmcy diesel geue.rntom supplying power to 11lE, IflF. and 112G.
1.1.oss of all AC power indicated by:
- a. Loss of fJO"ef to or from Startup Auxilia1Y TmnsfortnefS (SAl) lilC and Il2D resultine: in loss of all off-site electri<:ai power to 4160 VAC Emergency Buses 1I2E. li2F, and 1I1G for g,eater than 15 minu~
A..'""D
- b. Faihl.re of emergency diesel generators to supply power to emergency busses.
A.\\1) EITHER
- 2. Restoration of at least one 4160 VAC Emergency Bus, liLE, lilF, or 1/20, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> oftime of loss is 50T likely.
- 3. Fuel Clad Barrier Evaluation indicates continuing degradation (loss or Potential L(}ss) of core cooling
- 1. Loss of an AC PO\\\\'er indicated by:
ll. LOSf; of power to or from Startup Auxiliary TransfortnefS (SAl) llle and 1l2D re!>ultine: in loss of all off-site electrical power to 4160 \\7AC Emergency Buses I/2E, V2F, and 1l1G for greater than 15 minutes
.t."\\l)
- b. Faili.I.re of diesel generators to supply PO~'er to emergency busses.
A.. \\1)
- c. Restoration of at least one 4160 VAC Emer!encv
'-.. 1 F)E. 11")1:'
1 )G 1.~ ""OT*
~
VU:>.
,'~". J..::..r, or )..,JJj]S __
"' _ occurred within 15 minutes of time ofl().';.s of all AC pmller
- 1. Loss of Vital DC power to 125l25{) VIX Bus li2R22-S016 and 1/2R22*S017 indicated by bus
'froltage indication,~ less than 1051210 VDe for greater than 15 minutes.
SA5 - AC POWE'f capability to Es';entful Bl1~'seS reduced to a singJe power S01JKe for grealer than 1 j minutes such that any additional single fiilure wotdcire'.iult in STATION BLACKOUf. (Pg. 57 of Atl4)
- 1. a. AC power capabilitvto 4160 VAC EmergetlCv "l
~,
J Buses l!2K WF, and 1/20 reduced to a single power oource for greater than 15 minutes A."\\"D b... ANY additional single failure will result ill.station blackout.
SUI - los~ClL.w. Off~ite Power to E&sential BU';',;es fOf GREATER TRiiN 15 !It1inutes (Pg. 58 dAn. 4)
- 1. tt. LO;1i:; of power to or fj~om StMTI!p Auy.iliary Iraj]sfol'lner~ (SAn V1CLUl.d l/m re~.ulting in
~
~
los:; c,f aU off*!}ite electrical pO'ilief to :J..160 VAC Emergency Bm.e5 t2E. 1 i1F. and 1 ilG :fOf Q"H~llter than f 5 !lUnutes A.. "\\ll
- h. Emergency die'1el generatof'", supplying :power t",)
llE, V2F.LUl.a. 1.'1G.
- 1.
HL T 5 NRC SRO 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 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 100
- 1.
HLT 5 NRC SRO 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 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 100
HL T 5 NRC SRO 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 Recirc A AND B Runback lights will be (1)
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 100 HL T 5 NRC SRO 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 Recirc A AND B Runback lights will be (1)
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 100
- 3.
HLT 5 NRC SRO 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 100
- 3.
HLT 5 NRC SRO 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 100
- 4.
HL T 5 NRC SRO 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. 2Hll-P602; ONLY one loop's flow indicator will have flow 4 of 100
- 4.
HLT 5 NRC SRO 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. 2HI1-P602; Both loops flow indicators will have flow D. 2HII-P602; ONLY one loop's flow indicator will have flow 4 of 100
- 5.
HLT 5 NRC SRO Test Unit 1 was operating at 100% power with the following RWCU indications:
o RWCU Inlet Flow Indicator R609: 245 gpm o RWCU Dernin "A" & "B" Flow Ind R605 NB: 115 gpm each Subsequently, the following alarm is received, RWCU SYS LEAK (602-421).
Which ONE of the following flow indications at the 1 G31-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. 60gpm 5 of 100
- 5.
HLT 5 NRC SRO 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 lG3l-R6l5 Cleanup Leak: Detection Indicator on Panel lHll-P613 is the LOWEST value consistent with these plant conditions?
A. 0 gpm B. 15 gpm C. 45 gpm D. 60 gpm 5 of 100
- 6.
HLT 5 NRC SRO 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 IA W 34S0-EII-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 100
- 6.
HL T 5 NRC SRO 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 IA W 34S0-EII-OIO-l, "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 100
- 7.
HLT 5 NRC SRO 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-F001 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 100
- 7.
HLT 5 NRC SRO 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-F001 Turb Steam Supply Valve; will B. HPCI Turbine Stop Valve; will C. 2E41-F001 Turb Steam Supply Valve; will NOT D. HPCI Turbine Stop Valve; will NOT 7 of 100
- 8.
HLT 5 NRC SRO Test Unit 1 is at 100% power. Core Spray IE21-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 IE21-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 100
- 8.
HLT 5 NRC SRO 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 100
HL T 5 NRC SRO 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 100
- 9.
HLT 5 NRC SRO Test Unit 2 is operating at 30% RTP with the following annunciator illuminated:
LEAKDET BLOGIe IN TESTSTATlJS LEAKDET iliFF TEMP HIGH LEAKDET AMBIENT TEMP HIGH 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 100
- 10.
HLT 5 NRC SRO 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 100
- 10.
HLT 5 NRC SRO Test Concerning the Unit 2 Standby Liquid Control (SBLC) system:
TANK LEVEL 2C41-R601 TANK LEVEL 2C41-R601 P
E R
C E
N T
Figure A Figure B Which ONE of the following completes both of these statements?
During nonnal 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 100
- 11.
HLT 5 NRC SRO Test Unit 2 is in Mode 1 shutting down for a planned maintenance outage lAW 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 lAW 34AB-C71-001-2, Scram Procedure B. will; confirm Hydrogen injection is shutdown lAW 34AB-C71-001-2, Scram Procedure C. will NOT; fully insert the SRMs prior to IRMs going below Range 2 lAW 34GO-OPS-013-2, Plant Shutdown D. will NOT; confirm power is turned on to the Refueling Bridge lAW 34GO-OPS-013-2, Plant Shutdown 11 of 100
- 11.
HLT 5 NRC SRO 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...... 381 R9 B..... 331 R9 C...... 30/R9 D...... 38/R9 E...... 28/R9 F...... 37/R9 G
371 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 100
- 12.
HL T 5 NRC SRO Test Unit 2 is operating at 100% power when the 2A RPS MG Set trips.
Which one of the following predicts the status of2G31-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 100
- 12.
HLT 5 NRC SRO Test Unit 2 is operating at 100% power when the 2A RPS MG Set trips.
Which one of the following predicts the status of2G31-F001, Rx Water Cleanup Valve, AND identifies the PREFERRED source of Alternate Power to 2A RPS Bus IA W 34S0-C71-00 1-2, 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 100
HLT 5 NRC SRO Test
- 13.
Unit 1 is at 5% power and the following alarms are received:
o RMCSIRWM 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 100 HLT 5 NRC SRO 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 100
- 14.
HL T 5 NRC SRO 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 100
- 14.
HLT 5 NRC SRO 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 100
HLT 5 NRC SRO 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 100 HLT 5 NRC SRO 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 100
- 16.
HL T 5 NRC SRO 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 100
- 16.
HLT 5 NRC SRO 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, "APRMlOPRM TRIP"?
A. 104%
B. 110%
C. 112.5%
D. 113.8%
16 of 100
- 17.
HL T 5 NRC SRO 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 ltD" 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 1 00
- 17.
HLT 5 NRC SRO 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 1 00
- 18.
HLT 5 NRC SRO 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 ILS 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" lAW 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) de+er,.,j ltI~d When the RHR injection valves automatically open, RWL may be lBemteFea with _"""'(=~'--
R WL instruments.
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 100
- 18.
HL T 5 NRC SRO 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 (1) de+errni ",~d When the RHR injection valves automatically open, RWL may be ~oHitorod with _~{==-22l---
RWL instruments.
A4 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 100
HLT 5 NRC SRO 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 100 HL T 5 NRC SRO 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 100
- 20.
HLT 5 NRC SRO 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 100
- 20.
HLT 5 NRC SRO 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 100
- 21.
HL T 5 NRC SRO 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 100
- 21.
HLT 5 NRC SRO 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 100
HLT 5 NRC SRO Test
- 22.
a AS Unit )'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 100 HLT 5 NRC SRO Test
- 22.
d J46 Unit'is in a refueling outage when a rupture of the Fuel Pool Cooling and Cleanup CFPCC) 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 100
- 23.
HLT 5 NRC SRO 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 100
- 23.
HLT 5 NRC SRO 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 100
- 24.
HLT 5 NRC SRO Test Unit 2 is in an A TWS with the following conditions:
o Reactor Power................................................. 20%
o Reactor Pressure.............................................. 1125 psig, (highest reached) o MSNs............................................................. 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 100 HLT 5 NRC SRO Test
- 24.
Unit 2 is in an ATWS with the following conditions:
o Reactor Power................................................. 20%
o Reactor Pressure.............................................. 1125 psig, (highest reached) o MSN s............................................................. C10sed o Torus temp...................................................... 1 05°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 ofloop(s) of RHR required to be placed in Torus Cooling is ___ _
A. g.,
1 B. g.,
2 C. 4*,
1 D. 4*,
2 24 of 100
- 25.
HLT 5 NRC SRO 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?
IA W 34S0-N30-00l-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 100
- 25.
HLT 5 NRC SRO 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?
IA W 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 100
- 26.
HLT 5 NRC SRO 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 100
- 26.
HL T 5 NRC SRO Test Unit 1 is at 60% power with the following conditions:
o "A" RFPT is in Auto, controlled from the FW Master Controller 1C32-R600 o "B" RFPT is in Manual, controlled from MIA station 1C32-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 100
HL T 5 NRC SRO 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 100 HL T 5 NRC SRO 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 100
- 28.
HLT 5 NRC SRO 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 100
- 28.
HLT 5 NRC SRO 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 100
- 29.
HLT 5 NRC SRO 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 O2 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 O2 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 100
- 29.
HLT 5 NRC SRO Test Unit 2 is inerting the primary containment IA W Containment Atmospheric Control & Dilution, 34S0-T48-002-2, Section 7.l.l, Primary Containment Inerting.
The following conditions currently exist:
o SBGT 2A running o DW O2 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 O2 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 100
- 30.
HLT 5 NRC SRO 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 100
- 30.
HL T 5 NRC SRO 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 100
- 31.
HL T 5 NRC SRO Test Unit 2 is at 100% power when a Loss of Off-Site Power occurs and the 12C" 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 100
- 31.
HL T 5 NRC SRO Test Unit 2 is at 100% power when a Loss of Off-Site Power occurs and the 12C" 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; 600VBus 2D D. 600 V Bus 2D; 600 V Bus 2C 31 of 100
- 32.
HLT 5 NRC SRO 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 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 100
- 32.
HLT 5 NRC SRO 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 IHII-P655, the Battery Ground Detection System meter lR42-R613B indicates the following when placed to Position 1 and then Position 2:
) -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 100
- 33.
HLT 5 NRC SRO 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 100
- 33.
HL T 5 NRC SRO 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'tI must be placed to the "Remote" C. "Remote";
will remain in the "Remote" D. "Remote";
must be placed to the "At Engine" 33 of 100
- 34.
HL T 5 NRC SRO 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-R43-00I-I, "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 100
- 34.
HLT 5 NRC SRO 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)
IAW 34S0-R43-00l-l, "Diesel Generator Standby AC System".
o After the bus is de-energized, water is sprayed on the fire.
ill 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 100
HL T 5 NRC SRO 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 100 HLT 5 NRC SRO 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 100
- 36.
HL T 5 NRC SRO 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, 2Dll-K609 A-D 18 mrlhr 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 100
- 36.
HLT 5 NRC SRO 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 100
- 37.
HL T 5 NRC SRO 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 A. Is; 15 B. Is; 27 C. Is NOT; 15 D. Is NOT; 27 accurate and actual core flow is Mlbmlhr.
37 of 100
- 37.
HL T 5 NRC SRO 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 Mlbmfhr.
o Jet Pump Flow 2B21-R611B, "Total B Flow".................................................... 6 Mlbmfhr.
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 Mlbmfhr?
The 2B21-R613 recorder A. Is; 15 B. Is; 27 C. Is NOT; 15 D. Is NOT; 27 accurate and actual core flow is Mlbmlhr.
37 of 100
- 38.
HLT 5 NRC SRO 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.
lAW 34AB-R23-001-2 "Loss Of 600 Volt Emergency Bus" the 2C 600 V AC 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 100
- 38.
HLT 5 NRC SRO 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 MSIV s.............................................. 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-R23-001-2 "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 100
HL T 5 NRC SRO 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 100 HL T 5 NRC SRO Test
- 39.
Unit 1 is at 10% power when a seismic event causes the following:
o 1251250 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 100
- 40.
HL T 5 NRC SRO 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 100
- 40.
HLT 5 NRC SRO 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 100
- 41.
HLT 5 NRC SRO 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................ -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 100
- 41.
HLT 5 NRC SRO 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, 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 100
- 42.
HL T 5 NRC SRO 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 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) 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 100
- 42.
HLT 5 NRC SRO 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 ADDITIONAL vent path that is available AND (2) The EARLIEST time the operator is REQUIRED to closelconfirm 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 100
HLT 5 NRC SRO 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 BOP 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 1100P C. is NOT 1200P D. is NOT 1100P 43 of 100 HLT 5 NRC SRO 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 BOP PC flowchart ____ required.
The LOWEST Torus temperature which requires placing the Rx Mode Switch in Shutdown occurs at a torus temperature of ___ _
A. is 120 0P B. is 110 0 P C. is NOT 120 0 P D. is NOT 110 0 P 43 of 100
- 44.
HL T 5 NRC SRO 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 ofthe 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 100
- 44.
HLT 5 NRC SRO 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 ofthe following identifies the current status of "APRM Downscale" (603-228) annuciator and the required operator action IA W 34AB-CII-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 100
- 45.
HLT 5 NRC SRO 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-C71-00l-2, "Scram Procedure"
- 34AB-X43-001-2, "Fire Procedure" lAW 3 1 RS-OPS-OO 1-2, 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 100
- 45.
HL T 5 NRC SRO 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 100
- 46.
HLT 5 NRC SRO 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 100
- 46.
HL T 5 NRC SRO 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 blow down 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 100
- 47.
HLT 5 NRC SRO 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 100
- 47.
HLT 5 NRC SRO 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 100
- 48.
HLT 5 NRC SRO 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 100
- 48.
HLT 5 NRC SRO 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 100
- 49.
HLT 5 NRC SRO 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 100
- 49.
HLT 5 NRC SRO 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 100
- 50.
HLT 5 NRC SRO 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 100
- 50.
HL T 5 NRC SRO 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 2D2l-K60lA and 2D2l-K60lM 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 2D2l-P600 ARM Panel
- c. go below will automatically silence (reset)
D. go below must be manually silenced (reset) at 2D2l-P600 ARM Panel 50 of 100
- 51.
HL T 5 NRC SRO 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. can NOT; is NOT D. can NOT; is 51 of 100
- 51.
HLT 5 NRC SRO 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. can NOT; is 51 of 100
- 52.
HL T 5 NRC SRO 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-FOl1, "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 100
- 52.
HL T 5 NRC SRO 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 100
- 53.
HL T 5 NRC SRO Test Unit 1 is at 100% power when the following occurs:
o SRV "c" has failed open o Torus temperature reaches 1800 P 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 100
- 53.
HLT 5 NRC SRO 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 lAW 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 100
- 54.
HLT 5 NRC SRO 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 100
- 54.
HLT 5 NRC SRO 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 "BYPASS".
54 of 100
- 55.
HL T 5 NRC SRO Test Unit 2 is operating at 100% power when a Loss of Coolant Accident occurs. The High Pressure Coolant Injection (HPCn 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?
/If HPCI pump operation is acceptable NPSH liftS VOffffit LiHH~S 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 ItBd*¥ortex limi~
D. outside of; reducing flow to 3,000 gpm will restore acceptable operation for NPSH ~
¥-emU( liHl:i~s~
55 of 100
- 55.
HLT 5 NRC SRO Test Unit 2 is operating at 100% power when a Loss of Coolant Accident occurs. The High Pressure Coolant fujection (HPCI) system is being used to control RPV water level.
o HPCI flow rate............................... 3,500 gpm o RWL.............................................. -80" and increasing at I" per minute o RHR Loop "A" is in Suppression Pool Cooling o Torus level..................................... 135 inches o Torus temperature.......................... 210 0 P o Suppression Chamber Pressure...... 6 psig Which ONE of the following choices completes this statement?
~
HPCI pump operation is ___ acceptable NPSH ftHd Vort~( LHnits 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 aed Vortex limi~
D. outside of; reducing flow to 3,000 gpm will restore acceptable operation for NPSH aa4-
¥eruHi lifFl:its~
55 of 100
- 56.
HL T 5 NRC SRO 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-R610)................................ 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 100
- 56.
HL T 5 NRC SRO 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-R60l)...................... 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 feed water 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 100
- 57.
HLT 5 NRC SRO 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 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 100
- 57.
HL T 5 NRC SRO 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°F, rising 10°F/min Which ONE of the choices below completes both of the following statements?
IAW 34S0-T46-001-2 "Standby Gas Treatment System", the operator is required to ___ _
to limit the release of radioactive material.
IA W the 31EO-EOP-014-2, 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 100
- 58.
HL T 5 NRC SRO Test Unit 1 is in a startup with the following conditions:
o 1 T41-C004A, Rx Bldg Vent Accessible Area Exh Fan.......... Running o IT41-C007A, Rx Bldg Vent Inaccessible Area Exh Fan........ Running o 1 T41-COOIA, Rx Bldg Vent Supply Fan................................. Running o IT41-COOIB, Rx Bldg Vent Supply Fan................................. Tagged Out Which ONE of the choices below completes the following statement?
If IT41-COOIA, 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 100
- 58.
HL T 5 NRC SRO Test Unit 1 is in a startup with the following conditions:
o 1 T41-C004A, Rx Bldg Vent Accessible Area Exh Fan.......... Running o 1 T41-C007 A, Rx Bldg Vent Inaccessible Area Exh Fan........ Running o 1 T41-COOIA, Rx Bldg Vent Supply Fan................................. Running o IT41-COOIB, Rx Bldg Vent Supply Fan................................. Tagged Out Which ONE of the choices below completes the following statement?
If 1 T41-COOIA, 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 100
- 59.
HLT 5 NRC SRO 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 I EO-EOP-O I I-I, RCA flowchart?
The HIGHEST APRM power indication which allows the operator to use 34AB-C 11-005-1, 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 100
- 59.
HL T 5 NRC SRO 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 31EO-EOP-Oll-l, RCA flowchart?
The HIGHEST APRM power indication which allows the operator to use 34AB-C 11-005-1, 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 100
- 60.
HLT 5 NRC SRO 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?
In order to obtain release assessment information for an ELEV A 1ED 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 100
- 60.
HLT 5 NRC SRO 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?
In order to obtain release assessment information for an ELEVATED 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 100
- 61.
HLT 5 NRC SRO 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-F017, 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 100
- 61.
HLT 5 NRC SRO 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 100
HLT 5 NRC SRO 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-F001)
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 100 HLT 5 NRC SRO 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 filet 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 filet Isolation Valve (P42-F051)
D. Station Service Air Compressor B; RWCU fiboard Suction Isolation Valve (G31-FOOl) 62 of 100
- 63.
HLT 5 NRC SRO 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 lAW 31EO-PCG-001-2, "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 100
- 63.
HL T 5 NRC SRO 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 31 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 100
- 64.
HLT 5 NRC SRO Test Which ONE of the following plant fire locations requires a manual reactor scram lAW 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. futake Structure 64 of 100
- 64.
HLT 5 NRC SRO Test Which ONE of the following plant fire locations requires a manual reactor scram IA W 34AB-X43-00l-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. futake Structure 64 of 100
- 65.
HL T 5 NRC SRO Test Both units are operating at 100% power. On panellHII-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-SII-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 100
- 65.
HLT 5 NRC SRO 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-S 11-001-0, "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 100
- 66.
HLT 5 NRC SRO 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 100
- 66.
HLT 5 NRC SRO 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 100
- 67.
HLT 5 NRC SRO 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-POOl fully closed; 2Hll-P602 fully closed; 2G31-POOl 67 of 100
- 67.
HLT 5 NRC SRO 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-G3l-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 2G3l-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; 2Hll-P602 partially closed; 2G3l-POOl fully closed; 2Hll-P602 fully closed; 2G3l-POOl 67 of 100
- 68.
HLT 5 NRC SRO 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 100
- 68.
HL T 5 NRC SRO 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 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 100
HL T 5 NRC SRO 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-OOl-l, "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 100 HL T 5 NRC SRO 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-OOl-l, "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 100
- 70.
HLT 5 NRC SRO 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 100
- 70.
HLT 5 NRC SRO Test During perfonnance 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; can NOT D. is; can still 70 of 100
- 71.
HLT 5 NRC SRO 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 display indicates as follows:
o 0 tJ 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 31EO-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; lCII-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 100
- 71.
HLT 5 NRC SRO 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 display indicates as follows:
o 0 1'1 tJ SELF'IE'ST: OK ll,EQL1ENCE:SQ."'-lBPVil~, Meo£: OffiR..l\\lE BLOCKS: :1N>E'lIT\\\\'IlliDF...A\\V S~5 p()'f,\\ER: BElOWLPSP 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 31EO-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; 1C11-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 100
HL T 5 NRC SRO 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 mrlhr.
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 mrlhr B. is; 9.9E+5 mrlhr
- c. is NOT; 3,000 mrlhr D. is NOT; 9.9E+5 mrlhr 72 of 100 HL T 5 NRC SRO 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 mrlhr B. is; 9.9E+5 mrlhr C. is NOT; 3,000 mr/hr D. is NOT; 9.9E+5 mr/hr 72 of 100
- 73.
HL T 5 NRC SRO 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 100
- 73.
HLT 5 NRC SRO 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 IA W 31GO-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 100
HL T 5 NRC SRO 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 100 HLT 5 NRC SRO 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 100
- 75.
HL T 5 NRC SRO 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-N21-00l-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 75 of 100
- 75.
HLT 5 NRC SRO 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 75 of 100
- 76.
HL T 5 NRC SRO Test Unit 2 was operating at 100% power when an A TWS occurred. The following conditions now currently exist:
o APRMs o Recirc pumps o RWL o Reactor pressure o SBLC 2A 0% power (100 control rods not full in)
Both Tripped
-60" to -90" controlled by RFPT 2B 843 psig controlled by EHC injecting with the following tank level TANK LEVEL 2C41-R601 2R25-S101 Which ONE of the following completes the following statements IA W CP-3, "ATWS Level Control" and RCA, "RPV Control (ATWS)"?
Reactor water level is required to be ____ and a reactor cooldown is ___ _
A. maintained in the present band; NOT allowed B. maintained in the present band; required to be commenced, but NOT to exceed lOooP/hr C. raised to between +3" to +50";
NOT allowed D. raised to between +3" to +50";
required to be commenced, but NOT to exceed lOooP/hr 76 of 100
- 76.
HL T 5 NRC SRO Test Unit 2 was operating at 100% power when an A TWS occurred. The following conditions now currently exist:
o APRMs o Recirc pumps o RWL o Reactor pressure o SBLC 2A 0% power (100 control rods not full in)
Both Tripped
-60" to -90" controlled by RFPT 2B 843 psig controlled by EHC injecting with the following tank level TANK lEVEL 2C41-R601 2R26-S101 80 60 40 o
P E
R C
E N
T Which ONE of the following completes the following statements IAW CP-3, "ATWS Level Control" and RCA, "RPV Control (ATWS),,?
Reactor water level is required to be _____ and a reactor cooldown is ____ _
A. maintained in the present band; NOT allowed B. maintained in the present band; required to be commenced, but NOT to exceed 100°F/hr C. raised to between +3" to +50";
NOT allowed D. raised to between +3" to +50";
required to be commenced, but NOT to exceed 100°F/hr 76 of 100
- 77.
HLT 5 NRC SRO Test Unit 1 is in Startup and all requirements are met for transferring the reactor mode switch to RUN IA W 34GO-OPS-001-1, "Plant Startup".
All IRMs are reading between 25 on range 9 and 30 on range 10.
I&C reports that ALL IRMs are inoperable for their neutron flux - High trip (will not give trip).
Which ONE of the choices below completes the following statements IA W Tech Specs?
The purpose of the IRMs is to monitor neutron flux levels between the upper range of the Source Range Monitors to the ___ _
The Reactor Mode Switch ____ be placed in the "RUN" mode.
A. low power setpoint of RWM; can B. lower range of the APRMs; can C. lower range of the APRMs; can NOT D. low power setpoint of RWM; canNOT 77 of 100
- 77.
HLT 5 NRC SRO Test Unit 1 is in Startup and all requirements are met for transferring the reactor mode switch to RUN IA W 34GO-OPS-00l-l, "Plant Startup".
All IRMs are reading between 25 on range 9 and 30 on range 10.
I&C reports that ALL IRMs are inoperable for their neutron flux - High trip (will not give trip).
Which ONE of the choices below completes the following statements IA W Tech Specs?
The purpose of the IRMs is to monitor neutron flux levels between the upper range of the Source Range Monitors to the ___ _
The Reactor Mode Switch ____ be placed in the "RUN" mode.
A. low power setpoint of RWM; can B. lower range of the APRMs; can C. lower range of the APRMs; can NOT D. low power setpoint of RWM; can NOT 77 of 100
HLT 5 NRC SRO Test
- 78.
Unit 2 is operating at 100% reactor power when the "2A" Recirc pump trips.
Which ONE of the following completes both of these statements?
Indicated reactor water level on 2C32-R606A, Band C, "Narrow Range" instruments will initially __ _
lAW with Tech Specs 3.4.1, "Recirculation Loops Operating", the MAXIMUM amount of time allowed to satisify the applicable LCO action statement is hours.
A. increase; 12 B. increase; 24 C. decrease; 24 D. decrease; 12 78 of 100 HLT 5 NRC SRO Test
- 78.
Unit 2 is operating at 100% reactor power when the "2A" Recirc pump trips.
Which ONE of the following completes both of these statements?
Indicated reactor water level on 2C32-R606A, Band C, "Narrow Range" instruments will initially __ _
IA W with Tech Specs 3.4.1, "Recirculation Loops Operating", the MAXIMUM amount of time allowed to satisify the applicable LCO action statement is hours.
A. increase; 12 B. increase; 24 C. decrease; 24 D. decrease; 12 78 of 100
- 79.
HL T 5 NRC SRO Test Unit 2 had been operating at full power with Rod 26-27 stuck at position 00. Consequently, the rod was declared inoperable and the HCU was disarmed in accordance with Tech Spec 3.1.3, Control Rod Operability.
Subsequently, Unit 2 has shutdown and is now in Day 10 of a refueling outage with control rod 26-27 still fully inserted and disarmed.
o The refueling crew is currently transferring a grappled fuel bundle from core location 09-10 to core location 25-08.
o Control rod 26-27's Full-In rod position channel fails such that the Full-In position indication to the refueling permissive logic is lost Given these plant conditions, which ONE of the following choices completes BOTH statements?
The Refueling Permissive Logic ____ allow the fuel bundle currently on the grapple to be lowered.
IA W Tech Spec Bases 3.9.4, the crew allowed to bypass the inoperable position channel on rod 26-27 to permit refueling operations to proceed.
A. will NOT; is B. will NOT; is NOT C. will; is D. will; is NOT 79 of 100
- 79.
HL T 5 NRC SRO Test Unit 2 had been operating at full power with Rod 26-27 stuck at position 00. Consequently, the rod was declared inoperable and the RCU was disarmed in accordance with Tech Spec 3.1.3, Control Rod Operability.
Subsequently, Unit 2 has shutdown and is now in Day 10 of a refueling outage with control rod 26-27 still fully inserted and disarmed.
o The refueling crew is currently transferring a grappled fuel bundle from core location 09-10 to core location 25-08.
o Control rod 26-27's Full-In rod position channel fails such that the Full-In position indication to the refueling permissive logic is lost Given these plant conditions, which ONE of the following choices completes BOTH statements?
The Refueling Permissive Logic _____ allow the fuel bundle currently on the grapple to be lowered.
IA W Tech Spec Bases 3.9.4, the crew allowed to bypass the inoperable position channel on rod 26-27 to permit refueling operations to proceed.
A. will NOT; is B. will NOT; is NOT C. will; is D. will; is NOT 79 of 100
- 80.
HL T 5 NRC SRO Test Unit 2 was operating at 100% while fuel movement was in progress to load a cask when minor damage to a fuel bundle resulted in the following conditions.
o 2D21-K60lM - 70 mRemfhr o 2D21-K611K - 65 mRemfhr o 2D21-K611L -70 mRemfhr o 2Dll-K634A - 15 mRemfhr o 2Dll-K634B - 14 mRemfhr o 2Dll-K634C - 18 mRemfhr o 2Dll-K634D - 19 mRemfhr Which ONE of the following identifies the total number of Unit I and Unit 2 Standby Gas Treatment Systems (SBGT) that will automatically start and the minimum required procedure(s)
IA W 31EO-EOP-014-2, "Secondary Containment Control" flowchart?
REFERENCE PROVIDED A. two (ONLY);
34AB-DII-001-2, "Radioactivity Release Control" ONLY B. four; 34AB-DII-00l-2, "Radioactivity Release Control" AND 34GO-OPS-013-2, "Normal Plant Shutdown" C. two (ONLY);
34AB-DII-00l-2, "Radioactivity Release Control" AND 34GO-OPS-013-2, "Normal Plant Shutdown" D. four; 34AB-DII-00l-2, "Radioactivity Release Control" ONLY 80 of 100
- 80.
HLT 5 NRC SRO Test Unit 2 was operating at 100% while fuel movement was in progress to load a cask when minor damage to a fuel bundle resulted in the following conditions.
o 2D21-K601M - 70 rnRernfhr o 2D21-K611K - 65 mRernfhr o 2D21-K611L - 70 rnRernfhr o 2DII-K634A - 15 mRernfhr o 2DII-K634B - 14 rnRernfhr o 2D 11-K634C - 18 rnRernfhr o 2Dll-K634D - 19 mRernfhr Which ONE of the following identifies the total number of Unit 1 and Unit 2 Standby Gas Treatment Systems (SBGT) that will automatically start and the minimum required procedure(s)
IA W 31EO-EOP-014-2, "Secondary Containment Control" flowchart?
REFERENCE PROVIDED A. two (ONLY);
34AB-DII-001-2, "Radioactivity Release Control" ONLY B. four; 34AB-DII-001-2, "Radioactivity Release Control" AND 34GO-OPS-013-2, "Normal Plant Shutdown"
- c. two (ONLY);
34AB-DII-001-2, "Radioactivity Release Control" AND 34GO-OPS-013-2, "Normal Plant Shutdown" D. four; 34AB-D 11-001-2, "Radioactivity Release Control" ONLY 80 of 100
- 81.
HLT 5 NRC SRO Test Unit 2 is operating at 100% power with "2F" 4160 V bus being powered from 2C Startup Auxiliary Transformer (SAT) and ACB 135574, 4160V Bus "2F" Normal Supply breaker, is under clearance for maintenance.
Which ONE of the choices below completes BOTH of the following statements?
IA W TS Bases 3.8.1, "AC Sources - Operating", entry into a TS Required Action Statement (RAS) required due to ACB 135574 being tagged out.
Subsequently Unit 2 (ONLY) experienced a loss of offsite power and offsite power has been restored to the Startup Transformers.
To transfer the "2F" bus to the "2C" Startup transformer, the Mode Switch for the Emergency Diesel powering the "2F" bus required to be placed in the "TEST" position.
A. is NOT; is NOT B. is NOT; is C. is ;
is NOT D. is ;
is 81 of 100
- 81.
HL T 5 NRC SRO Test Unit 2 is operating at 100% power with "2F" 4160 V bus being powered from 2C Startup Auxiliary Transformer (SAT) and ACB 135574, 4160V Bus "2F" Normal Supply breaker, is under clearance for maintenance.
Which ONE of the choices below completes BOTH of the following statements?
IA W TS Bases 3.8.1, "AC Sources - Operating", entry into a TS Required Action Statement (RAS) required due to ACB 135574 being tagged out.
Subsequently Unit 2 (ONLY) experienced a loss of offsite power and offsite power has been restored to the Startup Transformers.
To transfer the "2F" bus to the "2C" Startup transformer, the Mode Switch for the Emergency Diesel powering the "2F" bus required to be placed in the "TEST" position.
A. is NOT; is NOT B. is NOT; is C. is ;
is NOT D. is ;
is 81 of 100
- 82.
HL T 5 NRC SRO Test Unit 1 is operating at 100% power when the "lA" RWCU pump develops a severe leak and cannot be isolated. Area temperatures on the 158' Reactor Building are as followed:
Ambient Temperatures:
Pt.2 Hx Room (lG31-N016B)
Pt.3 "A" Pump Room (North) (lG31-N016C)
Differential Temperatures:
Pt.1 Hx Room (lG31-N022A1N023A)
Pt.2 A Pump Room (lG31-N022BIN023B)
Which ONE of the following choices correctly predicts the impact on the IDll-K609A-D "RB Bldg. Contaminated Area Radiation" monitors AND identifies the required procedure for controlling reactor pressure?
When IDll-K609A-D monitors exceed ____, the Reactor Building HVAC system will isolate.
Reactor pressure is required to be controlled using EOP Flowchart ___ _
REFERENCE PROVIDED A. 6.9 mr/hr; RC/P B. 18 mr/hr; RC/P C. 18 mr/hr; CP-l point G D. 6.9 mr/hr; CP-l point G 82 of 100
- 82.
HL T 5 NRC SRO Test Unit 1 is operating at 100% power when the "lA" RWCU pump develops a severe leak: and cannot be isolated. Area temperatures on the 158' Reactor Building are as followed:
Ambient Temperatures:
Pt.2 Hx Room (lG31-N016B)
Pt.3 "A" Pump Room (North) (lG31-N016C)
Differential Temperatures:
Pt.l Hx Room (1 G31-N022A1N023A)
Pt.2 A Pump Room (lG31-N022BIN023B)
Which ONE of the following choices correctly predicts the impact on the 1D11-K609A-D "RB Bldg. Contaminated Area Radiation" monitors AND identifies the required procedure for controlling reactor pressure?
When ID11-K609A-D monitors exceed ____, the Reactor Building HVAC system will isolate.
Reactor pressure is required to be controlled using EOP Flowchart ___ _
REFERENCE PROVIDED A. 6.9 mr/hr; RC/P B. 18 mr/hr; RC/P C. 18 mr/hr; CP-1 point G D. 6.9 mr/hr; CP-1 point G 82 of 100
- 83.
HLT 5 NRC SRO Test Unit 2 is at operating at 59% power with both Recirc Pumps operating at 48% speed when a transient occurs. Reactor power stabilizes at 57% power with the following Recirc indications:
o "A" and "B" Recirc Pump Speeds................................... 48%
o 2B21-R611A "TOTAL A FLOW".................................. 24 Mlbmlhr o 2B21-R611B "TOTAL B FLOW".................................. 12 Mlbmlhr The crew performs 34SV-SUV-023-2, "Jet Pump and Recirculation Flow Mismatch Operability".
The diffuser-to-Iower plenum differential pressure for Jet Pumps 5 & 6 differs by 50% from established patterns.
Which ONE of the following choices completes both of these statements concerning the operational status of the Recirc Pump loops, AND the MOST LIMITING required actions for the Recirc Loop and JET pump conditions?
IA W Tech Spec Bases 3.4.1, a recirculation loop is considered not in operation ___ _
The operator is required to enter ___ _
A. when the pump in that loop is idle OR when the mismatch between total jet pump flows of the two loops is greater than required limits; 34S0-B31-001-2, "Reactor Recirc System"and raise "B" loop flow within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. when the pump in that loop is idle OR when the mismatch between total jet pump flows of the two loops is greater than required limits; 34GO-OPS-013-2 "Normal Plant Shutdown" and be in mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- c. ONLY when the pump in that loop is idle; 34S0-B31-001-2, "Reactor Recirc System"and raise "B" loop flow within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. ONLY when the pump in that loop is idle; 34GO-OPS-013-2 "Normal Plant Shutdown" and be in mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
83 of 100
- 83.
HLT 5 NRC SRO Test Unit 2 is at operating at 59% power with both Recirc Pumps operating at 48% speed when a transient occurs. Reactor power stabilizes at 57% power with the following Recirc indications:
o "A" and "B" Recirc Pump Speeds................................... 48%
o 2B21-R611A "TOTAL A FLOW".................................. 24 Mlbmlhr o 2B21-R611B "TOTAL B FLOW".................................. 12 Mlbmlhr The crew performs 34SV -SUV -023-2, "Jet Pump and Recirculation Flow Mismatch Operability".
The diffuser-to-Iower plenum differential pressure for Jet Pumps 5 & 6 differs by 50% from established patterns.
Which ONE of the following choices completes both of these statements concerning the operational status of the Recirc Pump loops, AND the MOST LIMITING required actions for the Recirc Loop and JET pump conditions?
IA W Tech Spec Bases 3.4.1, a recirculation loop is considered not in operation ____ _
The operator is required to enter ___ _
A. when the pump in that loop is idle OR when the mismatch between total jet pump flows of the two loops is greater than required limits; 34S0-B31-001-2, "Reactor Recirc System"and raise "B" loop flow within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. when the pump in that loop is idle OR when the mismatch between total jet pump flows of the two loops is greater than required limits; 34GO-OPS-013-2 "Normal Plant Shutdown" and be in mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- c. ONLY when the pump in that loop is idle; 34S0-B31-00l-2, "Reactor Recirc System"and raise "B" loop flow within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. ONLY when the pump in that loop is idle; 34GO-OPS-013-2 "Normal Plant Shutdown" and be in mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
83 of 100
- 84.
HLT 5 NRC SRO Test Unit 2 is at 80% power with a normal plant shutdown in progress due to a loss of 250V DC RX BLDG MCC 2B, 2R24-S022.
A transient subsequently occurs causing the following conditions:
o APRMs................................................................ 6%
o RWL................................................................... -175 inches, going down 2"/min o DW pressure....................................................... 3.5 psig o Reactor pressure.................................................. 880 psig controlled by LLS o MSIV s................................................................. closed Which ONE of the following completes both statements?
The System is available for RWL control.
IA W EOP flowcharts, if the current RWL trend continues for the next 5 minutes, the operator will be required to perform to control RWL.
A. HPCI; 31EO-EOP-114-2, "Preventing Injection Into The RPV From Core Spray And LPCI" B. RCIC; 31EO-EOP-114-2, "Preventing Injection Into The RPV From Core Spray And LPCI" C. HPCI; 31EO-EOP-113-2, "Terminating And Preventing Injection Into The RPV" D. RCIC; 31EO-EOP-113-2, "Terminating And Preventing Injection Into The RPV" 84 of 100
- 84.
HLT 5 NRC SRO Test Unit 2 is at 80% power with a normal plant shutdown in progress due to a loss of 250V DC RX BLDG MCC 2B, 2R24-S022.
A transient subsequently occurs causing the following conditions:
o APRMs................................................................ 6%
o RWL................................................................... -175 inches, going down 2"/min o DW pressure....................................................... 3.5 psig o Reactor pressure.................................................. 880 psig controlled by LLS o MSIV s................................................................. closed Which ONE of the following completes both statements?
The System is available for RWL control.
IA W EOP flowcharts, if the current RWL trend continues for the next 5 minutes, the operator will be required to perform to control RWL.
A. HPCI; 31EO-EOP-114-2, "Preventing Injection Into The RPV From Core Spray And LPCI" B. RCIC; 3 1 EO-EOP-l 14-2, "Preventing Injection Into The RPV From Core Spray And LPCI" C. HPCI; 3 1 EO-EOP-l 13-2, "Terminating And Preventing Injection Into The RPV" D. RCIC; 3 1 EO-EOP-l 13-2, "Terminating And Preventing Injection Into The RPV" 84 of 100
- 85.
HLT 5 NRC SRO Test Unit 2 is operating at 25% power when alarm 650-136 "Vibration Alarm" is received with the following Main Turbine vibration values:
o Bearing #IX - 11 mils o Bearing #2X - 14 mils o Bearing #1 Y - 10 mils o Bearing #2Y - 10 mils Which ONE of the following completes both statements concerning Main Turbine operation?
The Unit 2 Main Turbine ___ tripped.
In general, the LOWEST level of authority required to disable the Main Turbine high vibration trips is the and the System Engineer lAW 34AR-650-136.
A. has NOT; Unit 2 Shift Supervisor B. has; Operations Manager C. has NOT; Operations Manager D. has; Unit 2 Shift Supervisor 85 of 100
- 85.
HL T 5 NRC SRO Test Unit 2 is operating at 25% power when alarm 650-136 "Vibration Alarm" is received with the following Main Turbine vibration values:
o Bearing #IX - 11 mils o Bearing #2X - 14 mils o Bearing # 1 Y - 10 mils o Bearing #2Y - 10 mils Which ONE of the following completes both statements concerning Main Turbine operation?
The Unit 2 Main Turbine ___ tripped.
In general, the LOWEST level of authority required to disable the Main Turbine high vibration trips is the and the System Engineer lAW 34AR-650-136.
A. has NOT; Unit 2 Shift Supervisor B. has; Operations Manager C. has NOT; Operations Manager D. has; Unit 2 Shift Supervisor 85 of 100
- 86.
HLT 5 NRC SRO Test Unit 2 was at 100% power when the following alarm was received:
REACTOR VESSEL HIGH PRESSURE TRIP (603 -lOS) o Torus water level decreases to 88" o RPV pressure is now 760 psig The operator controlling Rx pressure reports that ONLY 4 SRVs are operable.
Which ONE of the following identifies the alarm setpoint and the required procedure to control reactor pressure?
The alarm setpoint is psig.
IA W 31EO-EOP-OlS-2, "CP-l ", RPV pressure will be controlled using __ _
A. 1074; 31EO-EOP-107-2 "Alternate RPV Pressure Control" B. lOSS; 31EO-EOP-107-2 "Alternate RPV Pressure Control" C. 1074; 31EO-EOP-108-2 "Alternate RPV Depressurization" D. lOSS; 31EO-EOP-I08-2 "Alternate RPV Depressurization" 86 of 100
- 86.
HLT 5 NRC SRO Test Unit 2 was at 100% power when the following alarm was received:
REACTOR VESSEL HIGH PRESSURE TRIP (603 -105) o Torus water level decreases to 88" o RPV pressure is now 760 psig The operator controlling Rx pressure reports that ONLY 4 SRVs are operable.
Which ONE of the following identifies the alarm setpoint and the required procedure to control reactor pressure?
The alarm setpoint is psig.
lAW 3IEO-EOP-015-2, "CP-I ", RPV pressure will be controlled using __ _
A. 1074; 3IEO-EOP-107-2 "Alternate RPV Pressure Control" B. 1055; 3IEO-EOP-107-2 "Alternate RPV Pressure Control" C. 1074; 31EO-EOP-I08-2 "Alternate RPV Depressurization" D. 1055; 31EO-EOP-I08-2 "Alternate RPV Depressurization" 86 of 100
- 87.
HLT 5 NRC SRO Test Which ONE of the choices below completes the following statement IA W 34AB-T47-00l-2, Complete Loss of Drywell Cooling, Attachment 1, Peak: Drywell Temperature?
The crew is required to enter ____ when any peak: temperature listed in Attachment 1 has been exceeded for at least ___ _
A. 34AB-C71-001-2, Reactor Scram Procedure; 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 34AB-C71-001-2, Reactor Scram Procedure; 30 minutes C. 34GO-OPS-0l4-2, Fast Reactor Shutdown; 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. 34GO-OPS-014-2, Fast Reactor Shutdown; 30 minutes 87 of 100
- 87.
HLT 5 NRC SRO Test Which ONE of the choices below completes the following statement IA W 34AB-T47-001-2, Complete Loss of Drywell Cooling, Attachment I, Peak Drywell Temperature?
The crew is required to enter ____ when any peak temperature listed in Attachment 1 has been exceeded for at least ___ _
A. 34AB-C71-001-2, Reactor Scram Procedure; 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 34AB-C71-001-2, Reactor Scram Procedure; 30 minutes C. 34GO-OPS-014-2, Fast Reactor Shutdown; 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. 34GO-OPS-014-2, Fast Reactor Shutdown; 30 minutes 87 of 100
- 88.
HLT 5 NRC SRO Test Unit 2 is at 15% power following a refueling outage with HPCI running for surveillence 34SV-E41-002-2, "HPCI PUMP OPERABILITY".
lAW Tech Specs 3.6.2.1,which ONE of the following identifies the LCO for Suppression Pool Average Temperature when HPCI testing is in progress, including the bases for this value?
A. 100°F This value was chosen to ensure that the resultant peak accident temperature is maintained below the drywell design temperature.
B. lOO°F This value was chosen to ensure that the unit has testing flexibility, and to provide margin below the 110°F limit at which a reactor shutdown is required.
C. 105°F; This value was chosen to ensure that the unit has testing flexibility, and to provide margin below the 110°F limit at which a reactor shutdown is required.
D. lO5°F This value was chosen to ensure that the resultant peak accident temperature is maintained below the drywell design temperature.
88 of 100
- 88.
HLT 5 NRC SRO Test Unit 2 is at 15% power following a refueling outage with HPCI running for surveillence 34SV-E41-002-2, "HPCI PUMP OPERABILITY".
lAW Tech Specs 3.6.2.1, which ONE of the following identifies the LCO for Suppression Pool Average Temperature when HPCI testing is in progress, including the bases for this value?
A. 100°F This value was chosen to ensure that the resultant peak accident temperature is maintained below the drywell design temperature.
B. lOO°F This value was chosen to ensure that the unit has testing flexibility, and to provide margin below the 110°F limit at which a reactor shutdown is required.
C. lO5°F; This value was chosen to ensure that the unit has testing flexibility, and to provide margin below the 110°F limit at which a reactor shutdown is required.
D. lO5°F This value was chosen to ensure that the resultant peak accident temperature is maintained below the drywell design temperature.
88 of 100
- 89.
HLT 5 NRC SRO Test Unit 1 is at 100% power. The ADS air supply header pressure decreases to 60 psig.
Which ONE of the following identifies the LOWEST required pneumatic supply header pressure to the ADS valve accumulators and the basis for this value following a failure of the pneumatic supply in accordance with Tech Specs SR 3.5.1.3 and Tech Spec Bases?
A. 80 psig supply pressure ensures the accumulators will accommodate at least TWO valve actuations with the drywell at 70% design pressure.
B. 80 psig supply pressure ensures the accumulators will accommodate at least FIVE valve actuations with the drywell at 70% design pressure.
- c. 90 psig supply pressure ensures the accumulators will accommodate at least TWO valve actuations with the drywell at 70% design pressure.
D. 90 psig supply pressure ensures the accumulators will accommodate at least FIVE valve actuations with the drywell at 70% design pressure.
89 of 100
- 89.
HLT 5 NRC SRO Test Unit 1 is at 100% power. The ADS air supply header pressure decreases to 60 psig.
Which ONE of the following identifies the LOWEST required pneumatic supply header pressure to the ADS valve accumulators and the basis for this value following a failure of the pneumatic supply in accordance with Tech Specs SR 3.5.1.3 and Tech Spec Bases?
A. 80 psig supply pressure ensures the accumulators will accommodate at least TWO valve actuations with the drywell at 70% design pressure.
B. 80 psig supply pressure ensures the accumulators will accommodate at least FIVE valve actuations with the drywell at 70% design pressure.
C. 90 psig supply pressure ensures the accumulators will accommodate at least TWO valve actuations with the drywell at 70% design pressure.
D. 90 psig supply pressure ensures the accumulators will accommodate at least FIVE valve actuations with the drywell at 70% design pressure.
89 of 100
- 90.
HLT 5 NRC SRO Test Unit 2 was operating at 100% power when an A TWS occurred and the following conditions currently exist:
o Reactor Power......................2.5% (Highest power since scram was 9%)
o Reactor pressure................... 960 psig maintained by LLS o Reactor water level.............. -85" maintained using RCIC o Torus level........................... 97 inches and slowly lowering o HPCI................................... Out of service Which ONE of the following identifies the MINIMUM required procedures?
A. ONLY 31EO-EOP-015-2, CP-l, Emergency Depressurization; 31EO-EOP-113-2, Terminating And/Or Preventing Injection Into The RPV is NOT required.
B. ONLY 31EO-EOP-113-2, Terminating And/Or Preventing Injection Into The RPV 31EO-EOP-015-2, CP-l, Emergency Depressurization is NOT required C. NEITHER 3 1 EO-EOP-O 1 5-2, CP-l, Emergency Depressurization NOR 31EO-EOP-113-2, Terminating And/Or Preventing Injection Into The RPV is required D. 31EO-EOP-015-2, CP-l, Emergency Depressurization AND 31EO-EOP-113-2, Terminating And/Or Preventing Injection Into The RPV 90 of 100
- 90.
HLT 5 NRC SRO Test Unit 2 was operating at 100% power when an A TWS occurred and the following conditions currently exist:
o Reactor Power...................... 2.5% (Highest power since scram was 9%)
o Reactor pressure................... 960 psig maintained by LLS o Reactor water level.............. -85" maintained using RCIC o Torus level........................... 97 inches and slowly lowering o HPCI................................... Out of service Which ONE of the following identifies the MINIMUM required procedures?
A. ONLY 31EO-EOP-015-2, CP-l, Emergency Depressurization; 31EO-EOP-113-2, Terminating And/Or Preventing Injection Into The RPV is NOT required.
B. ONLY 3 1 EO-EOP-l 13-2, Terminating And/Or Preventing Injection Into The RPV 31EO-EOP-015-2, CP-l, Emergency Depressurization is NOT required C. NEITHER 3 1 EO-EOP-Ol 5-2, CP-l, Emergency Depressurization NOR 31EO-EOP-113-2, Terminating And/Or Preventing Injection Into The RPV is required D. 31EO-EOP-015-2, CP-l, Emergency Depressurization AND 31EO-EOP-113-2, Terminating And/Or Preventing Injection Into The RPV 90 of 100
- 91.
HLT 5 NRC SRO Test Unit 2 was operating at 100% power when a transient occurred causing the following indications:
o 2B21-R623A "Fuel Zone"........................ -160 inches, decreasing 2"/minute o 2B21-R623B "Fuel Zone"........................ -163 inches, decreasing 2"/minute o RHR Pump "2D"................................. Green and White lights are illuminated, Red light extinquished Which ONE of the following completes both of these statements?
RHR pump "2D" has __ _
Reactor water level control will be directed from ---
A. been manually secured; 31EO-EOP-01O-2, "RC" (Non-ATWS) flow chart, RClLpath B. been manually secured; 31EO-EOP-015-2, "CP-1" flow chart, Alternate Level Control path C. automatically tripped; 31EO-EOP-01O-2, "RC" (Non-ATWS) flow chart, RCIL path D. automatically tripped; 31EO-EOP-015-2, "CP-1" flow chart, Alternate Level Control path 91 of 100
- 91.
HLT 5 NRC SRO Test Unit 2 was operating at lOO% power when a transient occurred causing the following indications:
o 2B21-R623A "Fuel Zone"........................ -160 inches, decreasing 2"/minute o 2B21-R623B "Fuel Zone"........................ -163 inches, decreasing 2"/minute o RHR Pump "2D"................................. Green and White lights are illuminated, Red light extinquished Which ONE of the following completes both of these statements?
RHR pump "2D" has __ _
Reactor water level control will be directed from ---
A. been manually secured; 31EO-EOP-01O-2, "RC" (Non-ATWS) flow chart, RCIL path B. been manually secured; 31EO-EOP-01S-2, "CP-1" flow chart, Alternate Level Control path C. automatically tripped; 31EO-EOP-01O-2, "RC" (Non-ATWS) flow chart, RCIL path D. automatically tripped; 31EO-EOP-015-2, "CP-1" flow chart, Alternate Level Control path 91 of 100
- 92.
HL T 5 NRC SRO Test Unit 2 is operating at 100% power and the following annunciators are in alarm due to a leak on a RBCCW pipe elbow in the Reactor Building:
o RBCCW SURGE TK LEVEL LOW OR EXCESS LEAKAGE (650-248) o RBCCW PUMPS DISCH PRESS LOW (650-239)
Subsequent investigation reveals the following conditions:
o RBCCW surge tank sight glass is lower than normal but stable with the make-up valve fully open o 2P42-R601, RBCCW Pump Discharge Pressure Indicator is at 85 psig and stable Which ONE of the following identifies an appropriate action IA W 34AB-P42-001-2, Loss of RBCCW, and the LOWEST level of authority required to approve "Emergency Maintenance" on the pipe elbow in accordance with 50AC-MNT-00I-0?
A. Trip the operating RWCU pump; Unit Shift Supervisor B. Trip the operating RWCU pump; Shift Manager C. Trip the operating CRD pump; Unit Shift Supervisor D. Trip the operating CRD pump; Shift Manager 92 of 100
- 92.
HLT 5 NRC SRO Test Unit 2 is operating at 100% power and the following annunciators are in alarm due to a leak on a RBCCW pipe elbow in the Reactor Building:
o RBCCW SURGE TK LEVEL LOW OR EXCESS LEAKAGE (650-248) o RBCCW PUMPS DISCH PRESS LOW (650-239)
Subsequent investigation reveals the following conditions:
o RBCCW surge tank sight glass is lower than normal but stable with the make-up valve fully open o 2P42-R601, RBCCW Pump Discharge Pressure Indicator is at 85 psig and stable Which ONE of the following identifies an appropriate action IA W 34AB-P42-001-2, Loss of RBCCW, and the LOWEST level of authority required to approve "Emergency Maintenance" on the pipe elbow in accordance with 50AC-MNT-00I-0?
A. Trip the operating RWCU pump; Unit Shift Supervisor B. Trip the operating RWCU pump; Shift Manager C. Trip the operating CRD pump; Unit Shift Supervisor D. Trip the operating CRD pump; Shift Manager 92 of 100
- 93.
HLT 5 NRC SRO Test At 1200 the Northern Control Center (NCC) notified the Control Room Operator that the 230KV Bus voltage cannot be maintained above the normal minimum voltage.
The following parameters currently exist on Unit 2:
o Main Generator H2 pressure....... 43 psig o Main Generator Megawatt...... 860 MWe o Main Generator Megavar..... +280 MVar o "2E" 4160 V Emergency Bus volts......... 3820 volts o "2F" 4160 V Emergency Bus volts......... 3820 volts o "2G" 4160 V Emergency Bus volts......... 3815 volts Which ONE of the following completes BOTH of these statements?
The Unit 2 Main Generator is operating ___ the acceptable limits of the generator capability curve.
IA W 34AB-S11-001-0, Operation With Degraded System Voltage", after 30 minutes, a MINIMUM of required to be supplied from the Emergency Diesel Generator(s) on Unit 2,.
REFERENCE PROVIDED A. within; one 4160 V Emergency bus is B. within; two 4160 V Emergency busses are C. outside; one 4160 V Emergency bus is D. outside; two 4160 V Emergency busses are 93 of 100
- 93.
HLT 5 NRC SRO Test At 1200 the Northern Control Center (NCC) notified the Control Room Operator that the 230KV Bus voltage cannot be maintained above the normal minimum voltage.
The following parameters currently exist on Unit 2:
o Main Generator H2 pressure....... 43 psig o Main Generator Megawatt...... 860 MWe o Main Generator Megavar..... +280 MVar o "2E" 4160 V Emergency Bus volts......... 3820 volts o "2P" 4160 V Emergency Bus volts......... 3820 volts o "2G" 4160 V Emergency Bus volts......... 3815 volts Which ONE of the following completes BOTH of these statements?
The Unit 2 Main Generator is operating ___ the acceptable limits of the generator capability curve.
IA W 34AB-S 11-001-0, Operation With Degraded System Voltage", after 30 minutes, a MINIMUM of required to be supplied from the Emergency Diesel Generator(s) on Unit 2,.
REFERENCE PROVIDED A. within; one 4160 V Emergency bus is B. within; two 4160 V Emergency busses are C. outside; one 4160 V Emergency bus is D. outside; two 4160 V Emergency busses are 93 of 100
- 94.
HLT 5 NRC SRO Test Unit 2 was operating at 100% reactor power with 2EII-FOI7A, "RHR Outbd Injection Valve" tagged in "Close" for repair. The following occurs:
o Group 1 isolation signal, o All MSN switches have been taken to closed position o Both MSN's in the "C" MSL are still open o Reports of a steam leak in the Reactor Building have been received o Main Steam Line Tunnel Ambient and Differential Temperature Alarms are lit o A partial loss of High pressure feed water. Only RCIC is available for injection.
Currently:
o Compensated RWL is -160" and is stable o Un-compensated RWL is -170" Which ONE of the following completes both of these statements?
lAW 34S0-EII-01O-2, "RHR SYSTEM," in order to place the "A" Loop of RHR in Torus Cooling, the interlock override switch(es) that MUST be manipulated is (are) ___ _
The HIGHEST REQUIRED emergency classification is a ____ emergency lAW 73EP-EIP-00l-0, "Emergency Classifications and Initial Actions".
NOTE:
2Ell-S 17 A is the Containment Spray Valve switch 2Ell-S 18A is the Cnmt Spray Vlv Cntl 2/3 Core Ht Permissive switch REFERENCE PROVIDED A. 2Ell-SI7A ONLY General B. 2Ell-SI7A ONLY Site Area C. 2Ell-SI7A and 2Ell-SI8A General D. 2Ell-SI7A and 2Ell-SI8A Site Area 94 of 100
- 94.
HL T 5 NRC SRO Test Unit 2 was operating at 100% reactor power with 2Ell-F017A, "RHR Outbd Injection Valve" tagged in "Close" for repair. The following occurs:
o Group 1 isolation signal, o All MSN switches have been taken to closed position o Both MSN's in the "c" MSL are still open o Reports of a steam leak in the Reactor Building have been received o Main Steam Line Tunnel Ambient and Differential Temperature Alarms are lit o A partial loss of High pressure feedwater. Only RCIC is available for injection.
Currently:
o Compensated RWL is -160" and is stable o Un-compensated RWL is -170" Which ONE of the following completes both of these statements?
IA W 34S0-E11-0l0-2, "RHR SYSTEM," in order to place the "A" Loop of RHR in Torus Cooling, the interlock override switch(es) that MUST be manipulated is (are) ___ _
The HIGHEST REQUIRED emergency classification is a ____ emergency IA W 73EP-EIP-001-0, "Emergency Classifications and Initial Actions".
NOTE:
2E1l-S 17 A is the Containment Spray Valve switch 2E11-S 18A is the Cnmt Spray Vlv Cntl 2/3 Core Ht Permissive switch REFERENCE PROVIDED A. 2Ell-S17A ONLY General B. 2Ell-S17A ONLY Site Area C. 2Ell-S17A and 2Ell-S18A General D. 2Ell-S17A and 2Ell-S18A Site Area 94 of 100
- 95.
HL T 5 NRC SRO Test Unit 1 is starting up from a scheduled Refueling outage. Control rod movement is in progress to raise reactor power to 5% power. The Shift Manager and the Shift Technical Advisor, along with the following, are in the main control room:
Unit 1 Unit 2 o Shift Supervisor Shift Supervisor o Reactivity Management SRO o 3 NPOs INPO Which ONE of the following completes both of these statements?
lAW with 30AC-OPS-003-0, "Plant Operations" and NMP-OS-OOI, "Reactivity Management Program" the number of NPOs on Unit 1 meet the minimum required.
Any changes to the Unit 1 reactivity plan must be approved by the ___ _
A. does; Reactivity Management SRO B. does; Shift Supervisor C. does NOT; Reactivity Management SRO D. does NOT; Shift Supervisor 95 of 100
- 95.
HLT 5 NRC SRO Test Unit 1 is starting up from a scheduled Refueling outage. Control rod movement is in progress to raise reactor power to 5% power. The Shift Manager and the Shift Technical Advisor, along with the following, are in the main control room:
Unit 1 Unit 2 o Shift Supervisor Shift Supervisor o Reactivity Management SRO o 3 NPOs I NPO Which ONE of the following completes both of these statements?
IA W with 30AC-OPS-003-0, "Plant Operations" and NMP-OS-OOI, "Reactivity Management Program" the number of NPOs on Unit 1 meet the minimum required.
Any changes to the Unit 1 reactivity plan must be approved by the ___ _
A. does; Reactivity Management SRO B. does; Shift Supervisor C. does NOT; Reactivity Management SRO D. does NOT; Shift Supervisor 95 of 100
HLT 5 NRC SRO Test
- 96.
Unit 2 is starting up with the Reactor Mode switch in the "Start & Hot Stby" position.
o All control rods are fully inserted.
o I&C reports that the "A" & "B" SRM Channel Check surveillance was missed.
Which ONE of the following completes both of these statements?
lAW 34GO-OPS-001-2, "Plant Startup" and Tech Specs, all operable SRM channels must be indicating a MINIMUM of cps.
lAW Tech Specs SR 3.0.3, the "A" & "B" SRMs REQUIRED to be declared inoperable immediately because of the MISSED surveillance.
A. 3; are B. 5; are C. 3; are NOT D. 5; are NOT 96 of 100 HLT 5 NRC SRO Test
- 96.
Unit 2 is starting up with the Reactor Mode switch in the "Start & Hot Stby" position.
o All control rods are fully inserted.
o I&C reports that the "A" & "B" SRM Channel Check surveillance was missed.
Which ONE of the following completes both of these statements?
lAW 34GO-OPS-001-2, "Plant Startup" and Tech Specs, all operable SRM channels must be indicating a MINIMUM of cps.
lAW Tech Specs SR 3.0.3, the "A" & "B" SRMs REQUIRED to be declared inoperable immediately because of the MISSED surveillance.
A. 3',
are B. 5',
are C. 3',
are NOT D. 5',
are NOT 96 of 100
- 97.
HLT 5 NRC SRO Test Unit 2 is operating at 100% power when it is discovered that the "A" ADS valve, 2B21-FOI3A, is inop for its ADS function.
lAW with 31 GO-OPS-006-0, "Conditions, Required Actions and Completion Times", which ONE of the following completes following statement.
A (An) ___ Required Action Sheet is required.
The Shift Supervisor and Shift Manager must ___ in the appropriate boxes below.
I SS SIGN I TSA ACTIVE A. Tracking; ONLY initial (signature is NOT allowed)
B. Active; sign C. Active; ONLY initial (signature is NOT allowed)
D. Tracking; sign 97 of 100 SOS SIGN I
- 97.
HLT 5 NRC SRO Test Unit 2 is operating at 100% power when it is discovered that the "A" ADS valve, 2B21-F013A, is inop for its ADS function.
lAW with 31GO-OPS-006-0, "Conditions, Required Actions and Completion Times", which ONE of the following completes following statement.
A (An) ___ Required Action Sheet is required.
The Shift Supervisor and Shift Manager must ___ in the appropriate boxes below.
I SS SIGN I TSA ACTIVE A. Tracking; ONLY initial (signature is NOT allowed)
B. Active; sign C. Active; ONLY initial (signature is NOT allowed)
D. Tracking; sign 97 of 100 SOS SIGN I
- 98.
HL T 5 NRC SRO Test Which ONE of the following choices answers both of these statements IA W with the requirements of 73EP-RAD-00 1-0, "Radiological Event"?
When one Area Radiation Monitor (ARM) UNEXPECTEDLY alarms and radiation levels in the vicinity of the monitor have risen to 10 times normal, then a is required.
The is the MINIMUM level of qualification necessary to declare a Radiological Event AND will make immediate decisions concerning Emergency Call List notifications.
A. Plant Page Announcement Shift Manager B. Plant Page Announcement Control Room Shift Supervisor C. Notification of Unusual Event declaration Shift Manager D. Notification of Unusual Event declaration Control Room Shift Supervisor 98 of 100
- 98.
HLT 5 NRC SRO Test Which ONE of the following choices answers both of these statements IA W with the requirements of 73EP-RAD-OOl-O, "Radiological Event"?
When one Area Radiation Monitor (ARM) UNEXPECTEDLY alarms and radiation levels in the vicinity of the monitor have risen to 10 times normal, then a is required.
The is the MINIMUM level of qualification necessary to declare a Radiological Event AND will make immediate decisions concerning Emergency Call List notifications.
A. Plant Page Announcement Shift Manager B. Plant Page Announcement Control Room Shift Supervisor C. Notification of Unusual Event declaration Shift Manager D. Notification of Unusual Event declaration Control Room Shift Supervisor 98 of 100
- 99.
HLT 5 NRC SRO Test IA W 73EP-EIP-004-0, "Duties Of Emergency Director", which ONE of the following completes both of these statements?
If the SM is unavailable, then the __ unit's Shift Supervisor (SS) will become the Emergency Director.
If the SM is unavailable and the event involves BOTH units, the __ Shift Supervisor (SS) will become the Emergency Director. "
A. affected; Unit 1 B. affected; Unit 2 C. Non-affected; Unit 1 D. Non-affected; Unit 2 99 of 100
- 99.
HLT 5 NRC SRO Test IA W 73EP-EIP-004-0, "Duties Of Emergency Director", which ONE of the following completes both of these statements?
If the SM is unavailable, then the __ unit's Shift Supervisor (SS) will become the Emergency Director.
If the SM is unavailable and the event involves BOTH units, the __ Shift Supervisor (SS) will become the Emergency Director. "
A. affected; Unit 1 B. affected; Unit 2 C. Non-affected; Unit 1 D. Non-affected; Unit 2 99 of 100
100.
HLT 5 NRC SRO Test Unit 1 is at 100% power with the IB EDG tagged out of service for repairs. The following sequence of events occurs:
o 1130 Offsite power is lost to Unit 1 ONLY o 1135 SO reports lA EDG Jacket Water Temp of 200oP, rising 0.5°P Imin o 1145 lC EDG trips on Differential Lockout o 1205 Current Time Which ONE of the choices below completes the following statement?
The HIGHEST required emergency classification is a(n) __ _
Once formal declaration of the event is made the MAXIMUM amount of time allowed to make initial notification to State and local governments is __ _
REFERENCE PROVIDED A. Alert; 15 minutes B. Alert; 30 minutes C. Site Area Emergency; 15 minutes D. Site Area Emergency; 30 minutes End of Exam 100 of 100 100.
HLT 5 NRC SRO Test Unit 1 is at 100% power with the IB EDG tagged out of service for repairs. The following sequence of events occurs:
o 1130 Offsite power is lost to Unit 1 ONLY o 1135 SO reports lA EDG Jacket Water Temp of 200°F, rising 0.5°F Imin o 1145 lC EDG trips on Differential Lockout o 1205 Current Time Which ONE of the choices below completes the following statement?
The HIGHEST required emergency classification is a(n) __ _
Once formal declaration of the event is made the MAXIMUM amount of time allowed to make initial notification to State and local governments is __ _
REFERENCE PROVIDED A. Alert; 15 minutes B. Alert; 30 minutes C. Site Area Emergency; 15 minutes D. Site Area Emergency; 30 minutes End of Exam 100 of 100