IR 05000413/1993301
| ML20058B052 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/12/1993 |
| From: | Ernstes M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058B021 | List: |
| References | |
| RTR-NUREG-1021 50-413-93-301, NUDOCS 9312010375 | |
| Download: ML20058B052 (85) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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REGION 11 S
101 MARIETTA STREET, N.W., SUITE 2900
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3 ATLANTA, GEORGIA 303234199 E
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Report No.: 50- % 3/93-301 Licensee: Duke Power Company Docket Nos.:
50-413 and 50-414 License Nos.: NPF-35, NPF-52 Facility Name: Catawba Nuclear Plant Examination Conducted: October 21, 1993 Chief Examiner:
y Michael E. Ernstes V
Date Signed WL E
Approved By:
Lawrence L. Lawyer, Chief
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Date Signed Operator Licensing Section
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Operations Branch Division of Reactor Safety
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SUMMARY Scope:
An NRC examiner conducted regular, announced operator licensing requalification examinations on October 21, 1993.
Examiners-administered examinations under the guidelines of the Examiner-Standards (ES), NUREG-1021, Revision 7.
One Senior Reactor Operator (SRO) received a walkthrough examination and one Reactor Operator (RO) received a written examination.
Results:
Operator Pass / Fail:
SR0 R0 Total Percent Crews Percent Pass
1
100%
N/A N/A v
Fail
0
0%
N/A N/A There was no requalification program evaluation made due to the small sample size of operators.
No violations or deviations were identified.
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9312010375 931115 ADOCK0500g3 PDR
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REPORT DETAILS 1.
Persons Contacted Licensee Employees S. Frye, Director Operations Training C. Nodine, Instructor K. Phillips, Instructor Other licensee employees contacted included instructors and operators.
2.
Discussion a.
Scope An NRC examiner conducted regular, announced operator licensing I
requalification examinations on October 21, 1993. The examiner administered examinations under the guidelines of NUREG-1021, Revision 7.
The examinations were administered to licensed operators who had failed the NRC administered requalification examinations in May 1993.
One SR0 received a walkthrough examination and one R0 received a written examination.
b.
Results Both operators passed the examinations. There was no requalification program evaluation made due to the small sample size of operators.
c.
Proposed Examinations The proposed examinations met the guidelines of NUREG-1021, Revision 7.
The written examinations and Job Performance Measures-(JPMs) were written at a cognitive level which gave a valid test of the operators'
ability to apply knowledge of plant systems and procedures. The proposed JPMs noted some steps as critical that had no measurable performance standard. These steps only required verification of an indication with no measurable action. The exam team changed these steps to non-critical.
No other changes to the examinations were required.
3.
Exit Interview
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At the conclusion of the site visit, the examiner met with representatives of the plant staff listed in paragraph I to discuss the results of the examinations.
The licensee did not identify as proprietary any material
provided to, or reviewed by the examiners. Dissenting comments were not S
received from the licensee.
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U.S. NUCLEAR REGULATORY COMMISSION
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CATAWBA NUCLEAR STATION REQUALIFICATION EXAMINATION NAME CLASS. PART A TEST #: SOA934R 10/24/93 DATE DATE
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Page 1 of 17 S.S.#:
REFERENCE SET USED:
Originated:
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Approved
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SCORE
% OF CATEGORY TOTAL POINTS:
16.00 TOTAL QUESTIONS: 16.0
INSTRUCTIONS:
1.
Put your name on each answer sheet.
2.
Write your answers on the answer sheets.
3.
Ask the test monitor / instructor concerning questions which are not clear to you.
4.
Cheating or evidence of cheating will not be tolerated.
My signature on this form is my declaration that the responses given on the attached test or quiz are entirely my own.
It further declares that I am aware that I am subject to termination from the training program immediately, and in addition, will be subject to further disciplinary action up to and including discharge from the company for cheating and/or compromising on exams / tests, i
Students Signature
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1.
(1,00 pts.)
Which one of the following describes the effect of the low VG pressure on 1A D/G7 A.
Will prevent an automatic start attempt on a blackout but will allow an automatic start attempt on a LOCA.
B.
Will allow an automatic start on either blackout or j
LOCA, but D/G will not attain speed necessary for start.
C.
Will prevent an automatic start on a LOCA, but will allow an automatic start on a blackout.
D.
Will prevent an automatic start on either blackout or LOCA, but will allow a manual start attempt to be made.
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2.
(1.00 pts.)
If
'B' NI pump becomes inoperable, what would be the required Tech Spec. action?
A.
Enter T.S.
3.0.3; Be in Mode 3 in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
B.
Apply T.S.
3.8.1.1 (A.C. Sources), action C.; Be in Mode 3 in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Apply T.S.
3.5.2 (ECCS Subsystems - Tave > 350 deg F),
action a.; Be in Mode 3 in 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.
D.
T.S. Interpretation allows ECCS cross train alignment; Be in Mode 3 in 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.
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3.
(1. 00 pts. )
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Which one of the following describes an effect of a continued vacuum decrease?
A.
The Turbine will trip and Reactor power will be stabilized at ~ 10%.
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B.
Turbine steam demand will continue to increase until Overpower (109%) Reactor trip occurs.
C.
The Turbine will trip causing a direct reactor trip.
D.
Loss of steam dump capability will cause an OPDT Reactor trip.
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(1.00 pts.)
If vacuum continues to decrease to 15" hg, select the one answer that would describe primary heat removal at that time.
A.
Control rods drive to reduce reactor power, heat removal via condenser and atmosphere steam dumps.
B.
Reactor trips, heat removal via condenser and atmospheric steam dumps.
C.
Reactor trips, heat removal via atmosphere steam dumps.
Condenser dumps unavailable.
D.
Reactor trips, heat removal via S/G PORVs and S/G safeties.
No steam dumps available.
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5.
(1. 00 pts. )
Which of the following describes the nature of the Steam Generator Level Control failure?
A.
Median selected CF inlet header pressure has failed low.
B.
Average CF inlet header pressure has failed high.
C.
Average SM flow has failed low.
D.
Average SM pressure has failed high.
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(1.00 pts.)
Which of the following is true concerning PZR PORV operation for current conditions?
A.
PZR PORV NC34A will NOT open in ' AUTO'-
It is inoperable.
B.
PZR PORVs NC32B and NC36B will NOT open in ' AUTO'
and are inoperable.
C.
PZR PORVs NC32B and NO36B will open in ' AUTO', but will NOT reclose when Pzr pressure is less than 2185 psig.
D.
PZR PORVs NC32B and NC34A must have backup motive force (N2) ali~gned to operate in ' AUTO'.
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Which one of the following describes the effect on the plant, if
'A'
loop Tcold fails low?
A.
Tave will decrease causing automatic control rod withdrawal.
B.
'A'
loop Tave will decrease below P12 setpoint, blocking steam dump operation.
C.
'A' loop OTDT setpoint may be exceeded causing reactor trip.
D.
'A' loop OPDT setpoint may be reduced, resulting in reactor trip.
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8.
(1.00 pts.)
For present plant conditions, what should the CF/SM delta P be centrolled at?
A.
140 pcid B.
170 psid C.
180 psid D.
220 psid
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SOA934R THE FOLLOWING -QUESTIONS ARE NOT SCENARIO RELA TED
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(1.00 pts.)
Given the following:
- Containment pressure is 2.5 psig
- Containment H2 concentration is 5.5%
What is the required power setting for the
'A'
H2 recombiner? Assume recombiner plate temperature remain stable at 1300 deg. F for all power settings.
A.
52 Kw B.
56 Kw C.
60 Kw D.
62 Kw a
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(1. 00 pts. )
A Steam Generator Tube Rupture has occurred on Unit 1.
Ruptured S/G pressure has decreased to 700 psig.
Ruptured S/G ItaiCATED Narrow Fange level is 95%.
What is ACTUAL S/G Marrow Range level?
A.
100%
B.
95%
C.
89%
D.
74%
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11. (1.00 pts.)
Both U4' and
'B' H2 analyzers are OPERABLE.
Which of the following describes the alignment of the Hydrogen Analyzers following a LOCA7 A.
'A'
and
'B'
H2 analyzers sampling all areas with analyzer output to the Control Room.
B.
U4' H2 analyzer ON, sampling desired areas with analyzer output to control room.
'B' H2 analyzer OFF, sampling the operations level, and directing the H2 sample to the post accident sample panel.
C.
'A' H2 analyzer OFF, sampling desired areas, and directing the H2 sample to the post accident sample panel.
'B' H2 analyzer ON, sampling the operations level, with analyzer output to the control room.
D.
'A' H2 analyzer ON, sampling desired areas with analyzer output to the control room.
'B' H2 analyzer ON, sampling the operations level, with analyzer output to the post accident sample panel.
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s 12. (1.00 pts.)
Which one of the following describes why ND1B and ND37A have alternate power supplies provided?
A.
Allows putting ND in service in case one train of power is unavailable.
B.
Ensure capability to isolate ND during opetation from the SSF.
C.
Allows restoration of ND if NC pressure interlock fails.
D.
Backup power ensures ND can auto isolate during low temperature operation.
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13. (1.00 pts.)
Given the following:
- Safety Injection has occurred.
- 1CA-58A, 'CA Pump A Disch to S/G 1B Isol' has automatically closed.
Which of the following could have caused 1CA-58A to close?
A.
lA Motor driven CA pump has failed to start and the turbine driven CA pump is ON.
B.
1B Motor driven CA pump has failed to start and the turbine driven CA pump is ON.
C.
The turbine driven CA pump has failed to start.
D.
1B Motor driven CA pump discharge flow is greater that 780 gpm and the turbine driven CA pump is OFF.
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14. (1.00 pts.)
Which one of the following is isolated from PS (Nuclear Service Water) after a Phase
"B" (Sp) actuation?
A.
Positive Displacement pump coolers B.
VC chillers C.
KD Heat Exchangers D.
ND pump motor air cooler
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A plant heatup is in progress on Unit 1. The following conditions are noted:
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NC Tave = 275 degF
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NC pressure = 500 psig Why is this an unacceptable operating condition?
A.
Low temperature overpressure protection limits are being exceeded.
B.
Safety Injection on low steamline pressure has occurred.
C.
Heatup Limits are being exceeded.
D.
NC pump seal deltaP is inadequate.
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16.
(1. 00 pts. )
A large break LOCA has occurred on Unit 1.
Given the following:
- 1A RN pump ON
- IB RN pump TRIPPED
- 2A RN pump CN
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- 2B RN pump ON
- 1A NS pump ON
- 1B NC pump ON Determine the required RN to NS heat exchanger alignment, when NS is transferred to Cold Leg Recirculation.
(select one)
A.
Establish 4600 gpm each to 1A and 1B NS heat exchangers.
B.
Close 2RN-47A or 2RN-48B (RN Supply X-over Isols) and align 4600 gpm to only 1A NS heat exchanger.
C.
Establish 4600 gpm to only 1A NS heat exchanger.
D.
Close 2RN-47A or 2RN-48B (RN Supply X-over Isols) and
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align 4600 gpm each to 1A and 1B NS heat exchangers.
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/t'QL ScNku PROGRAM:
Operations Training MODULE:
License Requalification TOPIC:
Static Simulator Scenario #13 EXERCISE:
Decreasing Condenser Vacuum / Tech Spec Problems OVERVIEW:
This Exercise Guide will test the candidates ability to correctly diagnose transient / accident conditions, evaluate plant response and /or specify the correct course of action for Decreasing Condenser Vacuum, based on Control Room indications and appropriate Control Room reference materials.
PREREOUISITE KNOWLEDGE LEVEL:
E Previously licensed at the RO or SRO level.
02/04-01-93/CWNh Rev:
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OP-CN-EX-S-SSS13 Page 2 of 5 1.0 Synopsis The unit is at 100% power, steady atate, beginning of life.
The
'A'
Diesel Generator has had a loss of starting air, pressurizer pressure channel 2 fails low, and median CF header pressure input to DFCS has failed low.
A Loss of Condenser Vacuum occurs and the simulator is frozen just prior to the Low Vacuum Turbine Trip.
2.0 Initial conditions 2.1 Reset Simulator to IC-ll.
2.2 Plant Conditions Unit one Power Pistory 100%, BOL Boron 1246 ppm Tave 591*F
+67 pcm 2.3 Select:
ICCM-A = RVLIS ICCM-B = Core Cooling 2.4 Ensure Rod Step counters indicating properly.
2.5 Rotate chart recorders to clear paper.
3.0 reocedure 3.1 Turn Chart Recorder Power On 3.2 Run Simulator 3.3 set up Ohc as follows:
A.
Start Trend Recorders, if desired, using Trend Group 00 B.
Select Display Group 089 to display on Utility Video.
c.
Select Nuclear 06 to display on Monitor Video Rev:
02/04-01-93/CWN
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OP-CN-EX-S-SSS13 Page 3 of 5 D.
Acknowledge OAC Alarm Video 3.4 Select Turbine Graphic 1H 3.5 Acknowledge Control Room Annunciators 3.6 Freeze Simulator 3.7 Simulate failure of D/G starting air:
A.
OVR/ ANN /DGX7 (D/G
'A' Panel Trouble)
1.
Set value = 1 2.
Direct Activate 3.3 Fall Channel 2 PZR press low:
A.
OVR/XMT/NCX26 (PNC:5150 Pzr Press Mtr PI-456)
's 1.
Set new value = 1700 2.
Direct Activate 3.9 Insert the loss of vacuum malfunction:
A.
MALF/MTX3 (Loss of Condenser Vacuum)
1.
Set value = 100%
2.
Direct Activate 3.10 Insert Loss of Median CF Inlet Header Press A.
OVR/XMT/CFX21 (PCF:5140 S/G CF Inlet Hdr)
1.
Set value = 0 2.
Direct Activate B.
OVR/XMT/CFX22 (PCF:5141 S/G CF Inlet Hdr)
Rev 02/04-01-93/CWN
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Set value = 0 2.
Delay'= 2 sec.
3.
Direct Activate 3.11 Type in "RUN 110" 3.12 After simulator freezes turn of power to chart recorders.
4.0 Turnover Sheet (Attached)
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OP-CN-EX-S-SSS13 Page 5 of 5 ATTACHMENT 1 TURNOVER SHEET Conditions Existing at the time of the Incident:
A.
Plant Cotiditions
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Power History 100% BOL
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Boron 1246 ppm
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Tave 591*F
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Xenon 2846 pcm
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Samarium +67 pcm B.
Tech. Spec. Action Items:
D/G
- A'
has low VG pressure of 140 psig.
- C.
Work in Progress:
Investigating D/G
'A'
loss of starting air (press. currently 140 psi)
D.
Cntrent Procedures OP/1/A/6100/03 Enclosure 4.3 Manual Actions Taken During the Incident:
A.
operator Computer Alarms Acknowledged B.
Control Room Annunciators Acknowledged Simulator and chart recorders are " Frozen", the OAC is operational.
Revs 02/04-01-93/CWN J
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KEY EXAM: SOA934R 1.
(1.00 pts.)
[ DG1
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TIME:
2.5 Which one of the following describes the effect of the low VG pressure on 1A D/G?
A.
Will prevent an automatic start attempt on a blackout but will allow an automatic start attempt on a LOCA.
B.
Will allow an automatic start on either blackout or LOCA, but D/G will not attain speed necessary for start.
C.
Will prevent an automatic start on a LOCA, but will allow an automatic start on a blackout.
D.
Will prevent on automatic start on either blackout or LOCA, but will allow a manual start attempt to be made.
ANSWER: D s
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KEY EXAM: SOA934R j
2.
(1.00 pts.)
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TIME:
4.5
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If
'B' NI pump becomes inoperable, what would be the required Tech Spec. action?
i A.
Enter T.S.
3.0.3; Be in Mode 3 in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
!
B.
Apply T.S.
3.8.1.1 (A.C. Sources), action C.; Be in Mode 3 in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Apply T.S.
3.5.2 (ECCS Subsystems - Tave > 350 deg F),
(
action a.; Be in Mode 3 in 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.
D.
T.S.
Interpretation allows ECCS cross train alignment; Be in Mode 3 in 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.
ANSWER: B s
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YlY EXAM: SOA934R
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3.
(1.00 pts.)
[ EHC -
15]
TIME:
2.0 Which one of the following describes an effect of a continued vacuum decrease?
A.
The Turbine will trip and Reactor power will be stabilized at ~ 10%.
B.
Turbine steam demand will continue to increase until Overpower (109%) Reactor trip occurs.
C.
The Turbine will trip causing a direct reactor trip.
D.
Loss of steam dump capability will cause an OPDT Reactor trip.
ANSWER: C
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KEY EXAM: SOA934R 4.
(1.00 pts.)
[ IDE -
21]
TIME:
2.0 If vacuum continues to decrease to 15" hg, select the one answer that would describe primary heat removal at that time.
A.
Control rods drive to reduce reactor power, heat removal via condenser and atmosphere steam dumps.
B.
Reactor trips, heat removal via condenser and atmospheric steam dumps.
C.
Reactor trips, heat removal via atmosphere steam dumps.
Condenser dumps unavailable.
D.
Reactor trips, heat removal via S/G PORVs and S/G safeties.
No steam dumps available.
ANSWER: D s
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KEY EXAM: SOA934R 5.
(1.00 pts. )
[ IFE
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TIME:
3.0 Which of the following describes the nature of the Steam Generator Level Control failure?
A.
Median selected CF inlet header pressure has failed low.
B.
Average CF inlet header pressure has failed high.
C.
Average SM flow has failed low.
D.
Average SM pressure has failed high.
ANSWER: A
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KEY EXAM: SOA934R t
6.
(14 00 pts.)
( IPE -
16]
TIME:
2.0 Which of the following is true concerning PZR PORV operation for current conditions?
A.
PZR PORV NC34A will NOT open in ' AUTO':
It is inoperable.
B.
PZR PORVs NC32B and NC36B will NOT open in ' AUTO'
and are inoperable.
C.
PZR PORVs NC32B and NC36B will open.in ' AUTO', but will NOT reclose when Pzr pressure is less than 2185 Psi 9-
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D.
PZR PORVs NC32B and NC34A must have backup motive
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force (N2) aligned to operate in ' AUTO'.
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ANSWER: B
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KEY EXAM: SOA934R 7.
(1.00 pts. )
[ IPX -
16]
TIME:
3.0 Which one of the following describes the effect on the plant, if
'A'
loop Tcold fails low?
A.
Tave will decrease causing automatic control rod withdrawal.
B.
' )U loop Tave will decrease below P12 setpoint, blocking steam dump operation.
C.
'A' loop OTDT setpoint may be exceeded causing reactor trip.
D.
'A' loop OPDT setpoint may be reduced, resulting in reactor trip.
ANSWER: C
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THE FOLLOWING QUESTIONS I
ARE NOT SCENARIO
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KEY EXAM: SOA934R 8.
(1. 00 pts. )
[ IWE -
3]
TIME:
2.0 For present plant conditions, what should the CF/SM delta P be controlled at?
A.
140 psid
!
B.
170 paid C.
180 psid j
D.
220 paid ANSWER: C i
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KEY EXAM: SOA934R 3.
(1.00 pts.)
[ VX
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3]
TIME:
5.0 Given the following:
- Containment pressure is 2.5 psig
- Containment H2 concentration is 5.5%
What is the required power setting for the
'A' H2 recombiner? Assume recombiner plate temperature remain stable at 1300 deg. F for all power settings.
A.
52 Kw B.
56 Kw C.
60 Kw D.
62 Kw ANSWER: C
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KEY EXAM: SOA934R
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10. (1.00 pts.)
[ IFE -
23)
TIME:
4.0
A Steam Generator Tubte Rupture has occurred on Unit 1.
'
Ruptured S/G pressure has decreased to 700 psig.
Ruptured S/G INDICATED Narrow Range level is 95%.
..I What is ACTUAL S/G Narro.t Rm:ga level?
'l A.
100%
i
B.
95%
C.
89%
D.
74%
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ANSWER: C
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KEY EXAM: SOA934R 11. (1. 00 pts. )
[ VX
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TIME:
4.0 Both
'A'
and
'B'
H2 analyzers are OPERABLE.
Which of the following describes the alignment of the Hydrogen Analyzers following a LOCA?
.I A.
'A'
and
'B'
H2 analyzers sampling all areas with analyzer output to the Control Room.
I B.
'A' H2 analyzer ON, sampling desired areas'with analyzer output to control room.
.
I
'B' H2 analyzer OFF, sampling the operations level, and directing the H2 sample to the post accident sample panel.
_
C.
'A' H2 analyzer OFF, sampling desired areas, and directing
.
the H2 sample to the post accident sample panel.
'B' H2 analyzer ON, sampling the operations level, with analyzer output to the control room.
-
D.
'A' H2 analyzer ON, sampling desired areas with analyzer
_;
output to the control room.
'B' H2 analyzer ON, sampling the operations, level, with analyzer output to the post accident sample panel.
'
ANSWER: B
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KEY EXAM: SOA934R 12. (1.00 pts.)
{ ND
-
6]
TIME:
1.5
,
'
which one.of the following describes why ND1B and ND37A have alternate power supplies provided?
A.
Allows putting ND in service in case one train of
'
power is unavailable.
B.
Ensure capability to isolate ND during operation from
'
the SSF.
'
C.
Allows restoration of ND if NC pressure interlock fails.
,
D.
Backup power ensures ND can auto isolate during low temperature operation.
)
ANSWER: A
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KEY EXAM: SOA934R 13. (1.00 pts.)
[ CA
- 42]
TIME:
2.5 Given the following:
- Safety Injection has occurred.
- ICA-58A, 'CA Pump A Disch to S/G 1B Isol' has automatically closed.
Which of the following could have caused ICA-58A to close?
A.
lA Motor driven CA pump has failed to start and_the turbine driven CA pump is ON.
B.
1B Motor driven CA pump has failed to start and the
,
f turbine driven CA pump is ON.
C.
The turbine driven CA pump has failed to start.
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D.
1B Motor driven CA pump discharge flow is greater that 780 gpm and the turbine driven CA pump is OFF.
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ANSWER: B i
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.j KEY EXAM: SOA934R j
I l
14. (1.00 pts.)
[ RN
-
TIME:
1.5 Which one of the following is isolated from RN (Nuclear Service Water) after a i
Phase
"B" (Sp) actuation?
I I
I A.
Positive Displacement pump coolers B.
VC chillers
'i C.
KD Heat Exchangers D.
ND pump motor air cooler
ANSWER: A
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KEY EXAM: SOA934R 15. (1.00 pto.)
[ NC
-
13]
TINE:
2.0 A plant heatup is in progress on Unit 1. The following conditions are noted:
i
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NC Tave = 275 degF
-
NC pressure = 500 psig why is this an unacceptable operating condition?
i A.
Low temperature overpressure protection limits are being exceeded.
B.
Safety Injection on low steamline pressure has occurred.
C.
Heatup Limits are being exceeded.
I D.
NC pump seal deltaP is inadequate.
ANSWER: A I
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P3Y EXAM: SOA934R 16, (1.00 pts.)
[ RN
-
41]
TIME:
3.5 A large break LOCA has occurred on Unit 1.
Given the following:
- 1A RN pump PN
- 1B RN pump TRIPPED
- 2A RN pump ON
- 2B RN pump ON
- 1A NS pump ON
- IB NC pump ON vetermine the required RN to NS heat exchanger alignment, when NS is transferred to Cold Leg Recirculation.
(select one)
A.
Establish 4600 gpm each to 1A and 1B NS heat exchangers.
B.
Close 2RN-47A or 2RN-48B (RN Supply X-over Isols) and align 4600 gpm to only 1A NS heat exchanger.
C.
Establish 4600 gpm to only 1A NS heat exchanger.
D.
Close 2RN-47A or 2RN-48B (RN Supply X-over Isols) and
'
align 4600 gpm each to 1A and 1B NS heat exchangers.
ANSWER: C Page 16
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U.S. NUCLEAR REGULATORY COMMISSION
.
CATAWBA NUCLEAR STATION Oc/owha /04 ~ #< 4 / c.,
.
REQUALIFICATION EXAMINATION NAME CLASS PART B.
.
TEST #: SOB 934R DATE DATE 10/21/93 Page 1 of 22 S.S.#:
REFERENCE SET USED:
Originated: Md*4 ope: cations : W.l. b/o d,
[
-
A pproved
_
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,v Graced
SCORE
% OF CATEGORY TOTAL POINTS:
21.00 TOTAL QUESTIONS: 21.0
&
INSTRUCTIONS:
1.
Put your name on each answer sheet.
2.
Write your answers on the answer sheets.
3.
Ask the test monitor / instructor concerning questions which are not clear to you.
.
4.
Cheating or evidence of cheating
,
will not be tolerated.
My signature on this form is my declaration that the responses given on the attached test-or quiz are entirely my own.
It further, declares that I am aware that I am subject to termination from the training program immediately, and in addition, will be subject to further disciplinary action.up-to and including d'.scharge from the company for cheating and/or compromising on exams / tests.
Students signature
.
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1.
(1.00 pts.)
Given:
-
Unit 1 is at 100% power
l
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Main Turbine Combined Intermediate Valve #5 (ISV and RSV)
)
are stuck in the open position and cannot be closed.
Which of the following describes an action that would satisfy Tech. Spec.
requirements?
A.
Close all Main Turbine Stop Valves within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
B.
Be in Mode 3 in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with the turbine tripped.
C.
Close 1HM-1 'MSRH 1A&lB SSRH STM SOURCE' within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D.
Close all Main Turbini Control Valves within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.
.
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2.
(1. 00 pts. )
Given:
-
Unit 1 is at 100% RTP
-
Containment Pressure Transmitter 1NSPT5170 (CPCS)
has been found inoperable.
What action is required?
A.
Place the aff?cted channel in the tripped condition within i hour and 100% RTP operation may continue indefinitely.
B.
Place the affected channel in the bypassed condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> an1 be in hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
C.
Place the affected channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and, if not repaired in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, be in hot standby within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D.
Place the affected channel in the tripped condition
-
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and, if not repaired, be in hot standby within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
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3.
(1.00 pts.)
A fire in the cable spreading room has resulted in an Alert and Site Assembly.
As Shift Supervisor you are informed by the Security Lt. that two (2) operations
,
personnel are unaccounted for.
Select the one action to be taken to locate the two missing operators.
A.
Assistant Shift Su.pervisor from the OSC will begin a
,
search.
B.
Fire Brigade will be informed at the scene of the fire
,
and will dispatch additional team members to locate the missing operators.
.
C.
Emergency Coordinator, in the TSC, will organize search
efforts with operations personnel.
_,
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D.
Security will begin search operations along with other groups if necessary.
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4.
(1.00 pts.)
The following plant conditions exist:
- Operators report a sudden pressure drop on RN header 1A.
Actions for loss of RN are being carried out.
- The round NLO is dispatched to the RN pump house and reports that the door has been found open.
Unknown individuals appear to be wrecking wiring and equipment.
Based on the situation in the RN pump house, choose a course of action.
A.
Declare an Unusual Event and contact Station Security.
B.
Declare an Alert and contact Station Security.
C.
Contact Station Security and begin an immediate shutdown of both units under a Site Area Emergency declaration.
D.
Contact county sheriff for assistance and declare an Unusual Event.
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5.
(1.00 pts.)
Unit 1 has completed a shutdown from 100% RTP due to an RN Tech. Spec. action.
The power history at the end of each hour is:
first - 90%
fifth - 21%
second - 77%
sixth - 4%
third - 58%
seventh - Rx shutdown fourth - 45%
Which of the following describes the required notification?
A.
Notify Chemistry to start sampling for Iodine by the end of the fifth hour.
B.
The Reactor Engineer must be notified of exceeding fuel maneuvering limits.
C.
The NRC must be notified of the shutdown by the end of the first hour.
D.
Notify RP to sample the Unit Vent for Gaseous effluents two to six hours after the end of the
'
seventh hour.
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6.
(1.00 pts.)
Given:
Unit 1 has tripped and Safety Injected due to a LOCA.
Both trains of ECCS have failed.
Containment EMFs 53A and 53B indicate 1000 R/hr.
Containment Isolation is incomplete.
The Technical Support Center (TSC) has NOT been staffed.
With regard to Protective Action Recommendations (PARS), which of the following actions should the Shif t Supervisor / Emergency Coordinator perform?
A.
Immediately recommend evacuation of zone A-0 and wait for the TSC to make further PARS.
B.
Immediately recommend evacuation of the 2 mile radius and 5 miles downwind and shelter for unevacuated areas.
C.
Make PARS after the TSC has been staffed and field
'
monitoring teams results have been received.
D.
Do NOT make PARS until the Shift Supervisor turns over Emergency Coordinator duties to the Station Manager.
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7.
(1.00 pts.)
Given initial plant conditions:
-
Unit 1 is in Mode 5
-
NC level has been reduced to 9.5% to allow NCP seal repair A subsequent loss of all ND cooling has resulted in operator actions to establish NV makeup. Present conditions are:
-
Core Exit Thermocouples are stable at 207 degF.
-
NC level is stable at 11%.
What is the required emergency classification?
A.
Notification of Unusual Event B.
Alert C.
Site Area Emergency D.
General Emergency
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B.
(1.00 pts.)
Which one or t.he following parameters, when maintained within its required limits assures that the FQ(z) limit will not be exceeded?
A.
Axial Flux Difference B.
Quadrant Power Tilt Patio C.
Thermal Power Mismatch D.
NC Tave and Pressure
.
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9.
(1. 00 pts. )
Unit 1 has experienced a Reactor trip. Given the following plant conditions:
- Unit tie PCBs 14, 15, 17, 18 are OPEN
- D/G 1A is running with 0 volts
-
1ETB undervoltage status lights are lit
-
SSF D/G will not start
-
Core life is 250 EFPD Which of the following actions is required?
A.
Cooldown the NC system to 280 deg.F B.
Depressurize the NC system to 150 poig C.
Cooldown the NC system to 350 deg.F D.
Depressurize All Steam Generators to 50 psig.
.
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10.
(1.00 pts.)
The following plant conditions exist:
-
Plant is 30 minutes into a LOSS OF ALL AC j
- Maintenance attempting to restore one D/G.
]
- OATC reports
"A" S/G Level increasing to 70%
!
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BOP notes PZR level offscale LOW.
)
l Select the one correct method to conduct a cooldown of the NC system.
i
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A.
Dump steam w the condenser using intact S/G's.
l I
B.
Locally operate PORV's using all S/G's.
,
Dump steam to the condenser using all S/G's.
C.
l D.
Manually operate intact S/G PORV's.
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11. (1.00 pts.)
Given the following conditions 1)
A valid reactor trip signal occurs 2)
Reactor trip breakers cannot be opened from inside the control roan 3)
Total CA flow is O gpm 4)
All S/G N/R levels are offscale low Which of the following describes a correct procedure flowpath?
A.
EP/01 ' Reactor Trip or Safety Injection' then Go To EP/2A1 ' Nuclear Power Generation /ATWS' then Go To EP/2C1 ' Loss of Secondary Heat Sink'.
B.
EP/2A1 ' Nuclear Power Generation /ATWS' then Go To EP/01 ' Reactor Trip or Safety Injection' then Go To EP/2C1 ' Loss of Secondary Heat Sink'.
C.
EP/01 ' Reactor Trip or Safety Injection' then Go To EP/2C1 ' Loss of Secondary Heat Sink' then Go To EP/2A1 ' Nuclear Power Generation /ATWS',
&
D.
EP/01 ' Reactor Trip or Safety Injection' then Go To EP/2A1 ' Nuclear Power Generation /ATWS' then Go To EP/01 ' Reactor Trip or Safety Injection' then Go To EP/2C1 ' Loss of Secondary Heat Sink'.
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'2.
(1.00 pts. )
A Unit 1 Safety Injection has occurred.
Given the following conditions:
- NC pressure 1115 psig increasing S/G A,B&D N/R level 8%
- NC subcooling 33 deg F
- Pzr level 16%
S/G C N/R level Ot
- Containment pressure 0.29 psig
- S/G A,B&D Press 940 psig EMF 11 Incore Inst Rm Trip 2
- ETB UV status lights LIT
- S/G C Pressure O psig Lowest NC Tcold has remained greater that 421 deg. F Which of the following describes the appropriate procedure flowpath for this event? Select one.
l A.
EP/01 Reactor Trip or Safety Injection
'
EP/1D Steam Line break Outside Containment EP/1C High Energy Line Break Inside Containment EP/1C1 S/I Termination following High Energy Line Break Inside Containment
.
B.
EP/03 Loss of All AC EP/3B Loss of All AC Recovery with S/I required EP/1D Steam Line Break Outside Containment C.
EP/01 Reactor Trip or Safety Injection EP/1C High Energy Line Break Inside Containment EP/1C2 Post LOCA Cooldown and Depressurization EP/1D1 S/I Termination Following Steam Line Break D.
EP/01 Reactor Trip or Safety Injection EP/1D Steam Line Break Outside Containment EP/1D1 S/I Termination Following Steam Line Break l
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13. (1.00 pts.)
In reference to shutdown operations, THERMAL MARGIN is defined as:
A.
Time to core damage on loss of ND.
B.
Time to core uncovery on loss of ND.
C.
Time to establish containment closure on loss of ND.
D.
Time to core boiling on loss of 10.
.
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14.
(1.00 pts.)
The following plant conditions exist:
- Unit has Safety Injected on High Containment pressure of 1.5 psig.
- Total ND flow to Cold Legs is 4000 gpm.
-
Radiation Protection and Secondary Chemistry confirmed a tube rupture on
"B" S/G based on earlier ENT alarms.
Select the one action to address current plant conditions:
A.
GO TO EP-1E 'SGTR' and isolate
"B" S/G.
B.
REFER TO EP-1E 'SGTR' to isolate
"B" S/G.
C.
GO TO EP1D ' Steam Line Break Outside Containment'
and isolate main steam.
D.
GO TO EP1E 'SGTR' and dump steam to equalize NCS and ruptured S/G pressures.
.
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15. (1.00 pts.)
During a S/G tube rupture event on
"A" S/G, EP1E is designed to cooldown and depressurize the NC system to stop break flow.
You would NOT continue in the procedure IF:
A.
the ruptured S/G is determined to be faulted also.
B.
all NCP's are off and subcooling is greater than 0 degF.
C.
the ruptured S/G PORV cannot be closed.
D.
core exit temperatures for initial NCS cooldown are greater than required.
.
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16. (1.00 pts.)
The following plant conditions exist:
-
'B'
S/G is ruptured
- NC system pressure is 1900 psig and
'B'
S/G pressure is 950 psig Reactor coolant system temperature must be reduce to less than prior to initiating depressurization.
A.
496 deg. F core exit T/C indication B.
496 deg. F highest Thot indication C.
510 deg. F core exit T/C indication D.
510 deg. F highest Thot indication
.
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17.
(1.00 pts.)
Which one of the following is the basis for tripping the turbine in EP/1/A/5000/2A1, " Nuclear Power Generation /ATWS"?
A.
To prevent actuation of SM isolation and subsequent loss of steam dump capability.
B.
To allow NC pressure to be controlled by the pressurizer PORVs.
C.
To generate an additional reactor trip signal.
D.
To preserve steam generator inventory and preclude addition of positive reactivity due to cooldown.
.
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18. (1.00 pts. )
Given the following plant conditions, which critical safety function should be given highest priority:
Cont. Press
= 4.5 psig PZR Press
= 2280 psig PZR level
= 54%
S/G levels C=
0% NR All others = 38% NR NC Cold leg Temp (lowest) = 440 deg. F Core Exit T/C's
= 445 deg. F S/G Pressures:
C=
50 psig All others = 900 psig S/R SUR = -0.33 dpm Time since Rx Trip = 50 minutes RVLIS = 100% UR level A.
Heat Sink B.
Containment Integrity C.
Reactor Coolant Integrity
.
D.
Reactor Coolant Inventory Page 19
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19. (1.00 pts.)
In EP/2F3 (Void in the Reactor Vessel), a calculation is performed to determine the maximum time the vessel head may be vented to containment.
Why is this
'
calculation necessary? (Select one)
,
A.
To ensure NC system pressure does not fall below minimum required pressure for head venting.
B.
To ensure maximum gas volume in containment does not exceed the 1.2 X 10 (6) cubic feet design value.
C.
To ensure H2 vented from the vessel does not cause containment H2 concentration to exceed 3%.
D.
To ensure the maximum volume of H2 vented does not exceed the 9500 cubic feet design value.
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t 20. (1.00 pts.)
A LOCA has occurred and the control room operators enter EP/2El,."High Containment Pressure", prior to entering EP/1C, "High Energy Line Break Inside Containment", due to containment pressure of 7.5 psig. While the operator is performing step 8 of EP/2El, an unexpected RED path is determined to be present
'
on the Heat Sink status Tree due to CA flow being 410 gpm with all S/G levels at
!
5% (using qualified instruments).
.
From the choices below, select the proper course of action for the operator to take.
A.
The operator should complete EP/2E1 and then enter
'
EP/2C1.
B.
The operator should suspend performance of EP/2E1
,
and enter EP/2C1.
C.
The operator should perform EP/2E1 and EP/2C1
'
concurrently.
D.
The operator should complete EP/2E1 and then enter EP/1C.
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21.
(1.00 pts.)
At 1115 a Unit 1 Safety Injecticn has occurred.
Given the following plant conditions at 1145:
- Reactor trips breakers A and B OPEN
- Lowest NC Tcold 381 deg.F
- Reactor power 10-8 amps IR
- Startup rate
+0.2 dpm
- Core Exit T/C's 411 deg.F and stable
- NC pressure 2270 psig
- Containment pressure 3.8 psig
- Boration from BAT or FWST cannot be established
- Pzr level 64% increasing
- S/G A, C, and D N/R level 38%
- S,G B N/R level 0%
l Concerning Critical Safety Functions, which one of the following describes the ap3ropriate action to be taken?
A.
Ensure CA flow to B S/G maintained greater than 25 gpm.
B.
Allow NC temperature to increase until IR startup rate
'
negative.
C.
Establish normal letdown and depressurize NC using enarging and letdown.
D.
Align one train of ND for Aux. Containment Spray.
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KEY EXAM: SOB 934R 1.
(1.00 pts.)
[ TS
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22]
TIME:
4.5 Given:
-
Unit 1 is at 100% power
-
Main Turbine Combined Intermediate Valve #5 (ISV and RSV)
are stud. in the open position and cannot be closed.
Which of the following describes an action that would satisfy Tech. Spec.
requirements?
A.
Close all Main Turbine Stop Valves within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
B.
Be in Mode'3 in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with the turbine tripped.
C.
Close 1HM-1 'MSRH 1A&lB SSRH STM SOURCE' within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D.
Close all Main Turbine Control Valves within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.
a ANSWER: A Page
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KEY EXAM: SOB 934R 2.
(1.00 pts.)
[ VX
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2)
TIME:
5.0 Given:
-
Unit 1 is at 100% RTP
-
Containment Pressure Transmitter INSPT5170 (CPCS)
has been found inoperable.
What action is required?
A.
Place the affected channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 100% RTP operation may continue indefinitely.
B.
Place the affected channel in the bypassed condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
C.
Place the affected channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and, if not repaired in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, be in hot standby within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D.
Place the affected channel in the tripped condition
'
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and, if not repaired, be in hot standby within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
ANSWER: C i
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e KEY EXAM: SOB 934R 3.
(l.C^ pts.)
[ SEP -
15]
TIME:
6.5 i
A fire in the cable spreading room has resulted in an Alert and Site Assembly.
As Shift Supervisor you are informed by the Security Lt. that two (2) operations personnel are unaccounted for.
Select the one action to be taken to locate the two missing operators.
A.
Assistant Shift Supervisor from the OSC will begin a search.
B.
Fire Brigade will be informed at the scene of the fire and will dispatch additional team members to locate the missing operators.
C.
Emergency Coordinator, in the TSC, will organize search efforts with operations personnel.
D.
Security will begin search operations along with other groups if necessary.
ANSWER: D
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KEY EXAM: SOB 934R 4.
(1.00 pts.)
{ SEP -
1}
TIME:
8.5 The following plant conditions exist:
-
Operators report a sudden pressure drop on RN header 1A.
Actions for loss of RN are being carried out.
- The round NLO is dispatched to the RN pump house and reports that the door has been found open.
Unknown individuals appear to be wrecking wiring and equipment.
Based on the situation in the RN pump house, choose a cource of action.
A.
Declare an Unusual Event and contact Station Security.
B.
Declare an Alert and contact Station Security.
C.
Contact Station Security and begin an immediate shutdown of both units under a Site Area Emergency declaration.
C.
Contact county sheriff for assistance and declare an Unusual Event.
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ANSWER: B Page
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KEY EXAM: SOB 934R
,
5.
(1.00 pts.)
[ CP
-
19]
TIME:
8.0 Unit I has completed a shutdown from 100% RTP due to an RN Tech.. Spec. action.
The power history at the end of each hour is:
first - 90%
fifth - 21%
second - 77%
sixth -
4%
third - 58%
seventh - Rx shutdown fourth - 45%
Which of the following describes the required notification?
A.
Notify Chemistry to start sampling for Iodine by the end of the fifth hour.
B.
The Reactor Engineer must be notified of exceeding fuel maneuvering limits.
C.
The NRC must be notified of the shutdown by the end of the first hour.
D.
Notify RP to sample the Unit Vent for Gaseous effluents two to six hours after the end of the
seventh hour.
ANSWER: C
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KEY EXAld: SOB 934R 6.
(1. 00 pts. )
{ SEP - 104}
TIME:
5.0 Given:
Unit I has tripped and Safety Injected due to a LOCA.
Both trains of ECCS have failed.
Containment EMFs 53A and 53B indicate 1000 R/hr.
Containment Isolation is incomplete.
The Technical Support Center (TSC) has NOT been staffed.
With regard to Protective Action Recommendations (PARS), which of the following actions should the Shift Supervisor / Emergency Coordinator perform?
A.
Imp "11 ate v recommend evacuation of zone A-0 and wai
.vr the TSC to make further PARS.
B.
Immediately recommend evacuation of the 2 mile radius and 5 miles downwind and shelter for unevacuated areas.
'
C.
Make PARS after the TSC has been staffed and field monitoring teams results have been received.
D.
Do NOT make PARS until the Shif t Supervisor turns over Emergency Coordinator duties to the Station Manager.
ANSWER: B l
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KEY EXAM: SOB 934R
(1.00 pts.)
[ SEP - 105)
TIME:
3.0 Given initial plant conditions-
-
Unit 1 is in Mode 5
-
NC level has been reduced to 9.5% to allow NCP seal repair A subsequent loss of all ND cooling has resulted in operator actions to establish NV makeup. Present conditions are:
-
Core Exit Thermocouples are stable at 207 degF.
-
NC level is stable at 11%.
What is the required emergency classification?
A.
Notification of Unusual Event s
B.
Alert C.
Site Area Emergency D.
General Emergency
.
ANSWER: B Page
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KEY EXAM: SOB 934R 8.
(1.00 pts.)
[ CP
-
2}
TIME:
3.0 Which one of the following parameters, when maintained within its required FQ(z) limit will not be exceeded?
limits assureb that
A.
Axial Flux Difference B.
Quadrant Power Tilt Ratio C
Thermal Power Mismatch
!
D.
NC Tave and dressure ANSWER: A
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KEf EXAM: SCB934R 9.
(1.00 pts.)
[ EP5
-
2]
TIMI:
5.5 Unit 1 has experienced a Reactor trip.
Given the following plant conditions:
- Unit tie PCBs 14, 15, 17, 18 are OPEN
- D/G 1A is rut,1ing with 0 volts
-
1ETB undervoltage status lights are lit
-
SSF D/G will not start
- Core life is 250 EFPD Which of the following actions is required?
A.
Cooldown the NC system to 280 deg.F B.
Depressurize the NC system to 150 psig C.
Cooldown the NC system to 350 deg.F D.
Depressurize All Steam Generators to 50 psig.
ANSWER: C a
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KEY EXAM: SOB 934R 10. (1.00 pts.)
[ EP5
-
6)
TIME:
3.5 The following plant conditions exist:
-
Plant is 30 minutes into a LOSS OF ALL AC
-
Maintenance attempting to restore one D/G.
-
OATC reports
"A" S/G Level increasing to 70%
- BOP notes PZR level offscale LOW.
Select the one correct method to conduct a cooldown of the NC system.
A.
Dump steam to the condenser using intact S/G's.
B.
Locally operate PORV's using all S/G's.
C.
Dump steam to the condenser using all S/G's.
D.
Manually operate intact S/G PORV's.
ANSWER: D e
Page 10
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KEY EXAM: SOB 934R 11.
(1.00 pts.)
[ EP1 12]
TIME:
3.0 Given the following conditi..ns 1)
A vaiid reactor trip signal occurs 2)
Reactor trip breakers cannot be opened from inside the control room 3)
Total CA flow is 0 gpm 4)
All S/G N/R levels are offscale low Which of the following describes a correct procedure flowpath?
A.
EP/01 ' Reactor Trip or Safety Injection' then Go To EP/2A1 ' Nuclear Power Generation /ATWS' then Go To EP/2C1 ' Loss of Secondary Heat Sink'.
B.
EP/2A1 ' Nuclear Power Generation /ATWS' then Go To EP/01 ' Reactor Trip or Safety Injection' then Go To EP/2C1 ' Loss of Secondary Heat Sink'.
C.
EP/01 ' Reactor Trip or Safety Injection' then Go To EP/2C1 ' Loss of Secondary Heat Sink' then Go To EP/2A1 ' Nuclear Power Generation /ATWS',
.
D.
EP/01 ' Reactor Trip or Safety Injection' then Go To EP/2A1 ' Nuclear Power Generation /ATWS' then Go To EP/01 ' Reactor Trip or Safety Injection' then Go To EP/2C1 ' Loss of Secondary Heat Sink'.
ANSWER: A 4'
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KEY EXAM: SOB 934R 12. (1.00 pts.)
[ EP3
-
1]
TIME:
4.5 A Unit 1 Safety Injection has occurred.
Given the following conditions:
- NC pressure 1115 psig increasing S/G A,B&D N/R level 8%
- NC subcooling 33 deg.F
- Pzr level 16%
S/G C N/R level 0%
- Containment pressure 0.29 psig
- S/G A,B&D Press 940 psig EMF 11 Incore Inst Rm Trip 2
- ETB UV status lights LIT
- S/G C Pressure O psig Lowest NC Tcold has remained greater that 421 deg. F Which of the following describes the appropriate procedure flowpath for this event? Select one.
A.
EP/01 Reactor Trip or Safety Injection EP/1D Steam Line break Outside Containment EP/1C High Energy Line Break Inside Containment EP/1C1 S/I Termination following High Energy Line Break Inside Containment
.
B.
EP/03 Loss of All AC EP/3B Loss of All AC Recovery with S/I required EP/1D Steam Line Break Outside Containment C.
EP/01 Reactor Trip or Safety Injection EP/1C High Energy Line Break Inside Containment EP/1C2 Post LOCA Cooldown and Depressurization EP/1D1 S/I Termination Following Steam Line Break D.
EP/01 Reactor Trip or Safety Injection EP/1D Steam Line Break Outside Containment EP/1D1 S/I Termination Following Steam Line Break ANSWER: A Page 12
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KEY EXAM: SOB 934R 13. (1.00 pts.)
[ SO
-
2]
TIME:
2.0 In reference to shutdown operations, THERMAL MARGIN is defined as:
A.
Time to core damage on loss of ND.
B.
Time to core uncovery on loss of ND.
C.
Time to establish containment closure on loss of ND.
D.
Time to core boiling on loss of'1H).
ANSWER: D
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KEY EXAM: SOB 934R i
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14. (1.00 pts.)
[ EP2
--
5)
TIME:
4.0 The following plant conditions exist:
,
'!
- Unit has Safety Injected on High Containment pressure of
.l 1.5 psig.
- Total ND flow to Cold Legs is 4000 gpm.
Radiation Protection and Secondary Chemistry confirmed
-
a tube rupture on
"B" S/G based on earlier EMF alarms.
!
Select the one action to address current plant conditions:
l l.
A.
GO TO EP-1E 'SGTR' and isolate
"B" S/G.
,
B.
REFER TO EP-1E 'CSTR' to isolate
"B" S/G.
I C.
GO TO EP1D ' Steam Line Break Outside Containment'
i and isolate main steam.
!
D.
GO TO EP1E 'SGTR' and dump steam to equalize
NCS and ruptured S/G pressures.
d.
- i
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-
b ANSWER: B
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KEY EXAM: SOB 934R 15. (1.00 pts.)
[ EP4
-
3]
TIME:
4.5 During a S/G tube rupture event on
"A" S/G, EP1E is designed to cooldown and depressurize the NC system to stop break flow.
You would NOT continue in the procedure IF:
A.
the ruptured S/G is determined to be faulted also.
B.
all NCP's are off and subcooling is greater than 0 degF.
the ruptured S/G PORV cannot be closed.
- D.
core exit temperatures for initial NCS cooldown are greater than required.
ANSWER: D
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KEY EXAM: SCB934R 16. (1.00 pts.)
[ EP4
-
4]
TIME:
2.0 The following plant conditions exist:
-
'B'
S/G is ruptured
-
NC system pressure is 1900 psig and
'B'
S/G pressure is 950 psig Reactor coolant system temperature must be reduce to less than prior to initiating depressurization.
A.
496 deg. F core exit T/C indication B.
496 deg. F highest Thot indication C.
510 deg. F core exit T/C indication D.
510 deg. F highest Thot indication ANSWER: A
Page 16
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KEY EXAM: SOB 934R 17.
(1. 00 pts. )
[ CSF -
35]
TIME:
1.5 Which one of the following is the basis for tripping the turbine in EP/1/A/5000/2A1, " Nuclear Power Generation /ATWS"?
A.
To prevent actuation of SM isolation and subsequent loss of steam dump capability.
B.
To allow NC pressure to be controlled by the pressurizer PORVs.
C.
To generate an additional reactor trip signal.
D.
To preserve steam generator inventory and preclude addition of positive reactivity due to cooldown.
ANSWER: D
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KEY EXAM: SOB 934R 18. (1.00 pts.)
{ CSF -
4]
TIME:
3.0 Given the following plant conditions, which critical safety function should be given highest priority:
Cont. Press
= 4.5 psig PZR Press
= 2280 psig PZR level
= 54%
S/G levels C=
0% NR All others = 38% NR NC Cold leg Temp (lowest) = 440 deg. F Core Exit T/C's
= 445 deg. F S/G Pressures:
C=
50 psig All others = 900 psig S/R SUR = -0.33 dpm Time since Rx Trip = 50 minutes RVLIS = 100% UR level A.
Heat Sink B.
Containment Integrity C.
Reactor Coolant Integrity
D.
Reactor Coolant Inventory ANSWER: C Page 18
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f KEY EXAM: SOB 934R 19.
(1.00 pts.)
[ CSF -
6]
TIME:
3.5 In EP/2F3 (Void in the Reactor Vessel), a calculation is performed to determine the maximum time the vessel head may be vented to containment.
Why is this calculation necessary? (Select one)
A.
To ensure NC system pressure does not fall below minimum required pressure for head venting.
B.
To ensure maximum gas volume in containment does not exceed the 1.2 X 10 (6) cubic feet design value.
C.
To ensure H2 vented from the vessel does not cause containment H2 concentration to exceed 3%.
D.
To ensure the maximum volume of H2 vented does not exceed the 9500 cubic feet design value.
ANSWER: C
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)
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KEY EXAM: SOB 934R 20. (1 00 pts.)
[ CSF -
20]
TIME:
3.0 A LOCA has occurred and the control room operators enter EP/2El, "High Containment Pressure", prior to entering EP/1C, "High Energy Line Break Inside Containment", due to containment pressure of 7.5 psig.
While the operator is performing step 8 of EP/2El, an unexpected RED path is determined to be present on the Heat Sink status Tree due to CA flow being 410 gpm with all S/G levels at 5% (using qualified instruments)
From the choices below, select the proper course of action for the operator to take.
A.
1he operator should complete EP/2E1 and then enter EP/2C1.
B.
The operator should suspend performance of EP/2E1 and enter EP/2C1.
C.
The operator should perform EP/2E1 and EP/2C1 concurrently.
D.
The operator should complete EP/2E1 and then enter EP/1C.
.
ANSWER: B Page 20
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YsEY EXR4: SOB 934R 21. (1.00 pts.)
[ CSF -
40]
TIME:
5.0 At 1115 a Unit 1 Safety Injection has occurred.
Given the following plant conditions at 1145:
- Reactor trips breakers A and B OPEN
- Lowest NC Teold 381 deg.F
- Reactor power 10-8 amps IR
- Startup rate
+0.2 dpm
- Core Exit T/C's 411 deg.F and stable
- NC pressure 2270 psig
- Containment pressure 3.8 psig
- Boration from BAT or FWST cannot be established
- Pzr level 64% increasing
- S/G A, C, and D N/R level 38%
- S/G B N/R level 0%
Concerning Critical Safety Functions, which one of the following describes the appropriate action to be taken?
A.
Ensure CA flow to B S/G maintained greater than 25 gpm.
B.
Allow NC temperature to increase until IR startup rate
'
negative.
C.
Establish normal letdown and depressurize NC using charging and letdown.
D.
Align one train of ND for Aux. Containment Spray.
ANSWER: B Page 21