ML032100224
| ML032100224 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/16/2003 |
| From: | Operator Licensing and Human Performance Branch |
| To: | Duke Energy Corp |
| References | |
| 50-369/03-301, 50-370/03-301, FOIA/PA-2004-0122 | |
| Download: ML032100224 (28) | |
See also: IR 05000369/2003301
Text
Final Submittal
(Blue Paper)
1. Senior Operator Written Examination
MCGUIRE JUNE 2003 EXAM
50-36912003-301 AND
50-370/2003-301
-
JUNE 16 30,2003
ES-401 Site-Specific SRO Written Examination Form ES-401-8
Cover Sheet
Date: June 30,2003 FaciIitylUnit: McGuire
Region: II Reactor Type: Westinghouse
Start Time: Finish Time:
Applicant Certification
All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature
Results
RO I SRO-Only I Total Examination Values -I-/- Points
~
Applicant's Scores -1-1- Points
Applicant's Grade -I-/- Percen
320f 34 NUREG-1021, Draft Revision 9
1 Pt. Given the following conditions:
Unit 1 is in a refueling outage.
Fuel movement is in progress.
The Spent Fuel Pool Level Low computer alarm has actuated.
Initially IEMF 17 (SPENT FUEL BLDG. REFUEL. BRDG) was
reading radiation 7 mredhr.
After 20 minutes IEMF-17 is 18 mredhr.
Which one (1) of the following describes the operator response to the
current conditions?
k Begin makeup io the pool from the Boric Acid Tank to restore
level.
B. Move the fuel transfer cart to the reactor side and close IKF-
122 (Fuel Transfer Tube Block Valve).
C. Move the fuel transfer cart to the spent fuel (pit) side and close
IKF-122 (Fuel Transfer Tube Block Valve).
D. Place the weir gate in position and inflate the seals.
33.1 doc
1 Pt. Unit 1 is in mode 4.
Given the following conditions:
(1) Surveillance testing has been recently completed on the ice condenser
(2) The surveillance test was not satisfactory as described below
Which one (1) of the following situations meets the requirements for a one hour
Tech Spec LCO?
A. The ice condenser door position monitoring system was declared
inoperable when one door did not indicate in the open position during
a surveillance test. T i e tinor was left in the open position.
B. The ice bed was declared inoperable when it was determined that it
failed a surveillance test based on total ice weight less than 2,099,790
pounds at a 95% level of confidence.
C. The Ice Bed Temperature Monitoring System was declared inoperable
when it failed a Tech Spec surveillance test -channel check failure.
D. The ice condenser intermediate deck door was declared inoperable
when it was discovered to be obstructed from opening by ice and
debris.
40.1 doc
1 Pt. Unit 1 is preparing for a reactor start up following a refueling outage. Given
the following conditions:
Tavg=515°F
Plant heatup in progress using NCPs
At 0200, a Station Engineer reports that a mistake had been made in
analyzing the containment Appendix J Leak Rate Test results that were
conducted prior to exceeding 200 "F in mode 5. Reanalysis indicated that
the combined containment leak rate (Type A) had exceeded 1.O La.
Which one of the following actions are required by Tech Specs in response
to this situation?
REFERENCES PROVIDED
A. Commence a plant cooldown to reach mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
B. Commence a plant cooldown to reach mode 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
C. Commence a plant cooldown to reach mode 5 within 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />.
D. Commence a plant cooldown to reach mode 5 within 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />.
Ques-207.l.doc
4
1 Pt Which one of the following statements complies with the requirements of
OMP 4-3 (/YAP lmplemenfafion Guidelines) regarding the rules of usage
for abnormal procedures (APs) when the emergency procedures (EPs)
have been implemented?
A. APs may not be implemented when EPs have been entered.
B. Only one AP at a time may be implemented when EPs have
been implemented. Concurrent implementation of APs when
EPs are in use is not allowed.
C. APs may be implemented concurrently with EPs. However, the
APs were written assuming that SI has not actuated and
operators must be careful when using APs if SI has occurred.
D. APs may be implemented concurrently with EPs with the
exception of events where SI has actuated. APs were written
assuming the SI had not occurred and cannot be used if SI has
actuated.
Ques-338.1 .doc
1 Pt. Unit 2 is operating at 100% power. 21\11-59 (ColdLeg Accumulator Check
Valve) begins to leak at 0200. Given the following accumulator indications:
Time
Level (%)
-
0200
21%
-
0300
31%
-
0400
41%
-0500
51%
Pressire' (psig) 586 611 636 661
Boron (ppm) 2500 2490 2480 2470
When does the accumulator first exceed a limiting condition for operation?
REFERENCES PROVIDED:
A. 0200
1 Pt. Unit 1 was operating at 100% when a large break LOCA with loss of offsite
power occurs. One diesel generator fails to start. The operators are
entering E-I (Loss of Reactor or Secondaty Coolant).
Given the following critical safety function status indications:
Core Cooling - RED
Subcriticality - GREEN
Containment - RED
Inventory - GREEN
Heat Sink - RED
Integrity - RED
Which one of the following describes the highest priority problem, and the
appropriate operator action?
A, Integrity; Transition to FR-P.l, (Response to Imminent
PressurizedThermal Shock).
B. Core cooling; Transition to FR-C.l, (Response to Inadequate
Core Cooling).
C. Heat Sink; Transition to FR-H.l, (Response to Loss of
Secondary Heat Sink).
D. Containment; Transition to FR-Z.l, (Response to High
Containment Pressure).
_______.____________.-----..----
Ques-776.l.dr.x
7
1 Pt. Unit 1 is operating at 100% power when the OAC registers a low spent fuel
pool level alarm. Given the following events and conditions:
The operators read -2.1 ft SFP level and stable on the main control
board.
The operating KF pump has tripped.
An NLO reports a large leak in the auxiliary building has stopped.
Normal SFP makeup is not available.
Which one of the following statements correctly describes the corrective
action for this event?
k Implement AP~Z/A/5500/41(Lossof Spent Fuel Cooling 0.r
Level), find and isolate the leak on the KF discharge piping.
B. Implement AP/l/A/5500/41 (Loss of Spent Fuel Cooling or
Level), find and isolate the leak on the KF suction piping.
C. Implement AP/I/N5500/21 (Loss of KC or KC System Leakage),
and initiate assured makeup due a leak on the discharge
piping.
D. Implement AP/l/A/5500/21 (Loss of KC or KC System Leakage),
and initiate assured makeup due to a leak on the suction
piping.
_________.________________
Ques892.3.doc
0
0
1 Pt. Unit 2 is operating at 100 % power. Given the following events and
conditions:
" B essential train components are in service.
The Test Group Supervisor comes to you the Control Room SRO and
wants to perform valve stoke testing.
Which one of the following valves would you NOTallow testing?
A. ORN-1 (LLI SUpply to RN)
B. 2RN40A (Train A to Non- Ess Hdr /so!)
C. ORN-7A (Train 1A & 2 A SNSWP Supply)
D. 2RN-64A (A8 Non-Ess Return /sol)
1 Pt. Which one of the following is a correct list of SAFETY LIMITS?
A. Thermal Power, RCS Highest Loop Tave and Pressurizer
Pressure.
B. Thermal Power, AFD, Pressurizer Pressure.
C. AFD, QPTR and Reactor Power.
D. Linear Heat Generation Rate, Thermal Power and QPTR.
Ques-991.l.dcc
1 Pt. Unit 1 has experienced a 50% load rejection which resulted in Control Bank
" D Group 1 being greater than 12 steps misaligned from its associated
step counter. Tech Spec 3.1.4 Rod Control Group Alignment Limits states:
' N l shutdown and control rods shall be OPERABLE; with all individual
indicated rod positions within12 steps of their group step counter demand
position:
Which one of the following is the bases for this Tech Spec?
A. Ensure SDM limits are maintained and QPTR is maintained
within limits.
B. Ensure power distribution and SDM limits are preserved.
C. Ensure QPTR is maintained within limits and rod alignments
are correct.
D. Ensure AFD is maintained and limit power distribution.
Ques-1004.l.doc
~
1 Pt. Unit I is operating at 100% power when the following occurs:
LOCA outside containment
The leak can be isolated
Containment Sump Level is Normal
FWST level is 1 7 8
FWST has &ruptured
Which of the following procedures would be used to MITIGATE the event?
k ECA-1.I(Loss of Emergency Coolant Recirc)
B. ECA-1.2 {LCCA Outsids Containrnenf)
C. ES-1.2 (Post LOCA Cooldown and Depressurization)
D. ES-1.3 (Transfer to Cold Leg Recirc)
1 Pt. Given thG following conditions:
.
0 Pressurizer Level Channel 1 is at 28% level
Pressurizer Level Channel 2 associated bistables are in the tripped
condition due to surveillance testing
Pressurizer Level Channel 3 fails high.
N-41 is 8%
N-42 is 10%
N-43 is 9%
N-44is 9%
Impulse pressure channel 1 is 11%
Impulse pressure channel 2 is 9%
KO reactor tiip has cjccurred
Which of the following describes the proper operator response?
A. Trip the reactor and enter E-0 (Reactor Trip or Safety Injection)
B. Trip the reactor and enter FRS.1 (Response Nuclear Power
Generafion/ATWS)
C. Do not trip the reactor because thermal power is less than P-7
D. Do not trip the reactor. Initiate unit shutdown.
1 Pt. Given the following conditions on Unit 1:
A steam leak has occurred on the main steam header
Unit 1 reactor has been tripped and safety injection has actuated
The MSlVs will not close
20 minutes into the event lowest loop NC Tcold is 305 degrees
Based on the above conditions which one of the following is the correct
procedure flowpath?
A. From E-0 Reactor Trip or Safety Injection GO TO FR-P.2
(Response to Anticipated Pressurized Thermal Shock)
B. From E 4 go directly to ECA 2.1, (Uncontrolled
Depressurization of all Steam Generators)
C. From E 4 GO TO FR-P.l, (Response to Imminent Pressurized
Thermal Shock)
D. From E-0 GO TO E-2, (Faulted Steam Generator Isolation) and
then to ECA 2.1
1 Pt. Given the following conditions on Unit 1:
Chemistry had confirmed two leaking fuel rods
A large break LOCA occurs
E-0 Reactor Trip or Safety lnjection is complete
ES-1.3 Transfer to Cold Leg Recirc is complete
E-I Loss of Reactor or Secondary Coolant is complete
ES-1.2 Post LOCA Cooldown and Depressurizationis in effect.
All Red and Orange Paths have been addressed
IEMF 51A is reading 39WHR
Pressurizer level is 0%
The SRO is currently considering imp!ementing Yel!ow Path
procedures. Which one of the following describes proper procedure
implementation?
A. Go to FR-1.3, (Response to Voids in the Reactor Vessel) and
exit ES-1.2
B. Stay in ES-1.2 and implement FR-1.3 concurrently
C. Go to FR-Z.3, (Response to High Containment Radiation Level)
and exit ES-1.2
D. Stay in ES-1.2 and implement FR-2.3 concurrently
Ques-1042.doc
1 Pt(s) Given the following conditions on Unit 1:
Mode3
NC System is at 1700 psig and 450 degrees
In process of cooling down and depressurizing the NC System
Safety Injection has occurred
NC Pressure going down in an uncontrolled manner
Containment pressure going up in uncontrolled manner
Which one of the following describes the proper procedures to mitigate the
above?
A. Enter AP135 (ECCS Actuation During Plant Shutdown) and then
go to E-0 (Reactor Trip or Safety Injection).
B. Enter E-0 and then go to AP/35
C. Enter AP/35 and then go to AP/34 (Shutdown LOCA)
D. Enter E-O and then go to E 4 (Loss of Reactor or Secondary
Coolanf).
__..___--___._._____----.-.-------.-
1 Pt Given the following conditions on Unit 1:
Unit 1 is at 100% power.
A,B, and C VL AHU are running
Aand C VL AHUs have tripped and will not restart
Attempts to start D VL AHU were unsuccessful
Average temperature in lower containment for past 365 days has
been 105 degrees.
Maintenance indicated it will take two days to repair the VL AHUs.
Containment lower compartment temperature is 126 degrees and
steady.
Wnich one (1) of :he foliowing describes the rquirzd Technical
Specification actions to address the high containment temperature?
Reference Provided
A. Restore temperature to within limits in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
B. Reduce temperature to 4 2 5 degrees in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
C. No action is required to address high containment
temperature.
D. Be in Mode 3 in 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.
1 Pt. Given the following conditions on Unit 1:
In Mode 5 cooling down for a refueling outage.
The 1B ND pump tripped due to an electrical fault.
The 1A ND pump has been started per AP/I/A/5500/19 (Lossof
ND or ND System Leakage) Encl. 14 (Startup of ND Pumps)
NC temperature before the pump trip was 150 degrees
NC temperature has increased to 207 degrees.
AP/l/A/5500/19 (Loss of ND) is in effect
The SRO instructs the RO to cooldown to the pre-event temperature.
Which one (1) of the following describes the maximum mcidown rzte and
minimum flow rate allowed to cooldown?
REFERENCES PROVlDED
A. Maximum cooldown rate of 50 degreeslhr and minimum flow
rate of 1500 gpm.
B. Maximum cooldown rate of 75 degreeslhr and minimum flow
rate of 1000 gpm
C. Maximum cooldown rate of 50 degreeslhr and minimum flow
rate of 2000 gpm.
D. Maximum cooldown rate of 75 degreeslhr and minimum flow
rate of 1500 gpm.
1 Pt. As a result of thunderstorms Unit 2 has experienced a Loss of Offsite
Power and Reactor trip. E-0(Reactor Tip or Safety Injection) was
implemented and the crew has transitioned to ES-0.1 (Reactor Trip
Response).
The SRO asks the RO to check NC temperatures.
Which one (1) of the following would the RO use to describe the response
of the NC system?
A, NC Tave STABLE or trending to 557 degrees
13. NC T hots STABLE or trending to 553 degrees
C. NC T colds STABLE or trending to 557 degrees
D. NC Tave STABLE or trending to 553 degrees.
1 Pt. Radwaste is in the process of releasing WGDT 'A'. 1EMF -36 L is
inoperable due to PM. Trip 2 is received on OEMF-50 (Wasfe Gas
Discharge). The gaseous waste release is secured as a result of IWG-160
closing. Radwaste calls the control room SRO and reports OEMF-50 has
been purged and is ready to reinitiate the release.
Which one (1) of the following describes the actions of the control room
SRO?
k The SRO can authorize up to two (2) restarts without
re-sampling.
B. The SRO has Rad#aste terminate the release and existing
GWR paperwork, and generate new paperwork.
C. The SRO can authorize one (1) restart without re-sampling.
D. The SRO can authorize Radwaste to jumper control actions of
OEMFdO, restart release and take grab samples once per four
(4) hours during release.
Ques-lO58.doc
1 Pt. Given the following conditions on Unit 1:
SGTR in the '1A SIG
E-0 (Reactor Trip or Safety Injection) complete
E-3 (Steam Generator Tube Rupture) implemented.
Cooldown is secured due to operator exceeding Main Steam
Isolation set point.
Which one (1) of the following describes how the operator continues to
cooldown?
k Go to Bypass interlock on steam dumps and continue
cooldown with steam dumps.
5. Reset Main Steam Isolation, open MSlVs and continue
cooldown with steam dumps.
C. Reset Main Steam Isolation and PORVs and continue
cooldown using PORVs in manual.
D. Reset Main Steam Isolation and PORVs and continue
cooldown using PORVs in automatic.
Ques-1060.doc
1 Pt. Given the following:
Both Units operating at 100% power.
Atrain RN is operating on both units.
Operations Test Group is performing B train RN valve stroke
timing.
SRO is instructed to evaluate the consequences of stroking ORN-
2843 (Train I6 and 28 Discharge to RC)
Which one of the following describes the consequences of allowing the
technician to test this valve?
P.. NQConsequences &de to ATrain RN running an bath units.
B. Closing ORN-284B will isolate the RN nonessential header
return from Unit 2.
C. Closing ORN-2846 will isolate the RN nonessential header
return from Unit 1.
D. Closing ORN-284B will isolate RV pump discharge.
__.______._____..----.--------.- _-l_.__._______._____
1 Pt. Which one of the following describes the bases for prioritizing Critical
Safety Functions (CSF)?
A. The CSFs are prioritized to address challenges to the
boundaries that protect the general public from exposure to
radiation.
B. The CSFs are prioritized to address design bases accidents
that are described in the USFAR.
C. The CSFs are prioritized to ensure the proper optimal
responsa procedrers io implemented.
D. The CSFs are prioritized to address challenges to parameters
that would affect operation of Engineered Safeguard Features
equipment.
..._________1_.___1___I_______________
Ques-1067.doc
1 Pt(s) After Channel 1 7300 Process Control Cabinet Channel Operability Test
was completed the Unit 1 Pressurizer level master malhctions causing it to
demand full output while in automatic.
Which one of the following statements correctly describes the basis for the
McGuire limit on flow?
A. Letdown flow rates in excess of 135 gpm are limited to ensure
proper demineralizer operation and adhere to the design limits
of the letdown piping.
B. Letdown flow rates in excess of 120 gpm exceed the design limits
of the letdown orifice valves and induce resonance vibration.
C. Charging flow rates in excess of 100 gpm during normal
operation can induce vibration in the regenerative heat
exchanger tubes.
D. Charging flow rates between 65 gpm and 100 gpm total charging
flow will cause flashing in the regenerative heat exchanger.
Ques-107l.doc
1 Pt(s) As an SRO working on a Complex Maintenance Plan you are asked to
evaluate four possible work teams who must repair filter housing in a
1500 mRem/hr radiation field.
Which one of the following work teams would maintain station ALARA?
A. A qualified male worker who has previously performed this
task. He can complete this job in 20 minutes. This worker has
exceeded his Alert level for exposure and will require a dose
extension.
5. Two male workers who arc qualified to perform tbe task.
Together they can perform the task in 15 minutes. Both
workers have already accumulated 325 &em this year.
C. A team of a female worker who is qualified to perform the task
and a male worker who needs to qualify to this task. The female
is a declared pregnant worker. The team will need 15 minutes to
complete the task. The female has no dose and the male worker
has 200 &em for the year.
D. A team of a male and female both are qualified to the task but
will take 20 minutes to complete the task. Each has less than 100
mRem this year.
1 Pt(s) The following conditions exist on Unit 1:
Reactor power is 100%
1A CA Pump is running with 1CA-60A (1A CA Pump Disch to 1A S/G
Control) and 1CA-56 (1A CA Pump Disch to 1B S/G Control) closed
for post maintenance testing.
NIR level in 1B S/G increases to 84% due to 1CF-23 (1B S/G Control
Valve) failing open.
Which one of the following statements correctly describes the response of
the CA system to the above conditions?
A. 1A CA Pump remains running
1B CA pump auto starts
1CA-44B (1B CA Pump Disch to 1C S/G Control) and 1CA-40B
(1B CA Pump to Disch to 1D S/G Control) do not reposition.
Depressing the MD CA Modulating Valve Reset Train A
pushbutton will cause 1CA-60A and 1CA-56A to close.
B. 1A CA Pump remains running
1B CA pump auto starts
ICA-60A and 1CA-56A remain closed.
1CA-44B and 1CA-40B fail closed.
Depressing the MD CA Modulating Valve Reset Train A
pushbutton will cause 1CA-60A and 1CA-56A to open
C. 1A CA Pump trips
1B CA pump remains off
1CA-60A and 1CA-56A remain closed.
1CA-44B and 1CA-40B do not change position.
Depressing the MD CA Modulating Valve Reset Train A
pushbutton will cause 1CA-60A and 1CA-56A to open.
D. 1A CA Pump trips
1B CA Pump remains off
1CA-44B and 1CA-40B fail open.
Depressing the MD CA Modulating Valve Reset Train A
pushbutton will cause 1CA-60A and 1CA-56A to close.
ANSWER KEY REPORT
for McGuire SRO Upgrade test Test Form: 0
-
- ID Points Type - Answers
~
1 ANSWER-KEY 1
~
1.00 MCS C
2 ANSWER-KEY 2 1.00 MCS D
3 ANSWER-KEY 3 1.00 MCS B
4 ANSWER-KEY 4 1.00 MCS C
5 ANSWER-KEY 5 1.00 MCS C
6 ANSWER-KEY 6 1.00 MCS B
7 ANSWER-KEY 7 1.00 MCS A
8 ANSWER-KEY 8 1.00 MCS A
9 ANSWER-KEY 9 1.00 MCS A
10 ANSWER-KEY 10 1.00 MCS B
11 ANSWER-KEY 11 1.00 MCS A
12 ANSWER-KEY 12 1.00 MCS D
13 ANSWER-KEY 13 1.00 MCS D
14 ANSWER-KEY 14 1.00 MCS D
15 ANSWER-KEY 15 1.00 MCM A (1 .OO) D (1.00)
16 ANSWER-KEY 16 1.00 MCS C
17 ANSWER-KEY 17 1.00 MCS D
18 ANSWER-KEY 18 1.00 MCS C
19 ANSWER-KEY 19 1.00 MCS B
20 ANSWER-KEY 20 1.00 MCS C
21 ANSWER-KEY 21 1.00 MCS B
22 ANSWER-KEY 22 1.00 MCS A
23 ANSWER-KEY 23 1.00 MCS C
24 ANSWERKEY 24~
1.00 MCS A
25 ANSWER-KEY 25 1.00 MCS A
SECTION 1 ( 2 5 items) 25.00
Tuesday, July 15,200311:00:01 AM 1