IR 05000335/1992300
| ML17227A726 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie, Susquehanna  |
| Issue date: | 02/01/1993 |
| From: | Ernstes M, Moorman J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17227A725 | List: |
| References | |
| 50-335-92-300, 50-335-92-300-0, NUDOCS 9302160168 | |
| Download: ML17227A726 (61) | |
Text
~y RiRECC (4 P0 Cy 0O
Cy o~
Cy Wp*~W UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 ENCLOSURE
EXAMINATION REPORT - 50-335/93-300 r
Facility Licensee:
Florida Power and Light Company Facility Name:
St.
Lucie Nuclear Plant Facility Docket Nos.:
50-335 and 50-389 Facility License Nos.:
DPR-67 AND NPF-16 Requalification written examinations and operating tests were administered at the St. Lucie Nuclear Plant near Jensen Beach, Florida.
Chief Examiner:
p/ ~/g~~
l J
mes H. Moorman, III Date Signed Approved By:
Michael
. Ernstes, Chief Operator Licensing Section
Operations Branch Division of Reactor Safety
/
Ciz Date Signed SUMMARY SCOPE:
Retake requalification written exams were administered on December 4,
1992 to three reactor operators who had failed exams administered October 30, 1992.
One Senior Reactor Operator (SRO)
was also given a
written exam.
During the week of January 18, 1993, a retake requalification operating test (JPMs)
was administered to one RO.
One SRO was administered a complete operating test.,
No crew evaluations were conducted.
RESULTS:
One RO failed the written exam.
All other operators passed their exams.
9302160168 930202 PDR ADOCK 05000335 V
REPORT DETAILS 1.
Facility Employees Attending Exit Interview K.
p.
K.
L.
J.
J.
Beatty, Training Hanager
- Corporate Fincher, Training Hanager Hetzger, Operations Training - Corporate Rich, Operations Training Spodick, Operations Training Supervisor West, Operations Supervisor 2.
NRC Personnel
- J Hoorman, III, Senior Examiner, Region II
- Chief Examiner 3.
Discussion a
~
Examination Results C.
Licensed operator retake requalification examinations were administered at the St.
Lucie Nuclear Plant in accordance with NUREG-1021, Operator Licensing Standards, Revision 7.
Retake written examinations were administered to three ROs and retake JPHs were administered to one RO.
One RO failed the written exam while all others passed the exams.
One SRO was administered the written examination on December 4,
1992, and the operating test on January 20, 1993.
This operator had taken a
position at a Florida Power and Light (FPRL) fossil station and no longer needed an NRC operators'icense.
The St.
Lucie management had requested that his license be terminated just prior to the requalification exams that were administered in October 1992.
This operator had been selected to be examined during the October 1992 exams.
Prior to the NRC officially terminating his license, he requested that FP&L return him to his previous position.
Since he had missed only the evaluation portion of the requalification program, the NRC allowed him to maintain his current license by passing an NRC administered requalification examination.
Written Exam Preparation and Administration The written exam was prepared by the licensee and approved by the NRC for use as a retake exam.
The exam was administered on December 4,
1992, by the facility. It was then mailed to the NRC for parallel grading.
The sampling plan that was used to select the examination topics for the exam administered in October 1992 was also used to generate this exa Report Detail s d.
Operating Test Preparation and Administration The job performance measures (JPMs)
and simulator scenarios were validated onsite by the exam team on January 19, 1993.
The proposed job performance measures covered high level tasks that were performed both inside and outside of the control room.
An operating crew for the simulator exam was composed of two ROs and two SROs.
One scenarios was used for the evaluation.
This scenario required the use of EOP-15, Functional Recovery.
This is the procedure used when an optimal recovery procedure cannot be entered and is similar to "contingency" procedures used by other reactor types.
The simulator scenario used for the evaluation involved a loss o'f all offsite and emergency power (blackout).
In this configuration, there are some important indications that are de-energized and unavailable.
To compensate for this, some parameters must be extrapolated from other indications.
The reactor coolant system (RCS) pressure input used to calculate subcooling is de-energized, leaving no direct indication of subcooling.
The wide range RCS pressure indication is also de-energized.
This leaves only narrow range safety pressure channels (1500 psia to 2500 psia range)
and the low range pressure indication (0 psia to 750 psia range).
Indication for the turbine driven auxiliary feedwater pump is also affected in this scenario.
The normal indication of pump discharge pressure and flow is de-energized.
The only indication available to monitor emergency feedwater flow is feed header pressure and the pumps'team throttle valve position.
The lack of these indications makes it difficult to perform the Safety Fucntion Status Checks of EOP-10, Blackout.
Facility representatives were aware of these problems and stated that a plant modification to correct these was scheduled to be installed during the next outage.
4.
Exit Interview At the conclusion of the site visit, the examiner met with representatives of the plant staff to discuss the results of the examinations.
The licensee did not identify as proprietary any material provided to or reviewed by the examine ENCLOSURE
SIMULATOR FIDELITY REPORT Facility Licensee:
Florida Power and Light Facility Docket Nos.
50-335 and 50-389 Operating Tests Administered On:
January 20, 1993 This form is used only to report observations.
These observations do not constitute, in and of themselves, audit or inspection findings and are not, without further verification or review, indicative of noncompliance with
CFR 55.45(b).
These observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations.
No licensee action is required solely in response to these observations.
During the conduct of the simulator portions of the operating tests, the following items were observed:
Progress had been made toward replacing the "Sigma" control board indicators with the newer digital indicator WRITTEN EXAMINATION NAME:
DATE:
SSN/CD:
LOR TRAINING PROGRAM NRC EXAM NO. 0820259R AUTHOR:
D. Carpenter REVIEWED BY:
DATE: 11/17/92 DATE:
GRADE:
INSTRUCTIONS 1.
WRITE YOUR ANSWERS ON THE ANSWER SHEET PROVIDED, fill in your choices with a number II2 pencil.
2.
Point value for each question appears in parentheses.
3.
There are
points on this exam.
4.
Do not talk to anyone but the examiner during the examination unless otherwise directed.
5.
Do not transmit or receive any information, material or other communication to anyone but the examiner during the examination unless otherwise directed.
6.
Do not allow access to your examination by anyone but the examiner during the examination.
Do not seek access to any other individual's examination or materials.
7.
Oo not leave the examination area without the approval of the examiner.
8.
Any evidence of cheating detected by the examiner is grounds for dismissal from the examination.
9.
SIGN AFTER YOU HAVE FINISHED EXAM:
I I have neither given nor received any assistance in completing this exam.
SIGNATURE DATE
Licensed 0 erator Re ual RO NRC 0 en Reference Exam Unit 1 has been diagnosed as having a 20 GPH S/G tube leak.
'C'harging pump and '8'ontainment spray pump are out of service.
All other equipment is operational.
During a controlled shutdown, Pressurizer level decreases rapidly with increasing secondary radiation resulting in a TH/LP reactor trip.
On the trip a Loss of Offsite Power occurs and the 'A'G trips on differential current.
EOP strategy should be:
'a ~
b.
C.
d.
)-EOP-O),
then )-EOP-)5 due to a dual event in progress.
)-EOP-01, then 1-EOP-02 with ONPs for SGTL and Loss of Safety Related AC Bus.
)-EOP-O),
then
)-EOP-04 to mitigate the steam generator tube rupture.
)-EOP-O),
then
)-EOP-09 with ONP for SGT Licensed 0 erator Re ual RO NRC 0 en Reference Exam 2.
A LOCA occurred on Unit 1, =25 minutes ago.
You are checking for Natural Circulation and observe the following indications:
RCS Pressure:
820 psia T hot:
515 'F Pressurizer Level:
0%
SG Pressures:
820 psia SG Levels:
50%
NR and increasing HPSI Flow: = 1000 gpm CET Temperatures:
515-520 'F All charging pumps operating RVLNS indicates sensors 1-4 are voided Which of the following best describes the status of the heat removal safety functions?
'a ~
b.
C.
Natural circulation is not satisfied, because GET subcooling is not being maintained.
Therefore heat removal safety functions are not being met.
The excessive head void interferes with the formation of natural circulation and results in GET superheat, therefore heat removal safety functions are not met.
Break-flow and two-phase natural circulation are adequately maintaining the heat removal safety functions.
d.
S/G level and pressure indicates adequate heat removal. Single phase Natural Circulation is accomplishing the heat removal safety functio Licensed 0 erator Re ual RO NRC 0 en Reference Exam
[1.00]
3.
A SGTR has been diagnosed and is in progress on Unit 2.
You have been assigned to complete the Safety Function Status Check Sheet of EOP-04.
Which one of the following sets of conditions will ensure that the RCS Inventory Control Safety Function is satisfied?
a 0 Pzr level is 10%,
Pzr pressure is 800 psia, all charging pumps are running, total SI flow (2 trains)
is 500 gpm, and Rx vessel level sensors 4 through
are covered.
b.
C.
d.
Pzr level is 0%,
Pzr pressure is 600 psia, all charging pumps are running, total SI flow (2 trains)
is 1000 gpm, and Rx vessel level sensor 8 is covered.
Pzr level is 30%,
Pzr pressure is 800 psia, all charging pumps are running, RCS subcooling is 15'F, total SI flow (2 trains) is 1000 gpm, and Rx vessel level sensors 4 through 8 are covered.
Pzr level is 40%,
Pzr pressure is 800 psia, no charging pumps are running, RCS subcooling is 25'F, SI flow is throttled, and Rx vessel level sensors
through 8 are covered.
[1.00]
While performing Safety Function Status Check of EOP-05 the RCO reports that RCS temp is 350'nd pressurizer pressure is 1300 psia, which of the following would be appropriate crew actions as a result of this condition?
a
~
b.
C.
stop any cooldown and depressurize the RCS to within the limits of Fig.
1.
ensure all RCP's are secured.
stabilize RCS temperature and pressure at the current conditions.
d.
establish 20'ubcooling by reducing RCS temperatur Licensed 0 erator Re ual RO NRC 0 en Reference Exam
[1.00]
5.
Immediately following a complete loss of main feedwater from 50% power and prior to the reactor/turbine trip on low S/G level, the pressurizer pressure will:
a 0 b.
C.
d.
decrease, because the steam generator level initially increases, causing a contraction of the RCS inventbry.
increase, because the RCS delta T power increases until the reactor trip occurs.
decrease, because the increased boiling rate in the steam generator tube bundle region decreases RCS T>>,.
increase, because the RCS temperature increases due to elevated S/G temperatures.
6.
When restoring S/G level following a Total Loss of Feedwater
{TLOF), the initial feed RATE is based on:
a ~
b.
c ~
d.
the shut-off head of the Auxiliary Feed Pumps at the maximum S/G pressure.
industry experience that no significant water hammer will result in the feed line/ring.
the Technical Specification for RCS cooldown rate.
the time requirement to refill the steam generator downcomer region.
[1.00]
7.
I-EOP-09 directs the operators to open the condenser vacuum breaker valves.
This is accomplished by:
'a ~
b.
c ~
d.
failing them open by isolating air.
manual operation of the valves.
local pushbutton at the valves.
placing control switch on RTGB 101 to ope Licensed 0 erator Re ual RO HRC 0 en Reference Exam 8.
Unit 2 experienced a Station Blackout, EOP-1 and EOP-10 have been implemented.
All SFSC acceptance criteria are satisfied and one 4.16KV bus has been re-energized.
Which of the following is the proper procedure implementation?
a ~
b.
co d.
Exit 2-EOP-10 and refer to ONP 2-0910054,
"Loss of Safety Related AC Bus" to restore power to essential equipment.
Verify SFSC acceptance criteria for 2-EOP-09,
"Loss of Offsite Power" can be met, and exit to 2-EOP-09.
Exit 2-EOP-10 and refer to OP 2-0030128,
"Reactor Plant Shutdown" to continue plant shutdown.
Verify SFSC acceptance criteria for 2-EOP-02,
"Trip Recovery" can be met, and exit to 2-EOP-0 Licensed 0 erator Re ual RO NRC 0 en Reference Exam
[1.00]
9.
Unit 2 was at 100% power with the 2A diesel out of service for maintenance.
A system disturbance caused a loss of off-site power and on the trip the 2B diesel failed to start.
The crew exited EOP-Ol to EOP-10 "Station Blackout."
While performing the steps of the Station Blackout procedure, Chemistry called and reported that a routine Steam Generator sample, drawn just moments before the trip, indicates a primary to secondary leak into the 2B Steam Generator, a Chemistry calculation shows a leak rate of 100 GPH.
The crew should now:
a 0 b.
C.
d.
Exit to EOP-15, a Station Blackout and a Steam Generator Tube Rupture is a dual event.
Exit to the Steam Generator Tube Rupture procedure, it is written to incorporate a Station Blackout.
Stay in the Station Blackout procedure, regaining vital auxiliaries is the priority safety function.
Exit to the Steam Generator Tube Rupture procedure and use applicable portions of ONP 2-0910054, Loss of a Safety Related AC Bu Licensed 0 erator Re ual RO NRC 0 en Reference Exam 10.
Unit 2 is combating a complicated emergency using 2-EOP-15.
Current plant conditions are:
Pressurizer pressure
= 950 psia SIAS and CIAS have actuated RCS temperature
= 470 degrees Pressurizer level is 35%
All RCPs have been stopped RCP controlled bleedoff temperature 125 degrees RCP guide bearing temperatures all
= 180 degrees RCP thrust bearing temperature
= 190 degrees Based on the above conditions select the correct RCP strategy.
a b.
C.
d.
RCPs can be restarted when pressurizer pressure is less than 1300 psia.
RCPs cannot be restarted while in EOP-15.
RCPs cannot be restarted due to low pressurizer level.
RCPs can be restarted based on the above conditions.
[1.00]
ll.
While opening a
PORV isolation valve in the unit 2 control room, the breaker trips open.
The SNPO investigates and finds the breaker will not reclose.
It is determined that the thermal overload device has actuated.
This device:
a.
b.
C.
d.
compares actual current to an overcurrent setpoint and actuates trip relays which are reset automatically.
when subjected to high current, overheats and actuates a circuit-interrupting mechanism which is reset manually.
senses equipment temperature and actuates breaker trip circuit relays which are reset automatically.
is an induction coil driven by equipment temperature and actuates a breaker tripping mechanism which is reset manuall Licensed 0 erator Re ual RO NRC 0 en Reference Exam
[1.00]
.
12.
Unit 2 has just had a Loss of Offsite Power.
The 2A diesel generator has failed to start.
Local troubleshooting indicates the diesel generator will be out of service for a long time.
The ANPS directs you to note the 2A battery discharge rate and give him a time estimate on when low battery voltage could affect safety systems.
You observe a
200 AMP discharge rate and then report, "I anticipate voltage problems in a.
2 - 6 Hours b.
8 -
12 Hours c.
14 - 18 Hours d.
20 - 24 Hours
[1.00]
13.
Given:
Using:
Unit 2, cycle 6, 7000 EFPH L 100% power RCS Boron Concentration:
270 ppm BAN TK Concentration:
5844 ppm Makeup Water Boron Concentration:
ppm RCS Volume: 62,500 gallons Differential Boron worth: ll pcm/ppm Plant Physics Curve Book and (c c,)
V~
V~yg lzl mu P
It is desired to decrease reactivity by 165 pcm.
The required boron addition is:
a ~
b.
c ~
d.
146.8 gallons 168.4 gallons 187.8 gallons 201.8 gallons
Licensed 0 erator Re ual RO NRC 0 en Reference Exam
[1.00]
14.
An indication of clad failure, is the Letdown Radiation Honitor Gross Activity and the Selected Isotope Activity a ~
b.
c ~
d.
increasing, increasing decreasing, staying the same staying the same, decreasing increasing, staying the same i1.00]
15.
Unit 1 has been operating for 105 days at 100% power.
A transient occurs that has the following effects:
Reactor power decreased slightly, RCS Tave decreased slightly, Digital Data Processing System shows flux lower for a single string of incore detectors.
Which one of the following events caused the transient with the above indications?
a ~
b.
c ~
d.
An inadvertent boration.
A dropped CEA.
Xenon oscillation.
A trip of both Heater Drain Pump Licensed 0 erator Re ual RO NRC 0 en Reference Exam
[1.00]
16.
Given the following Unit 1 indications, select the correct Nuclear Instrumentation configuration.
Unit 1 is at 10% power CPS/% Power Channel B indicates 10'PS RTGB 104 %Power Recorder is selected to A and indicates 10%
Extended Range Light is out on Channels A, C, and D
'a ~
c ~
d.
Wide Range Log Safety Channel 8 is failed.
Linear Power Range Safety Channel 8 is failed.
Wide Range Log Control Channel B is failed.
Linear Power Range Control Channel B is failed.
17.
Unit 2 is in Mode 3 preparing to perform a reactor startup when Wide Range Log Safety NI Channel A fails.
What is the necessary ACTION to be performed IAW the Unit 2 Technical Specifications?
a
b.
c ~
d.
Bypass the Rate of Change of Power Bistable and continue the start-up.
Bypass the TM/LP, LPD 5 HI PWR Bistables, and stay in Mode 3 until repaired.
Trip the Rate of Change of Power Bistable and stay in Mode 3 until repaired.
Trip the TM/LP, LPD 5 HI PWR Bistables, and continue the start-u Licensed 0 erator Re ual RO NRC 0 en Reference Exam
[1.00]
18.
The bases for the minimum contained volume in the condensate storage tanks is:
a.
Unit 2 must have a minimum of 182,000 gallons to ensure sufficient water is available for cooldown to 350 F following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hot standby.
b.
C.
d.
Unit 1 must have a minimum of 125,000 gallons to ensure sufficient water is available for cooldown to 325 F following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at hot standby.
Unit 2 requires 149,600 gallons of water for cooldown to 350 F following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hot standby.
Unit 1 requires 116,000 gallons of water for cooldown to 325 F following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at hot standby.
[1.00]
19.
The 1C AFM pump has tripped on electrical overspeed.
Prior to placing the AB bypass switch to the normal position, the ONOP has a step to verify the pump is not rotating. If the pump was rotating upon restart it would possibly:
a ~
b.
C.
d.
not come up to full speed.
not start at all.
trip on overspeed.
cause damage to the governor.
[1.00]
20.
Procedure 2-EOP-10, Station Blackout, requires the operator to shut the RCP bleed-off isolation valves (V2505 5. V2524).
Other than losing RCS inventory, what would be the consequence of leaving these valves open?
'a ~
b.
c ~
d.
Seal leakoff could fill the VCT.
Bleedoff system relief may be challenged.
quench tank rupture disk could blow.
Flashing may occur in the bleedoff lin Licensed 0 erator Re ual RO NRC 0 en Reference Exam
[1.00]
21.
Unit 1 has tripped from 100% due to a with subsequent failure of the Diesel The operating crew has entered EOP-10 strategy of EOP-10 is:
loss of off-site power Generators to start.
(Blackout).
The basic a.
Establish, maintain, and verify natural circulation conditions in the RCS.
b.
Conserve CST inventory per EOP-99, Figures 3 and 4.
C.
Cooldown, due to loss of CCW and seal injection to the RCP seals.
d.
Allow the RCS to heat up to a maximum of 542 Tave to ensure pressurizer level is maintained.
[1.00]
22.
Of the following D/G indications on RTGB, which one would indicate that the D/G might NOT be ready to start?
a ~
b.
c ~
d.
Governor Yellow light on.
Green light on output breaker.
Green light on voltage regulator control.
Start-stop control Yellow light on.
[1.00]
23.
Which one of the following is the approximate time to reach boiling conditions after shutdown cooling is lost five days after shutdown on Unit 1, with the RCS at mid-loop and an initial temperature of 130 'F, and at atmospheric pressure?
a.
10 minutes b.
15 minutes c.
20 minutes d.
25 minutes
Licensed 0 erator Re ual RO NRC 0 en Reference Exam
[1.00]
24.
Unit 2 has been shutdown for 28 days and is in Node 5 with
. nozzle dams being installed in both SGs.
2A and 2B Shutdown Cooling System (SDC) loops were in service but have been secured due to loss of RCS level.
Operat'ors are unsuccessful in stopping the leak.
ONOP 2-0440030 is being implemented with the following plant conditions:
2A Charging pump has been started to restore RCS level.
RCS level is 29 ft.
2 in.
and slowly increasing 2A and 2B SGs are iii wet lay-up SDC temperature is 120f and stable Containment integrity exists Which one of the following would be used for RCS heat removal?
a.
boil off b.
SGs in the natural circulation mode.
c.
SDC when RCS level is above 29 ft. 6 in.
d.
once thru cooling mode
[1.00]
25.
During a gaseous release from the A Gas Decay Tank the RCO acknowledges a High Alarm on the Gaseous Effluent Honitor, which one of the following best describes his actions?
a ~
b.
notify chemistry to take a backup sample of the GDT.
verify oxygen concentration is within Tech.
Spec.
limits.
c ~
d.
ensure that HVE-10A or HVE-10B is running.
verify the gaseous waste isolation valve (V6565) is shu Licensed 0 erator Re ual RO NRG 0 en Reference Exam
[1.00]
26.
During an event where harsh environment conditions exist, Reg.
Guide 1.97 designated instruments should be used for diagnosis of events and confirmation of safety functions...
Which one of the following describes how this instrumentation is identified?
a ~
b.
C.
d.
Instrument tags on the RTGBs have 1.97 related information stamped into them.
Black bezels surround the instruments to help in identifying type and category.
The Eg lists provided in the control rooms contain all instruments that meet this requirement.
White bezels surround the instruments that meet the specifications of the Reg.
Guide.
[1.00]
27.
If one safety valve on 2A SG is gagged and two safety valves on 2B SG are gagged, then Reactor power:
a ~
b.
c ~
d.
Must be reduced to g 66.3%
Must be reduced to < 79.6%
Must be reduced to g 88.2%
Must be reduced to g 92.8%
Licensed 0 erator Re ual RO NRC 0 en Reference Exam
[1.00]
28.
At Unit 2, while withdrawing Group 5 to ARO during power ascension (power = 30%), two of the Group 5 CEAs drop to the bottom.
The last measured F', is 1.60.
Which of the actions listed below is the most appropriate7 a ~
b.
Realign both CEAs to < 7" deviation within the time limits of Technical Specification, Fig. 3. 1-la.
Be in HOT STANDBY within one hour.
C.
d.
Determine from symptoms and CEA position indications the operability of the CEA per appendix B.
Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
[1.00]
29.
According to AP 0010120,
"Duties and Responsibilities of Operators on Shift", which one of the following is an acceptable set of circumstances for manually initiating AFAS?
a ~
b.
c ~
d.
A loss of all main feedwater occurred at 100% power resulting low SG level reactor trip.
Three minutes post trip both SGs are approaching 30%
WR level.
A loss of offsite power had occurred from 100% power and one DG failed to start.
Five minutes later a
manual start was attempted and was successful.
A reactor trip has occurred and an ESDE is in progress.
Both NSIVs were closed and when AFAS initiated only the 'B'ide components actuated.
A normal reactor plant shutdown has occurred for refueling.
Hain feedwater and the 15% bypass valves are no longer useful and AFW is desire Licensed 0 erator Re ual RO NRC 0 en Reference Exam
[1.00]
30.
Which ONE of the following conditions would require the use of AP 0010124 "Control and Use of Jumpers and Disconnected Leads" ?
a 0 b.
c ~
d.
Replacing Sigmas with the new digital displays on RTGB 206 IAW the PCH package.
A temporary cable is installed on a receptacle to operate a welding machine.
I&C technicians, while troubleshooting, connect a hand held digital Fluke to two terminals.
Temporarily bypassing the Overspeed Protection Circuit in the DEH compute WRITTEN EXAMINATION LOR TRAINING PROGRAM NRC EXAM NO. 0820259R AUTHOR: 0. Carpenter DATE: ll/17/92 ANSWER KEY 1.
c.
REF:
0802999 2.
c.
REF:
0802999 3.
d.
REF:
0802825 REF:
0802999 5.
d.
REF:
0702827 6.
b.
REF:
0702827 7.
b.
REF:
0702835 8.
b.
REF'802999 9.
a.
REF:
0802999 10.
c.
REF'802999 ll.
b.
REF:
0702502 12.
b.
REF:
0702504 13.
b.
REF:
0702205 14.
a.
REF:
0702205 15.
b.
REF:
0702405 16.
a.
REF:
0702403 a.
REF:
0702404 18.
c.
REF'702412 19.
c.
REF:
0702412 20.
a.
REF'702202 21.
REF:
22.
REF:
23.
REF:
24.
REF:
25.
REF:
26.
REF:
27.
REF:
28.
REF,:
29.
REF:
30.
REF:
0702209 C.
0702501 C ~
0702207 C ~
0702207 d.
0702410 d.
0702834 b.
0802810 b.
0802810 b.
0802424 d.
0802424
WRITTEN EXAMINATION LOR TRAINING PROGRAM NRC EXAM NO. 0820259R AUTHOR: D. Carpenter DATE: ll/17/92 ANSWER KEY l.
REF:
2.
REF:
3.
REF:
"(
4.
REF:
5.
REF:
6.
REF:
7.
REF:
8.
REF:
9.
REF:
10.
REF:
C.
0802999 C.
0802999 d.
0802825 a 0 0802999 d.
0702827 b.
0702827 b.
0702835 b.
0802999
'a ~
0802999 C ~
0802999 I c ll.
b.
REF:
0702502 ii 12.
b.
REF:
0702504 13.
b.
REF:
0702205 I z 14.
a.
REF:
0702205 t3 15.
b.
REF:
0702405 16.
a.
REF:
0702403 l5 17.
a.
REF:
0702404 18.
c.
REF:
0702412 i7 19.
c.
REF:
0702412 20.
a.
REF:
0702202 lg 21.
REF:
22.
REF:
Z I 23.
REF:
24.
REF:
25 REF:
2f 26.
REF:
x5'7.
REF:
28.
REF.:
2 'I 29.
REF:
30.
REF:
a ~
0702209 C ~
0702501 C.
0702207 C ~
0702207 d.
0702410 d.
0702834 b.
0802810 b.
0802810 b.
0802424 d.
0802424
WRITTEN EXAMINATION
]ifa~ )4e gSL.
tac c
NAME:
DATE:
SSN/CD:
LOR TRAINING PROGRAM NRC EXAM NO. 0820258R AUTHOR:
D. Carpenter REVIEWED BY:
DATE: 11/18/92 DATE:
GRADE:
INSTRUCTIONS 1.
WRITE YOUR ANSWERS ON THE ANSWER SHEET PROVIDED, fill in your choices with a number 82 pencil.
2.
Point value for each question appears in parentheses.
3.
There are
points on this exam.
4.
Do not talk to anyone but the examiner during the examination unless otherwise directed.
5.
Do not transmit or receive any information, material or other communication to anyone but the examiner during the examination unless otherwise directed.
6.
Do not allow access to your examination by anyone but the examiner during the examination.
Do not seek access to any other individual's examination or materials.
7.
Do not leave the examination area without the approval of the examiner.
8.
Any evidence of cheating detected by the examiner is grounds for dismissal from the examination.
9.
SIGN AFTER YOU HAVE FINISHED EXAM:
I have neither given nor received any assistance in completing this exam.
SIGNATURE DATE
Licensed 0 erator Re ual RO NRC Static Simulator Exam
[1.00]
Based on the cur rent plant conditions, which one of the following is correct concerning AFAS 1 and 2?
'a ~
AFAS 1 is timing out to actuation, AFAS 2 is not needed at this time..
b.
C.
AFAS 1 has occurred and reset on level, AFAS 2 is precluded due to rupture logic.
AFAS 1 is precluded due to rupture logic, AFAS 2 is not needed at this time.
d.
AFAS 1 is not needed at this time, AFAS 2 is precluded due to rupture logic.
[1.00]
2.
NSIS has occurred on channel B.
The B HSIV did not close.
Which one of the following is the correct method to close the NSIV?
'a ~
C.
Locally isolate instrument air and break the HSIV pressure switch tubing.
Hanually initiate channel A NSIS on RTGB 206.
Locally isolate instrument air and open the accumulator drain valve.
d.
Remove the B HSIY control power fuses inside RTGB 206.
[1.00]
3.
If during the downpower the operators forgot to transfer to the start-up transformers and opened the OCBs prior to tripping the turbine or the reactor what would the electrical line-up be now.
'a b.
c ~
d.
The diesels would be carrying the vital busses.
Off-site power would be from the start-ups.
A blackout would have occurred.
Off-site power would be from the auxiliarie Licensed 0 erator Re ual RO NRC Static Simulator Exam 4.
Given the current plant configuration, which one of the following is correct concerning the Emergency Diesel Generator operations?
'a ~
b.
C.
d.
If a LOOP occurred now, it would disable all but two (2) of the DG trips.
To increase DG output frequency, position the DG governor to raise.
The DGs are running in the isochronous mode with the output breakers open.
Depressing the Emergency Shutdown on RTGB 201 will shutdown the DG.
5.
Which ONE of the following statements describes the reason that all of the Pressurizer Safety Valve discharge line temperature indications, TIA 1107 (V-1200), TIA 1108 (V-1201), TIA 1109 (1202)
and both PORV discharge line temperature indications, TIA 1106 and TIA 1110 are reading high?
a 0 b.
C.
d.
The instruments have failed high due to the harsh environment inside the Containment during a
LOCA.
Pressurizer Pressure exceeded the lift setpoint of the Pressurizer Safeties and the PORV's when the Reactor and Turbine tripped.
The discharge lines have a
common discharge into the quench Tank.
The temperature indications reflect the conditions in the common discharge header.
Al'l of the Pressurizer Safeties and PORV's are leaking by because of the increased D/P across the valves when the quench Tank rupture disc blew ou Licensed 0 erator Re ual RO NRC Static Simulator Exam
[1.00]
If the crew is successful in getting the B HSIV closed at this point, which one of the following would be the appropriate actions to take?
a ~
Exit 2-EOP-15 and enter 2-EOP-03, LOCA, since the ESDE has been terminated.
b.
C.
Exit 2-EOP-15 and enter 2-EOP-01 for re-diagnosis of plant conditions.
Remain in 2-EOP-15 until all SFSC acceptance criteria are satisfied.
d.
Remain in 2-EOP-15 until Pzr level and RCS subcooling are recovered.
[1.00]
7.
Which one of the following best describes how this event could result in a Pressurized Thermal Shock scenario if the RCS leak were not present?
a 0 Charging pumps overpressurize the RCS because of the high pressurizer level caused by a reactor vessel head void.
b.
C.
d.
Addition of RCS inventory by charging and HPSI pumps and the RCS heatup resulting from dryout of the affected S/G results in excessive RCS pressure.
Cooldown exceeding Tech Spec limits results in brittle fracture of the most limiting RCS components.
High containment pressure and temperature as a result of the ESDE has the potential for causing PTS of the steel containment vesse Licensed 0 erator Re ual RO NRC Static Simulator Exam
[1.00]
8.
Based on this event when must the NRC be notified?
a
~
b.
C.
d.
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
[1.00]
9.
The four Reactor Coolant Pumps'eals are being cooled by:
a.
CVCS.
b.
CCW flow.
c.
RCS flow.
d.
ambient losse Licensed 0 erator Re ual RO NRC Static Simulator Exam QUESTIONS 10 THROUGH 15 ARE NOT STATIC SIMULATOR RELATED
Licensed 0 erator Re ual RO NRC Static Simulator Exam
[1.00]
10.
RAS closes V3659 and V3495, HPSI recirc isolation valves.
Which one of the following statements best describes why these valves are closed on RAS?
'a ~
b.
C.
To ensure adequate injection flow to the RCS from the remaining ECCS pumps.
To ensure the NPSH of the HPSI pumps are maintained during the recirc phase.
To prevent an unmonitored release to the environment from the RWT vent.
d.
To prevent corrosive, high temperature water damaging the RWT liner.
[1.00]
11.
The NPD checks the auxiliary feedwater pumps every shift for
"steam binding".
Choose the correct flow path that would likely cause
"steam binding" on Unit 2.
a ~
b.
c ~
d.
One check valve, one MOV leak by.
One check valve, one MOV, one solenoid valve leak by.
Two check valves, one MOV leak by.
Two check valves, one MOV, one solenoid valve leak by.
[1.00]
12.
The Unit 2 Containment Isolation Monitors indicate radioactivity inside the containment, and are used for the Containment Isolation Actuation Signal.
(Choose the response which best completes this statement).
a ~
b.
c ~
d.
general area beta/gamma particulate, gaseous, and iodine new fuel alpha N16 gamma
Licensed 0 erator Re ual RO NRC Static Simulator Exam
[1.00]
13.
An RCP oil reservoir level indication PCM was recently installed on Unit 2 to increase reliability of the indication.
One disadvantage of this modification is; a 0 b.
C.
The new power supply is from a non-vital source.
High and low level alarms are no longer operational.
Indicator response time may be delayed for up to 15 seconds.
d.
Reservoir level indication is lost on a CIAS.
14.
The sample line to the '8'CW Radiation Monitor has isolated due to a spurious low pressure signal which has closed the solenoid isolation valve I-SE-26-2.
When the signal is cleared, how can the solenoid valve be re-opened?
a ~
b.
c ~
d.
Push the reset button on the radiation monitoring panel in the Unit 2 control room.
The valve will automatically stroke open when the low pressure signal clears.
Take the solenoid valve open/close switch on RTGB 206 to CLOSE-OYERRIDE, then to OPEN.
Send an operator to the CCW building to locally open the solenoid valv Licensed 0 erator Re ual RO NRC Static Simulator Exam 15.
Which one of the following statements is most correct concerning the SG tube rupture event?
a ~
b.
Co d.
No relationship exists between this event and the Tech Spec requirements for RCS leakage.
Types of SGTR events are based on the ability of the PPLCS to maintain pressurizer pressure.
Stress Corrosion Cracking has been identified as a
cause of SG tube failures in the industry.
The core heat removal safety function is severely impacted by this even WRITTEN EXAMINATION LOR TRAINING PROGRAM NRC EXAM NO. 0820258R AUTHOR:
D. Carpenter DATE: ll/18/92 ANSWER KEY 1.
d.
REF:
0702412 2.
a.
REF:
0702401 3.
a.
REF:
0702502 4.
c.
REF:
0702501 5.
c.
REF:
0702206 6.
c.
REF:
0802999 7.
b.
REF:
0802999 8.
d.
REF:
0702833 9.
a.
REF'702205 10.
c.
REF:
0702401 ll.
d.
REF:
0702412 12.
a.
REF:
0702411 13.
d.
REF:
0802424 14.
a.
REF:
0702835 15.
c.
REF:
0702825
WRITTEN EXAMINATION
/Lfe.e r e
+FCktrF/
s/l
~.
NAME:
DATE:
SSN/CD:
LOR TRAINING PROGRAM NRC EXAM NO. 0820259S AUTHOR:
D. Carpenter REVIEWED BY:
DATE: 11/17/92 DATE:
GRADE:
INSTRUCTIONS 1.
WRITE YOUR ANSWERS ON THE ANSWER SHEET PROVIDED, fill in your choices with a number ¹2 pencil.
2.
Point value for each question appears in parentheses.
3.
There are
points on this exam.
4.
Do not talk to anyone but the examiner during the examination unless otherwise directed.
5.
Do not transmit or receive any information, material or other communication to anyone but the examiner during the examination unless otherwise directed.
6.
Do not allow access to your examination by anyone but the examiner during the examination.
Do not seek access to any other individual's examination or materials.
7.
Do not leave the examination area without the approval of the examiner.
8.
Any evidence of cheating detected by the examiner is grounds for dismissal from the examination.
9.
SIGN AFTER YOU HAVE FINISHED EXAM:
I have neither given nor received any assistance in completing this exam.
SIGNATURE DATE
E.
Licensed 0 erator Re ual SRO NRC 0 en Reference Exam f1.003 Unit 1 has been diagnosed as having a 20 GPM S/G tube leak.
'C'harging pump and 'B'ontainment spray pump are out of service.
All other equipment is operational.
During a controlled shutdown, Pressurizer level decreases rapidly with increasing secondary radiation resulting in a TH/LP reactor trip.
On the trip a Loss of Offsite Power occurs and the 'A'G trips on differential current.
EOP strategy should be:
a ~
b.
c ~
d.
1-EOP-01, then 1-EOP-15 due to a dual event in progress.
l-EOP-Ol, then 1-EOP-02 with ONPs for SGTL and Loss of Safety Related AC Bus.
I-EOP-01, then 1-EOP-04 to mitigate the steam generator tube rupture, I-EOP-01, then I-EOP-09 with ONP for SGTL.
[1.00]
2.
The unit was being brought off line due to primary safety valve leakage on V-1202 of approximately 150 gallons per hour.
At 15% power, the 'leakage increased to an estimated 750 gallons per hour.
Which ONE of the following statements is the correct action according to Technical Specifications?
a ~
b.
C.
d.
Be in at least hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown in the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or 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 />.
Be in at least hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in hot shutdown in the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Isolate the pressure boundary leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in hot standby within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Licensed 0 erator Re ual SRO NRC 0 en Reference Exam
[).00]
3.
A SGTR has been diagnosed and is in progress on Unit 2.
You have been assigned to complete the Safety Function Status Check Sheet of EOP-04.
Which one of the following sets of conditions will ensure that the RCS Inventory Control Safety Function is satisi'ied?
a ~
Pzr level is 10%,
Pzr pressure is 800 psia, all charging pumps are running, total SI flow (2 trains)
is 500 gpm, and Rx vessel level sensors 4 through 8 are covered.
b.
C.
d.
Pzr level is 0%,
Pzr pressure is 600 psia, all charging pumps are running, total SI flow (2 trains)
is 1000 gpm, and Rx vessel level sensor 8 is covered.
Pzr level is 30%,
Pzr pressure is 800 psia, all charging pumps are running, RCS subcooling is 15'F, total SI flow (2 trains) is 1000 gpm, and Rx vessel level sensors 4 through 8 are covered.
Pzr level is 40%,
Pzr pressure is 800 psia, no charging pumps are running, RCS subcooling is 25'F, SI flow is throttled, and Rx vessel level sensors I
through 8 are covered.
[1.00]
4.
While performing Safety Function Status Check of EOP-05 the RCO reports that RCS temp is 350'nd pressurizer pressure is 1300 psia, which of the following would be appropriate crew actions as a result of this condition?
a ~
b.
c ~
stop any cooldown and depressurize the RCS to within the limits of Fig. l.
ensure all RCP's are secured.
stabilize RCS temperature and pressure at the current conditions.
d.
establish 20'ubcooling by reducing RCS temperatur Licensed 0 erator Re ual SRO NRG 0 en Reference Exam
[1. 00]
5.
When restoring S/G level following a Total Loss of Feedwater (TLOF), the initial feed RATE is based on:
'a ~
b.
c ~
d.
the shut-off head of the Auxiliary Feed Pumps at the maximum S/G pressure.
industry experience that no significant water hammer will result in the feed line/ring.
the Technical Specification for RCS cooldown rate.
the time requirement to refill the steam generator downcomer region.
[1.00]
6.
1-EOP-09 directs the operators to open the condenser vacuum breaker valves.
This is accomplished by:
a ~
b.
c ~
d.
failing them open by isolating air.
manual operation of the valves.
local pushbutton at the valves.
placing control switch on RTGB 101 to ope Licensed 0 erator Re ual SRO NRC 0 en Reference Exam
[1.00]
7.
Unit 2 experienced a Station Blackout, EOP-1 and EOP-10 have been implemented.
All SFSC acceptance criteria are satisfied and one 4. 16KV bus has been re-energized.
Which of the following best describes the actions to be taken by the crew?
'a ~
b.
c ~
Exit 2-EOP-10 and refer to ONP 2-0910054,
"Loss of Safety Related AC Bus" to restore power to essential equipment.
Verify SFSC acceptance criteria for 2-EOP-09,
"Loss of Offsite Power" can be met, and exit to 2-EOP-09.
Exit 2-EOP-10 and refer to OP 2-0030128,
"Reactor Plant Shutdown" to continue plant shutdown.
Verify SFSC acceptance criteria for 2-EOP-02,
"Trip Recovery" can be met, and exit to 2-EOP-0 Licensed 0 erator Re ual SRQ NRC 0 en Reference Exam
[1.00]
8.
Unit 2 was at 100% power with the 2A diesel out of service for maintenance.
A system disturbance caused a loss of off-site power and on the trip the 2B diesel failed to start.
The crew exited EOP-Ol to EOP-10 "Station Blackout."
While performing the steps of the Station Blackout procedure, Chemistry called and reported that a routine Steam Generator sample, drawn just moments before the trip, indicates a primary to secondary leak into the 2B Steam Generator, a Chemistry calculation shows a leak rate of 100 GPH.
The crew should now:
'a ~
b.
C.
d.
Exit to EOP-15, a Station Blackout and a Steam Generator Tube Rupture is a dual event.
Exit to the Steam Generator Tube Rupture procedure, it is written to incorporate a Station Blackout.
Stay in the Station Blackout procedure, regaining vital auxiliaries is the priority safety function.
Exit to the Steam Generator Tube Rupture procedure and use applicable portions of ONP 2-0910054, Loss of a Safety Related AC Bu Licensed 0 erator Re ual SRO NRC 0 en Reference Exam
[1.00]
Unit 2 is combating a complicated emergency using 2-EOP-15.
Current plant conditions are:
Pressurizer pressure
= 950 psia SIAS and CIAS have actuated RCS temperature
= 470 degrees Pressurizer level is 35%
All RCPs have been stopped RCP controlled bleedoff temperature
= 125 degrees RCP guide bearing temperatures all
= 180 degrees RCP thrust bearing temperature
= 190 degrees Based on the above conditions select the correct RCP strategy.
a 0 b.
c ~
d.
RCPs can be restarted when pressurizer pressure is less than 1300 psia.
RCPs cannot be restarted while in EOP-15.
RCPs cannot be restarted due to low pressurizer level.
RCPs can be restarted based on the above conditions.
[1.00]
10.
While opening a
PORV isolation valve in the unit 2 control room, the breaker trips open.
The SNPO investigates and finds the breaker will not reclose.
It is determined that the thermal overload device has actuated.
This device:
'a ~
b.
c ~
d.
compares actual current to an overcurrent setpoint and actuates trip relays which are reset automatically.
when subjected to high current, overheats and actuates a circuit-interrupting mechanism which is reset manually.
senses equipment temperature and actuates breaker trip circuit relays which are reset automatically.
is an induction coil driven by equipment temperature and actuates a breaker tripping mechanism which is reset manuall Licensed 0 erator Re ual SRO NRC 0 en Reference Exam
[1.00]
ll.
Unit 2 has just had a Loss of Offsite Power.
The 2A diesel generator has failed to start.
.Local troubleshooting indicates the diesel generator will be out of service for a long time.
The ANPS 'directs you to note the 2A battery discharge rate and give him a time estimate on when low battery voltage could affect safety systems.
You observe a
200 AMP discharge rate and then report, "I anticipate voltage problems in a.
2 - 6 Hours b.
8 -
12 Hours c.
14 -
18 Hours d.
20 - 24 Hours 12.
An indication of clad failure, is the Letdown Radiation Monitor Gross Activity and the Selected Isotope Activity
'a ~
b.
C.
d.
increasing, increasing decreasing, staying the same staying the same, decreasing increasing, staying the same
Licensed 0 erator Re ual SRO NRC 0 en Reference Exam
[1.00]
13.
Unit 1 has been operating for 105 days at 100% power.
A transient occurs that has the following effects:
Reactor power decreased slightly, RCS Tave decreased slightly, Digital Data Processing System shows flux lower fo'r a single string of incore detectors.
Which one of the following events caused the transient with the above indications?
a.
An inadvertent boration.
b.
A dropped CEA.
c.
Xenon oscillation.
d.
A trip of both Heater Drain Pumps.
[1.00]
14.
Given the following Unit 1 indications, select the correct Nuclear Instrumentation configuration..
Unit 1 is at 10% power CPS/%
Power Channel B indicates
CPS RTGB 104 %Power Recorder is selected to A and indicates 10%
Extended Range Light is out on Channels A, C, and D
a t b.
C.
d.
Wide Range Log Safety Channel B is failed.
Linear Power Range Safety Channel B is failed.
Wide Range Log Control Channel B is failed.
Linear Power Range Control Channel B is faile Licensed 0 erator Re ual SRO NRC 0 en Reference Exam
[1. 00]
15.
Unit 2 is in Hode 3 preparing to perform a reactor startup when Wide Range Log Safety NI Channel A fails.
What is the necessary ACTION to be performed IAW the Unit 2 Technical Specifications?
'a ~
b.
c ~
d.
Bypass the Rate of Change of Power Bistable and continue the start-up.
Bypass the TH/LP, LPD & HI PWR Bistables, and stay in Hode 3 until repaired.
Trip the Rate of Change of Power Bistable and stay in Hode 3 until repaired.
Trip the TH/LP, LPD & HI PWR Bistables, and continue the start-up.
[1.00]
16.
The bases for the minimum contained volume in the condensate storage tanks is:
'a ~
b.
C.
d.
Unit 2 must have a minimum of 182,000 gallons to ensure sufficient water is available for cooldown to 350 F following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hot standby.
Unit 1 must have a minimum of 125,000 gallons to ensure sufficient water is available for cooldown to 325 F following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at hot standby.
Unit 2 requires 149,600 gallons of water for cooldown to 350 F following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hot standby.
Unit 1 requires 116,000 gallons of water for cooldown to 325 F following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at hot standb Licensed 0 erator Re ual SRO NRC 0 en Reference Exam
[1.00]
17.
The 1C AFW pump has tripped on electrical overspeed.
Prior to placing the AB bypass switch to the normal position, the ONOP has a step to verify the pump is not rotating. If the pump was rotating upon restart it would possibly:
a ~
b.
C.
d.
not come up to full speed.
not start at all.
trip on overspeed.
cause damage to the governor.
[1.00]
18.
Procedure 2-EOP-10, Station Blackout, requires the operator to shut the RCP bleed-off isolation valves (V2505 L V2524).
Other than losing RCS inventory, what would be the consequence of leaving these valves open?
'a ~
b.
c ~
d.
Seal leakoff could fill the VCT.
Bleedoff system relief may be challenged.
quench tank rupture disk could blow.
Flashing may occur in the bleedoff line.
[1.00]
19.
Unit 1 has tripped from 100% due to a loss of off-site power with subsequent failure of the Diesel Generators to start.
The operating crew has entered EOP-10 (Blackout).
The basic strategy of EOP-10 is:
a
~
b.
C.
Establish, maintain, and verify natural circulation conditions in the RCS.
Conserve CST inventory per EOP-99, Figures 3 and 4.
Cooldown, due to loss of CCW and seal injection to the RCP seals.
d.
Allow the RCS to heat up to a maximum of 542 Tave to ensure pressurizer level is maintaine Licensed 0 erator Re ual SRO NRG 0 en Reference Exam 20.
Of the following D/G indications on RTGB, which one would indicate that the D/G might NOl be ready to start?
a.
Governor Yellow light on.
b.
Green light on output breaker.
c.
Green light on voltage regulator control.
d.
Start-stop control Yellow light on.
[1.00]
21.
Which one of the following is the approximate time to reach boiling conditions after shutdown cooling is lost five days after shutdown on Unit 1, with the RCS at mid-loop and an initial temperature of 130 'F, and at atmospheric pressure?
a.
10 minutes b.
15 minutes c.
20 minutes d.
25 minutes
Licensed 0 erator Re ual SRO NRC 0 en Reference Exam
[1.00]
22.
Unit 2 has been shutdown for 28 days and is in Mode 5 with nozzle dams being installed in both SGs.
2A and 2B Shutdown Cooling System (SDC) loops were in service but have been secured due to loss of RCS level.
Operators are unsuccessful in stopping the leak.
ONOP 2-0440030 is being implemented with the following plant conditions:
2A Charging pump has been started to restore RCS level.
RCS level is 29 ft.
2 in.
and slowly increasing 2A and 2B SGs are in wet lay-up SDC temperature is 120f and stable Containment integrity exists Which one of the following would be used for RCS heat removal?
a.
boil off b.
SGs in the natural circulation mode.
c.
SDC when RCS level is above 29 ft. 6 in.
d.
once thru cooling mode
[1.00]
23.
During a gaseous release from the A Gas Decay Tank the RCO acknowledges a High Alarm on the Gaseous Effluent Honitor, which one of the following best describes his actions?
'a ~
b.
notify chemistry to take a backup sample of the GDT.
verify oxygen concentration is within Tech.
Spec.
limits.
c ~
d.
ensure that HVE-10A or HVE-10B is running.
verify the gaseous waste isolation valve (V6565) is shu Licensed 0 erator Re ual SRO NRC 0 en Reference Exam
[1.00]
24.
During an event where harsh environment conditions exist, Reg.
Guide 1.97 designated instruments should be used for diagnosis of events and confirmation of safety functions...
Which one of the following describes how this instrumentation is identified?
'a ~
b.
C.
d.
Instrument tags on the RTGBs have 1.97 related information stamped into them.
Black bezels surround the instruments to help in identifying type and category.
The Eg lists provided in the control rooms, contain all instruments that meet this requirement.
White bezels surround the instruments that meet the specifications of the Reg.
Guide.
25.
If one safety valve on 2A SG is gagged and two safety valves on 2B SG are gagged, then Reactor power:
a.
Must be reduced to ~ 66.3%
b.
Hust be reduced to g 79.6%
c.
Nust be reduced to g 88.2%
d.
Nust be reduced to g 92.8%
Licensed 0 erator Re ual SRO NRC 0 en Reference Exam
[1.00]
26.
At Unit 2, while withdrawing Group 5 to ARO during power ascension (power = 30%),.two of the Group 5 CEAs drop to the bottom.
The last measured F,'is 1.60.
Which of the actions listed below is the most appropriate'
'a ~
b.
Realign both CEAs to < 7" deviation within the tiofe limits of Technical Specification, Fig. 3. l-la.
Be in HOT STANDBY within one hour.
C.
d.
Determine from symptoms and CEA position indications the operability of the CEA per appendix B.
Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
[1.00]
27.
Under what circumstances would an Owner Controlled Area evacuation be required?
a
~
b.
c ~
d.
Any time the Emergency Coordinator classifies an event and implements the Emergency Plan.
During a Site Area or General Emergency, or if the Emergency Coordinator deems it necessary.
Only during an event where two of the three fission product barriers have been breached.
At the request of the state Emergency Management facility anytime an emergency is declare Licensed 0 erator Re ual SRO NRC 0 en Reference Exam
[1.00]
28.
If the Emergency Condition is an Alert, Site Area
, or General, the NPS should transfer the emergency duties to; a
~
b.
C.
the Recovery Manager designate the site Vice President, Plant Manager, or Operati'ons Manager the Emergency Control Officer or Nuclear Energy Duty Officer d.
the Plant Manager, Operations Manager or Operations Supervisor
[1.00]
29.
According to AP 0010120,
"Duties and Responsibilities of Operators on Shift", which one of the following is an acceptable set of circumstances for manually initiating AFAS?
b.
c ~
d.
A loss of all main feedwater occurred at 100% power resulting low SG level reactor trip.
Three minutes post trip both SGs are approaching 30%
WR level.
A loss of offsite power had occurred from 100% power and one DG failed to start.
Five minutes later a
manual start was attempted and was successful.
A reactor trip has occurred and an ESDE is in progress.
Both HSIVs were closed and when AFAS initiated only the 'B'ide components actuated.
A normal reactor plant shutdown has occurred for refueling.
Main feedwater and the 15% bypass valves are no longer useful and AFW is desire Licensed 0 erator Re ual SRO NRC 0 en Reference Exam
[1.00]
30.
Which ONE of the following conditions would require the use of AP 0010124 "Control and Use of Jumpers and Disconnected Leads" ?
a.
Replacing Sigmas with the new digital displays on RTGB 206 IAW the PCH package.
b.
C.
d.
A temporary cable is installed on a receptacle to operate a welding machine.
I&C technicians, while troubleshooting, connect a hand held digital Fluke to two terminals.
Temporarily bypassing the Overspeed Protection Circuit in the DEH compute WRITTEN EXAMINATION LOR TRAINING PROGRAM NRC EXAM NO. 0820259S AUTHOR: D. Carpenter DATE: ll/17/92 ANSWER KEY 1.
c.
REF:
0802999 2.
b.
(SRO)
REF:
0802810 3.
d.
REF'802825 4:
a.
REF:
0802999 5.
b.
REF:
0702827 6.
b.
REF:
0702835 7.
b.
REF:
0802999 8.
a.
REF:
0802999 9.
c.
REF'802999 10.
b.
REF:
0702502 ll.
b.
REF:
0702504 12.
a.
REF:
0702205 13.
b.
REF:
0702405 14.
a.
REF:
0702403 15.
a.
REF:
0702404 16.
c.
REF:
0702412 17.
c.
REF:
0702412 18.
a.
REF:
0702202 19.
a.
REF:
0702209 20.
c.
REF:
07020501 21.
REF:
22..
REF:
23.
REF:
24.
REF:
25.
REF:
26.
REF:
27.
REF:
28.
REF:
29.
REF:
30.
REF:
c.
0702207 c.
0702207 d.
0702410 d.
0702834 b.
0802810 b.
0802810 b.
(SRO)
0702833 d.
(SRO)
0702833 b.
0802424 d.
0802424
WRITTEN EXAMINATION A~s Ae- /Pe'quWZ
$4. L
~.m 9'-9~
NAME:
DATE:
SSN/CD:
LOR TRAINING PROGRAM NRC EXAM NO. 0820258S AUTHOR:
D. Carpenter REVIEWED BY:
DATE: 11/1'8/92 DATE:
GRADE:
INSTRUCTIONS 1.
WRITE YOUR ANSWERS ON THE ANSWER SHEET PROVIDED, fill in your choices with a number ¹2 pencil.
2.
Point value for each question appears in parentheses.
3.
There are
points on this exam.
4.
Do not talk to anyone but the examiner during the examination unless otherwise directed.
5.
Do not transmit or receive any information, material or other communication to anyone but the examiner during the examination unless otherwise directed.
6.
Do not allow access to your examination by anyone but the examiner during the examination.
Do not seek access to any other individual's examination or materials.
7.
Do not leave the examination area without the approval of the examiner.
8.
Any evidence of cheating detected by the examiner is grounds for dismissal from the examination.
9.
SIGN AFTER YOU HAVE FINISHED EXAM:
I have neither given nor received any assistance in completing this exam.
SIGNATURE DATE
Licensed 0 erator Re ual SRO NRC Static Simulator Exam
[1.00]
Based on the current plant conditions, which one of the following is correct concerning AFAS 1 and 2?
a
~
AFAS 1 is timing out to actuation, AFAS 2 is not needed at this time.
b.
c ~
AFAS 1 has occurred and reset on level, AFAS 2 is precluded due to rupture logic.
AFAS 1 is precluded due to rupture logic, AFAS 2 is not needed at this time.
d.
AFAS 1 is not needed at this time, AFAS 2 is precluded due to rupture logic.
[1.00]
2.
HSIS has occurred on channel B.
The B HSIV did not close.
Which one of the following is the correct method to close the HSIV?
'a ~
b.
C.
Locally isolate instrument air and break the NSIV pressure switch tubing.
Manually initiate channel A HSIS on RTGB 206.
Locally isolate instrument air and open the accumulator drain valve.
d.
Remove the B MSIV control power fuses inside RTGB 206.
[1.00]
If during the downpower the operators forgot to transfer to the start-up transformers and opened the OCBs prior to tripping the turbine or the reactor what would the electrical line-up be now.
'a ~
b.
C.
The diesels would be carrying the vital busses.
Off-site power would be from the start-ups.
A blackout would have occurred.
d.
Off-site power would be from the auxiliarie Licensed 0 erator Re ual SRO NRC Static Simulator Exam
[l.00]
4.
Given the current plant configuration, which one of the following is correct concerning the Emergency Diesel Generator operations?
a ~
b.
C.
d.
If a LOOP occurred now, it would disable all but two (2) of the DG trips.
To increase DG output frequency, position the DG governor to raise.
The DGs are running in the isochronous mode with the output breakers open.
Depressing the Emergency Shutdown on RTGB 201 will shutdown the DG.
[1.00]
5.
Which ONE of the following statements describes the reason that all of the Pressurizer Safety Valve discharge line temperature indications, TIA 1107. (V-1200), TIA 1108 (V-1201),
TIA 1109 (1202)
and both PORV discharge line temperature indications, TIA 1106 and TIA 1110 are reading high?
'a ~
b.
C.
d.
The instruments have failed high due to the harsh environment inside the Containment during a
LOCA.
Pressurizer Pressure exceeded the lift setpoint of the Pressurizer Safeties and the PORV's when the Reactor and Turbine tripped.
The discharge lines have a
common discharge into the quench Tank.
The temperature indications reflect the conditions in the common discharge header.
All of the Pressurizer Safeties and PORV's are leaking by because of the increased D/P across the valves when the quench Tank rupture disc blew ou Licensed 0 erator Re ual SRO NRC Static Simulator Exam
[1.00]
6.
If the crew is successful in getting the B HSIV closed at this point, which one of the following would be the appropriate actions to take?
a ~
Exit 2-EOP-15 and enter 2-EOP-03, LOCA, since the ESDE has been terminated.
b.
C.
Exit 2-EOP-15 and enter 2-EOP-01 for re-diagnosis of plant conditions.
Remain in 2-EOP-15 until all SFSC acceptance criteria are satisfied.
d.
Remain in 2-EOP-15 until Pzr level and RCS subcooling are recovered.
[1.00]
7.
Which one of the following best describes how this event could result in a Pressurized Thermal Shock scenario if the RCS leak were not present?
a
~
Charging pumps overpressurize the RCS because of the high pressurizer level caused by a reactor vessel head void.
b.
C.
d.
Addition of RCS inventory by charging and HPSI pumps and the RCS heatup resulting from dryout of the affected S/G results in excessive RCS pressure.
Cooldown exceeding Tech Spec limits results in brittle fracture of the most limiting RCS components.
High containment pressure and temperature as a result of the ESDE has the potential for causing PTS of the steel containment vesse Licensed 0 erator Re ual SRO NRC Static Simulator Exam
[1.00]
8.
Based on this event the correct classification is:
a ~
Unusual Event b.
Alert C.
d.
Site Area Emergency General Emergency
[1.00]
The limiting case conditions for the impact of this event on Shutdown Margin are:
'a ~
b.
c ~
d.
BOC and 100% power.
BOC and Hot Standby.
EOC and 100% power.
EOC and Hot Standb Licensed 0 erator Re ual SRO NRC Static Simulator Exam QUESTlONS 10 THROUGH 15 ARE NOT STATIC SIMULATOR RELATED
Licensed 0 erator Re ual SRO NRC Static Simulator Exam
[1.00]
10.
RAS closes V3659 and V3495, HPSI recirc isolation valves.
Which one of the following statements best describes why these valves are closed on RAS?
'a ~
b.
c ~
To ensure adequate injection flowto the RCS from the remaining ECCS pumps.
To ensure the NPSH of the HPSI pumps are maintained during the recirc phase.
To prevent an unmonitored release to the environment from the RWT vent.
d.
To prevent corrosive, high temperature water damaging the RWT liner.
[1. 00]
ll.
The NPO checks the auxiliary feedwater pumps every shift for
"steam binding". Choose the correct flow path that would likely cause
"steam binding" on Unit 2.
a
b.
C.
d.
One check valve, one HOV leak by.
One check valve, one HOV, one solenoid valve leak by.
Two check valves, one HOV leak by.
Two check valves, one HOV, one solenoid valve leak by.
[1.00]
12.
The Unit 2 Containment Isolation Honitors indicate radioactivity inside the containment, and are used for the Containment Isolation Actuation Signal.
(Choose the response which best completes this statement).
a ~
b.
c ~
d.
general area beta/gamma particulate, gaseous, and iodine new fuel alpha N16 gamma
Licensed 0 erator Re ual SRO NRC Static Simulator Exam
[1.00]
13.
An RCP oil reservoir level indication PCM was recently installed on Unit 2 to increase reliability of the indication.
One disadvantage of this modification is; a ~
b.
C.
d.
The new power supply is from a non-vital source.
High and low level alarms are no longer operational.
Indicator response time may be delayed for up to
seconds.
Reservoir level indication is lost on a CIAS.
[1.00]
14.
The sample line to the 'B'CW Radiation Monitor has isolated due to a spurious low pressure signal which has closed the solenoid isolation valve I-SE-26-2.
When the signal is cleared, how can the solenoid valve be re-opened?
a ~
b.
c ~
d.
Push the reset button on the radiation monitoring panel in the Unit 2 control room.
The valve will automatically stroke open when the low pressure signal clears.
Take the solenoid valve open/close switch on RTGB 206 to CLOSE-OVERRIDE, then to OPEN.
Send an operator to the CCW building to locally open the solenoid valv Licensed 0 erator Re ual SRO NRC Static Simulator Exam
[1.007 15.
Which one of the following statements is most correct concerning the SG tube rupture event?
'a 0 b.
c ~
d.
No relationship exists between this event and the Tech Spec requirements for RCS leakage.
Types of SGTR events are based on the ability of the PPLCS to maintain pressurizer pressure.
Stress Corrosion Cracking has been identified as a
cause of SG tube failures in the industry.
The core heat removal safety function is severely impacted by this even WRITTEN EXAHINATION LOR TRAINING PROGRAM NRG EXAM NO. 0820258S AUTHOR:
D. Carpenter DATE: ll/18/92 ANSWER KEY 1.
d.
REF:
0702412 2.
a.
REF:
0702401 3.
a.
REF:
0702502 4.
c.
REF:
0702501 5.
c.
REF:
0702206 6.
c.
REF:
0802999 7.
b.
REF:
0802999 8.
c.
(SRO)
REF:
0702833 9.
d.
(SRO)
REF:
0802810 10.
c.
REF:
0702401 ll.
d.
REF'702412 12.
a.
REF:
0702411 13.
d.
REF:
0802424 14.
a.
REF:
0702835 15.
c.
REF:
0702825