ML20057B848
| ML20057B848 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 09/14/1993 |
| From: | Bielby M, Jordan M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20057B837 | List: |
| References | |
| 50-440-OL-93-02, 50-440-OL-93-2, NUDOCS 9309240063 | |
| Download: ML20057B848 (100) | |
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U. S. NUCLEAR REGULATORY COMMISSION t
REGION III Report No. 50-440/0L-93-02 t
Doclet No. 50-440 License No. NPF-58 i
Licensee: The Cleveland Electric Illuminating Company 10 Center Road Perry, OH 44081 j
Facility Name:
Perry Nuclear Power Station Examination Administered At:
Perry Nuclear Power Station i
Perry, OH i
i Examination Conducted: Week of August 9,1993 Examiners:
Colin Carroll, Sonalysts, Inc.
Chief Examiner:
h
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9h(/f3 ti. E. Bi el by, S~r.
Date Approved By:
CL h
M. J. Jordan, Chief Date Operator Licensing Section 1 Examination Summary Examination administered durina the week of Auoust 9. 1993 (Report No. 50-440/0L-93-02) j Written and operating Reactor Operator (RO) initial license examinations were administered to three non-licensed operators.
Examinations were administered i
in accordance with guidelines of NUREG 1021, Operator Licensing Examiner l
Standards, Revision 7.
1 Results: All individuals successfully passed all sections of their respective examinations and will be issued operator licenses.
The following is a summary of strengths and weaknesses noted during performance of this examination:
1 9309240063 930917 PDR ADOCK 05000440 V
PDR_
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1 Examination Summary 2
Strenaths:
Pre examination review of the written examination (Section 3.a.).
o e
Teamwork during dynamic scenarios (Section 3.c.).
Simulator modeling and operation (Section 5).
Weaknesses:
Knowledge of system operation for the Diesel Generator (DG) ventilation e
system, the Emergency Response Information System (ERIS) having faulted data, and useable Reactor Pressure Vessel (RPV) level indication during an event (Section 3.a.).
Knowledge of administrative procedures (Section 3.b.).
e Communications (Section 3.c.).
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Examination Summary 2
1 Strenoths:
Pre examination review of the written examination (Section 3.a.).
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Teamwork during dynamic scenarios (Section 3.c.).
Simulator modeling and operation (Section 5).
Weaknesses-Knowledge of system operation for the Diesel Generator (DG) ventilation system, the Emergency Response Information System (ERIS) having faulted data, and useable Reactor Pressure Vcssel (RPV) level indication during an event (Section 3.a.).
Knowledge of administrative procedures (Section 3.b.).
Communications (Section 3.c.).
3 REPORT DETAILS 1.
Examiners 4M. Bielby, Chief Examiner, Rill NRC C. Carroll, Examiner, Sonalysts, Inc.
2.
Persons Contacted Facility
+M. Bezilla, Operations Manager
+M. Wesley, Training Manager
+D. Bauguess, License Training Instructor 4L. Burgwald, Training Instructor
+J. McHugh, Training Coordinator
+J. Messina, Operations Staff Supervisor
+B.
Panfil, Simulator lead 4C. Persson, OTU Supervisor
+L. Routzahn, Licensing
+R. Schrauder, Director-PNSD U. S. Nuclear Regulatory Commission (NRCl A. Vegel, Resident inspector, Perry 4E. Plettner, RIII, BWR Operator Licensing
+ Denotes presence at the exit meeting on August 12, 1993.
3.
Initial License Training Program Observations The initial license training program appears to be functioning well as evidenced by the 100% pass rate.
Training department personnel were responsive to needs of license candidates and in assisting the NRC in developing this examination.
Training reference material submitted to the NRC appears to be well maintained.
All books were properly tabbed, labeled and indexed as detailed in Enclosure 1 of the NRC's 120 day notification letter to the facility.
The following infomation is provided for evaluatiori by the licensee via their SAT based training program.
No response is required.
a.
Written Examination l
The initial license written examination was a standard 100 point, multiple choice and matching question format, as prescribed by NUREG 1021, Revision 7.
1
Strenaths Training and operations personnel did a good pre exam review. The review alleviated inappropriate wording and terminology, and identified questions with more than one correct answer or no correct answer. As a result, there were no post exam comments by the facility.
Weaknesses Grading of the examination revealed three generic e
weaknesses. All three operators selected the same distractor, and failed to correctly identify:
1.
the failed position of the outside and recirculation dampers in the Diesel Generator (DG) building ventilation room A on a loss of essential 120 volt power. All three operators chose distractor b.,
outside dampers fail open and recirculation dampers fail closed. The correct answer was c., outside dampers fail closed, recirculation dampers fail open.
Reference ONI R25-1, Rev.2, page 7; Lesson Plan OT-3036-M43 Learning Objective F, Rev. 8/19/87.
2.
the color of the asterisk in the value box of Emergency Response Information System (ERIS) when there is insufficient room for good data. All three operators chose distractor a.,
cyan.
The correct answer was b., white.
Reference Perry SDM C95, Rev.
O, page 8; Lesson Plan OT-3036-C95-00 Learning Objective C.2, Rev. 1/22/88.
3.
all of the reactor pressure vessel (RPV) level instruments which would be providing valid level indication given a set of pressure / temperature parameters and the E0Ps. All three operators chose distractor d., wide ranges. The correct answer was b., shutdown and wide ranges.
Reference PEI-B13, Rev.
4/15/92; PEl-SPI Figure's la (Rev. 2), 2a (Rev. 2), 2b (Rev. 2), and 2c (Rev. 2); Lesson Plan OT-3402-07 Learning Objective C.
b.
Job Performance Measures (JPMs)
All operators were determined to be satisfactory in this area.
The JPMs performed in the simulator / control room were:
1.
Control Rod Drive Coupling Check 2
2.
Manually Initiate Containment Spray, Logic Inoperable (Faulted) 3.
Manually Initiate High Pressure Core Spray (HPCS), Logic Inoperable 4.
Startup Control Room Heating Ventilation Air Conditioning (HVAC) 5.
Deenergize Alternate Rod Insertion Valves 6.
Isolate a Recirculation Loop The JPMs performed in the plant room were:
i 1.
Condensate Alternate Injection 2.
Residual Heat Removal (RHR) Loop B Containment Flooding 3.
Transfer EHII to Diesel Generator and Parallel to Grid 4.
Vent the Reactor Pressure Vessel Using Main Steam Line Strenaths Operators were knowledgeable of plant equipment location and e
operation.
Simulator control board manipulations were quick i
l and accurate.
Operators were able to promptly retrieve and execute correct e
operating procedures in all instances.
Operators demonstrated familiarity with Off Normal Instructions (ONIs), Alarm Response Instructions (ARIs) and l
administrative procedures when responding to the alternate path (faulted) JPM.
Weaknesses l
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Operators were not familiar with the permanent key checkout form.
Specifically, who can authorize the checkout and/or where the forms are located.
e Operators were not familiar with the location or procedure for using the NRC Emergency Notification System (ENS) l phones.
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c.
Dynamic Simulator Scenarios All individuals were graded as satisfactory in the dynamic simulator scenarios. Three scenarios were written and administered in one day. A surrogate licensed senior reactor i
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operator was used in the shift supervisor position to complete the three member crew in all three scenarios.
Scenario 1 included a 1) reactivity manipulation using recirculation, 2) Startup Emergency Service Water (ESW)
"B" pump,
- 3) ESW pump amp meter downscale failure, 4) Average Power Range l
Monitor (APRM) downscale failure, 5) recirculation jet pump failure, 6) ESW pump shaft seizure, 7) fire in MCC/480 VAC Bus, 8) i loss of feedwater with Anticipated Transient Without Scram (ATWS) l and Standby Liquid Control (SLC) pump failure.
Scenario 2 included a 1) reactivity manipulation using recirculation pumps, 2) normal surveillance on the Main Turbine Bypass Valves, 3) inadvertent Safety Relief Valve (SRV) opening,
- 4) loss of APRM detector, 5) loss of display control system, 6) l inadvertent Reactor Core Isolation Cooling (RCIC) initiation, 7) i main turbine trip, RHR "A" pump and ESW "B" pump failure, 9) loss of Reactor Pressure Vessel (RPV) level indication.
Scenario 3 included a 1) reactivity manipulation by rod insertion, 1
- 2) startup CRD pump, 3) RCIC rupture diaphragm failure, 4) CRD pump shaft seizure, 5) SRV leaking, 6) full core display failure,
- 7) hydraulic lock ATWS.
Strenaths Two training instructors were allocated to run the scenarios. During major transients the operators needed to make multiple notifications to various departments. The use l
of two instructors enhanced the examination process because they were able to handle the large number of communications, provide timely feedback to the operators and run the simulator.
Crew members exhibited good teamwork. After individuals completed respective event response actions, they would consistently inform the shift supervisor (SS) they were free to assist in performing other actions.
When responding to alarms the opposite operator would break out the Alarm Response Instruction (ARI) to verify immediate and subsequent actions were performed.
Weaknesses Crew members did not always exhibit good communications.
Repeat-backs were inconsistent.
They were performed during normal situations, but either neglected or incomplete during emergency conditions.
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4.
Doerations. Security. Radiation Protection. Other e
Operations, security and radiation protection personnel were cooperative and professional when dealing with the examination team.
Plant and control room entrance and exits were made in a timely manner with a minimum of delays.
e During entrance into the personnel elevator outside of the RCA, examiners noticed a pair of cable supports directly over the elevator doors that were not bolted to the wall.
Work on the supports appeared to be recent and completed.
The item was turned over to the resident for followup.
5.
Simulator Observations e
The simulator performed well throughout the examination.
It did not halt or give erroneous indications during the ATWS and RPV flood transient conditions.
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The simulator setup contributes realism to training by incorporating a limited number of functioning backpanels which allow operators to actually install jumpers and lift leads required for bypassing isolations or initiation signals during execution of the E0Ps.
Expected results of these actions are modeled by the simulator.
e One discrepancy was noted during the examination and is listed in.
This discrepancy was not previously identified by the facility.
6.
Exit Meetina An exit meeting with Perry Nuclear Station management on August 12, 1993. Those attending the management meeting are listed in Section 2 of this report. The following items were discussed during the exit meeting:
e Strengths and weaknesses noted in this report.
e The general observations relating to the plant noted in Section 4.
The facility licensee did not identify as proprietary any of the materials provided to or reviewed by the examiners during the inspection.
5
. SIMULATION FACIllTY REPORT Facility Licensee:
Cleveland Electric illuminating Company (Perry Nuclear Power Station)
Facility Licensee Docket No.
50-440 Operating Tests Administered: Auguct 9 - 12, 1993 The following document observations made by the NRC examination team during the August 1993, initial examination.
These observations do not constitute.
audit or inspection findings and are not, without further verification and review, indicative of non-compliance with 10 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 in response to these observations.
During the conduct of the simulator portion of the operating tests, the following item was observed:
ITEM DESCRIPTION Turbine Control Valve During a surveillance to cycle TCVs, it (lCV) meter indication was noted that the meter indication would indicate slightly negative, vice positive, when opening the valves.
U.
S. NUCLEAR REGULATORY COMMISSION l
SITE SPECIFIC EXAMINATION REACTOR OPERATOR LICENSE REGION 3
1 CANDIDATE'S NAME:
FACILITY:
Perry REACTOR TYPE:
GEBWR6 i
i DATE ADMINISTERED:93/08/09 INSTRUCTIONS TO CANDIDATE:
l
\\' Use the answer sheets provided to document your answers.
Staple this cover i sheet on top of the answer sheets.
Points for each question are indicated in
' parentheses after the question.
The passing grade requires a final grade of at least 80%.
Examination papers will be picked up four (4) hours after the examination starts.
I CANDIDATE'S SCORE TEST VALUE 100.00%
TOTALS l
FINAL GRADE l
lAllworkdoneonthisexaminationismyown.
I have neither given nor l received aid.
Candidate's Signature l
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MASTER COPY 1
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not l
received or given assistance in completing the examination.
This must be done after you complete the examination.
- 3. Restroom trips are to be limited and only one applicant at a time may leave.
You must avoid all contacts with anyone outside the examination i
room to avoid even the appearance or possibility of cheating.
- 4. Use black ink or dark pencil ONLY to facilitate legible reproductions.
5.
Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer sheet.
- 6. Mark your answers on the answer sheet provided.
USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 7. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.
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- 8. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect ansver.
Write it out.
- 9. The point value for each question is inoicated in parentheses after the question.
- 10. Show all calculations, methods, or assumptions used to obtain an answer to l
any short answer questions,
- 11. Partial credit may be given except on multiple choice questions.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 12. Proportional grading will be applied.
Any additional wrong information that is provided may count against you.
For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points.
If one of your five responses is incorrect, 0.20 will be i
deducted and your total credit for that question will be 0.6D instead of 1.00 even though you got the four correct answers.
- 13. If the intent of a question is unclear, ask questions of the examiner only.
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- 16. When turning in your examinatio:,, assemble the completed examination with examination questions, examination aids and answer sheets.
In addition, turn in all scrap paper.
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- 15. Ensure all information you wish to have evaluated as part of your answer is on your answer sheet.
Scrap paper will be disposed of immediately following the examination.
- 16. To pass the examination, you must achieve a grade of 80% or greater.
- 17. There is a time limit of four (4) hours for completion of the examination.
- 18. When you are done and have turned in your examination, leave the examination area (EXAMINER WILL DEFINE THE AREA).
If you are found in this area while the examination is still in progress, your license may be denied or revoked.
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I QUESTION: 001 (1.00)
During a plant transient from 100% rated thermal power, actual reactor water level decreases and remains near the top of the active fuel for several minutes prior to recovery.
Immediately prior to this transient, it was discovered that Narrow Range Level Transmitters LT-N095A and B had failed upscale.
All other instrumentation functioned properly.
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Which ONE of the following automatic functions will NOT have actuated as a result of the transient?
(Assume no operator actions.)
a.
Reactor Scram.
b.
Closure Signal to the Residual Heat Removal System Shutdown Cooling Mode Isolation Valves.
c.
Automatic Depressurization System actuation.
d.
Recirculation Pump downshift from fast to slow speed.
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QUESTION: 002 (2.00)
MATCHING Isolation valves for the Instrument Air System close to isolate Instrument Air from the Containment and Drywell. For the valves listed in column 1, MATCH the proper isolation signal from column 2 (Isolation signals in column 2 may be used once, more than once, or not at all)
(8 answers required at 0.25 each)
COLUMN 1 COLUMN 2 (Isolation Valve)
(Isolation Signal)
- a. Valve PS2-F200 Containment 1.
Drywell pressure, 2 psig Isolation
- b. Valve P52-F160 Containment 2.
Reactor Water Level, Level 2 Isolation (air lock)
- c. Valve P52-F170 Containment 3.
Drywell Pressure, 1.68 psig Isolation (air lock)
- d. Valve P52-F646 Drywell 4.
Reactor Water Level, Level 3 l
Outboard Isolation
- 5. Reactor Water Level, Level 1 6.
Instrument air receiver pressure, l
90 psig 7.
Instrument air receiver pressure, j
112 psig
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QUESTION: 003 (1.00)
Select the choice that completes the following.
The LPRM detector is coated with:
- a. only U-235 which results in a rapidly changing LPRM sensitivity over core life due to the rapid U-235 fission rate.
b.-only U-235 because the depletion rate of U-235 by fission is so slow that LPRM sensitivity slowly changes over core life.
- c. U-235 and U-234 because the transmutation of U-234 to U-235 compensates for the rapid depletion of U-235 by fission over core life.
- d. U-235 and U-234 because the depletion rate o; U-234 by fission compensates for the non-fissioning U-235 neutron absorption events.
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l QUESTION: 004 (1.00)
Regarding the Remote Shutdcwn System (C61), all Division I Remote Shutdown Transfer Switches (RSTS) are in their NORMAL position.
MSIV pilot solenoid "B" control switch is in the NORMAL position.
P Which ONE of the following describes the response of the inboard MSIVs if the operator takes MSIV pilot solenoid "A" control switch to the CLOSE position and the reason for this response?
- a. Inboard MSIVs remain open because control has not been transferred to the MSIV pilot solenoid control switches on the Remote Shutdown
- Panel, b.
Inboard MSIVs remain open because only the "A" pilot solenoids for the MSIVs de-energize.
c.
Inboard MSIVs close because the "A" pilot solenoids for the MSIVs de-energize.
d.
Inboard MSIVs close because this switch energizes one pilot solenoid for each MSIV with 125 VDC power.
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REACTOR OPERATOR Page 8
QUESTION: 005 (1.00)
[
t Essential 120 volt bus EK-1-Al is lost. Diesel Generator Building Ventilation Room A outside air dampers (1M43-F020A and 1M43-F220A) fail 1
_ and Diesel Generator Building Ventilation Recirculation dampers (IM43-F030A, 1M43-F031A, 1M43-F230A and 1M43-F231A) fail 2
(1)
(2)
- a. OPEN OPEN
- b. OPEN CLOSED
- c. CIDSED OPEN d.
CLOSED CLOSED l
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QUESTION: 006 (1.00)
Integrated Operating Instruction, IOI-3 " Power Changes" specifies reactor power shall not exceed 100% steady state over an eight (8) hour period.
However, exceeding 100% power is permitted for short periods of time.
Which ONE of the following is the length of time power is permitted to be at 102%.
- a. NEVER b.
15 minutes
- c. 30 minutes d.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> l
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REACTOR OPERATOR Page 10 QUESTION: 007 (1.00)
Select'the choice that completes the following statement.
A 1
tag is placed on a circuit breaker to warn operatiens representatives that one or more ground devices have been placed on the circuit and are always used with a 2
tag in accordance with the tagging procedure.
1 2
a.
White Yellow b.
White Red c.
Yellow White d.
Yellow Red i
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l QUESTION: 008 (1.00)
Which ONE of the following terms'is used to describe a sliding link that has been opened?
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- a. A temporary Control Device.
- b. Lifted lead.
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- c. Maintenance Safety Block.
- d. Jumper, j
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F' REACTOR OPERATOR Page 12 QUESTION: 009 (1.00)
Which ONE of the following is defined as the process of injecting a simulated signal as close to the sensor as practicable for an analog channel to verify operability of alarm and/or trip functions and channel failure trips?
a.
Channel Check b.
Channel Calibration c.
Channel Functional Test
- d. Channel Maintenance Test 1
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I QUESTION: 010 (1.00)
A RHR LOCA signal has been received.
The Annulus Exhaust Gas Treatment l
System (AEGTS) has responded correctly.
The operator then places the AEGTS Train "B" fan switch to the STOP position, then returns the switch to the STANDBY position.
Which ONE of the following describes the response of AEGTS Train "B" fan?
- a. The fan remains in standby readiness and will automatically start on a low dp across AEGTS fan "A".
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- b. The fan stops, returns to standby readiness, and will automatically start if the LOCA initiation condition (s) clear and then are received again.
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- c. The fan remains running because the LOCA initiation signal cannot be overridden by the STOP or STANDBY position of the control switch,
- d. The fan stops, but then restarts because the manual override of the LOCA signal is only active when the control switch is in STOP.
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QUESTION: 011 (1.00)
[
A Station Blackout has occurred while the plant is shutdown in Operational Condition 4.
Division 2 DG automatically started but tripped 5 minutes later due to a faulty lube oil temperature switch.
Shift Supervisor directs the Supervising Operator to perforn " Override of Division 2 Diesel Generator non-LOCA Trips" per.SOI-R43.
Which ONE of the following describes the Division 2 Diesel Generator trip (s) which are NOT overridden?
- a. Generator overcurrent, generator reverse power, DG trip crankcase pressure high, DG overspeed.
- b. Generate overcurrent, generator reverse power, DG trip vibration high, DG trip lube oil pressure low.
c.
Generator overcurrent, generator reverse power, DG trip differential relay lockout, DG trip overspued.
- d. Generator overcurrent, DG trip turbo oil pressure low, DG trip engine bearing temperature high, DG trip overspeed.
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QUESTION: 012 (1.00)
A refuel outage is in progress. A licensed operator is returning to Day Shift
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Control Room duties from days off and will be working the following schedule for the week? (schedule excludes turnover time)
DAY HOURS i
i Saturday 0700 - 2200 i
Sunday 0700 - 1500 Monday 0700 - 1900 Tuesday 0700 - 1900 Wednesday 0700 - 2000 Thursday 0700 - 1800 Friday OFF Which ONE of the following describes the overtime guidelines that will be t
exceeded according to PAP 0110 " Shift Staffing and Overtime" a.
The guideline of no more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
b.
The guideline of no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period.
c.
The guideline of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7 day period.
d.
The guideline requiring at least an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> break between work periods.
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i REACTOR OPERATOR Page 16 QUESTION: 013 (1.00) t i
An operator is entering a high radiation area to perform a valve lineup.
The general area radiation level is 250 millirem per hour.
The following information is available on the operator's exposure history.
No special approvals have been given.
The operator is a qualified male radiation worker.
NRC-4 form is complete and on file.
i Current calendar quarter exposure:
250 mrom i
Current calendar year exposure:
750 mrem i
Lifetime exposure:
35.5 REM Operator's age:
36 years Which ONE of.the following is the MAXIMUM ALLOWABLE STAY TIME in this area before the most restrictive administrative or NRC limit is exceeded?
a.
I hr.
b.
2 hr.
j c.
3 hr.
{
d.
5 hr.
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REACTOR OPERATOR Page 17 QUESTION: 014 (1.00)
While observing the ERIS System, it is noted that a data box is indicated in YELLOW.
Which ONE of the following describes the status of this information?
a.
A safety action has been demanded and failed.
b.
The data has exceeded its maximum safe value.
c.
A safety related limit is being approached.
d.
The data inputs have failed.
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REACTOR OPERATOR Page 18 QUESTION: 015 (1.00)
Which ONE of the following areas may be entered WITHOUT the issuance of a RWP?
- a. Access to normally inaccessible pipe chases within the RRA.
- b. Containment Building.
- c. A neutron area with dose rates of 1 nrem per hour.
- d. Routine operator access to High Radiation areas for rounds.
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i REACTOR OPERATOR Page 19 QUESTION: 016 (1.00)
Which ONE of the following describes the requirement that must be met for the Licensed Operator at the Controls to be temporarily relieved by another on-shift licensed operator for personal reasons?
- a. Only a verbal turnover of the plant status.
- b. A verbal turnover of plant status and the permission of the Shift Supervisor.
- c. Only the "SO Relief / Turnover Checklist" must be reviewed and signed by the on-shift operator,
- d. The on-shift operator must review and sign the "So Relief / Turnover Checklist" and sign into the Unit Log.
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QUESTION: 017 (1.00)
Select the choice that completes the following statement.
Refueling operations are in progress with the reactor cavity flooded, when l
the water level in the cavity begins to decrease due to a leak.
As the cavity level decreases, the level decrease will be indicated:
a.
immediately on the Wide Range Level indicator.
b.
immediately on the Upset Level recorder.
- c. on the Narrow Range Level recorder when level decreases to the top of the main steam lines.
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- d. on the Shutdown Level Indicator before level decreases to below the vessel flange.
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REACTOR OPERATOR Page 21 QUESTION: 018 (1.00)
]
Plant conditions are as follows:
1 Reactor is at 72% of rated power.
Core flow is 65%.
Reactor recirc loop "A" flow rate is 57% of rated loop flow.
Reactor recirc loop "B" flow rate is 71% of rated loop flow.
i Which ONE of the following describes the status of the mismatch between reactor recirc loop flow rates?
- a. NOT ACCEPTABLE; recirc mismatch is greater than 5% of rated recirc
- flow,
- b. NOT ACCEPTABLE; recirc mismatch is greater than 10% of rated recirc flow.
- c. Acceptable; recirc mismatch is less than 5% of rated recirc flow.
- d. Acceptable; recirc mismatch is less than 10% of rated recirc flow.
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QUESTION: 019 (1.00)
Which ONE of the following describes the plant response to an initiation of the "A" SLC system by placing the SLC Pump A keylock switch to the ON position?
- a. The "A" SLC pump will start, both squib valves will fire, and one reactor water cleanup isolation valve will close.
.and both reactor water cleanup isolation valves will close.
- c. The storage tank outlet valve (F001A) will open, the "A" SLC pump will start, it's associated squib valve will fire, and one reactor water cleanup isolation valve will close.
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- d. The storage tank outlet valve (F001A) will open, the "A" SLC pump will start, both squib valves will fire, and both reactor water cleanup isolation valves will close.
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i REACTOR OPERATOR Page 23 QUESTION: 020 (1.00)
The plant is at 100% power with the EHC Pressure Regulator A in operation when its output signal fails low.
Which ONE of the following describes the expected plant response if no operator action is taken?
a.
Control valves fully close and bypass valves fully open.
The Reactor scrams due to high neutron flux.
- b. Control valves fully open and bypass valves fully open.
Reactor pressure decreases until~an MSIV isolation occurs.
- c. Control valves could momentarily open slightly, and bypass valves remain closed. Reactor pressure stabilizes at approximately the same value as before the transient.
- d. Control valves could momentarily close slightly, and bypass valves remain closed. Reactor pressure stabilizes at approximately the same value as before the transient.
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REACTOR OPERATOR Page 24 i
QUESTION: 021 (1.00) 1 Perry is at 100% power when a complete loss of instrument air occurs.
.Which ONE of the following describes the expected valve response for the listed Feedwater/ Condensate System air operated valves?
- FAILS OPEN Hotwell Dump Valves
- FAIL OPEN
- b. MFP Low Flow Control Valve (IN27-F110)
- FAILS OPEN Hotwell Dump Valves
- FAIL OPEN
- FAILS AS IS Hotwell Dump Valves
- FAIL OPEN
- FAILS AS IS Hotwell Dump Valves
- FAIL CLOSED I
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REACTOR OPERATOR Page 25 i
QUESTION: 022 (1.00)
A signal has been generated that automatically closed 1G33-F004 (RWCU Outboard Isolation Valve).
1G33-F001 (RWCU Inboard Isolation Valve) remained j
open.
Which ONE of the following conditions caused the isolation?
i a.
Low reactor water level.
i
- b. A RWCU pump room high ambient temperature.
)
- c. SLC initiation, both pumps running.
j
- d. Non-regenerative heat exchanger high outlet temperature.
)
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REACTOR OPERATOR Page 26 QUESTION: 023 (1.00)
Which ONE of the following RCIC system valves will remain open i
following an automatic isolation signal from the RCIC system Isolation logic?
(Assume all the valves below were open prior to the
-isolation signal.)
I a.
1E51-F510 RCIC Turbine Trip Throttle Valve Latch.
b.
1E51-F076 RHR & RCIC Steam Supply Warmup Isolation.
d.
1E51-F031 RCIC Pump Suppression Pool Suction Isolation.
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REACTOR OPERATOR Page 27 QUESTION: 024 (1.00)
A spurious NS4 isolation has occurred. After resetting the isolation, the "A" RPS MG set trips and the alternate power supply is unavailable.
Which ONE of the following describes the status of the MSIV's and the Main Steam Line Drain valves?
- a. All MSIVs and main steam line drain valves are open.
- b. Inboard MSIVs and the outboard main steam line drain valves are open.
- c. Outboard MSIVs and the outboard main steam line drain valves are open.
- d. All MSIV's and the inboard Main Steam line drain valves are open.
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REACTOR OPERATOR Page 28 I
QUESTION: 025 (1. 00)
Which ONE of the following describes the response of the Fire Service Water system pumps to an inadvertent actuation of the i
deluge system for the main transformer.
- a. The diesel fire pump starts when fire header pressure is less than I
120 psig and the motor fire pump starts at 105 psig in the fire header.
- b. The motor fire pump is started by the receipt of the deluge l
initiation signal, and the diesel fire pump starts when fire header pressure is less than 105 psig.
I
- c. The motor and diesel fire pumps both start on receipt of the deluge initiation signal.
- d. The motor fire pump starts when fire header pressure is less than 120 psig, and the diesel fire pump starts when pressure is less than 105 psig.
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- REACTOR OPERATOR Page 29 j
2 QUESTION: 026
(,1. 00 )
Reactor Power is 60% as sensed by turbine 1st stage pressure.
While performing Main Turbine Stop valve testing, an operator inadvertently j
begins testing Turbine Stop valve "C" while Turbine Stop valve "B" is 50%
j open.
i Which ONE of the following describes the response of the Reactor Protection System to this event?
l
- a. Half scram on RPS A.
- b. Half scram on RPS B.
c.
Full Reactor Scram.
d.
Neither full nor half scram is generated, f
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i REACTOR OPER7sTOR Page 30 i
i QUESTION: 027 (1. 00) f All the required conditions have been met for an Automatic i
Depressurization AND RPV depressurization is in progress.
During depressurization ALL the low pressure ECCS pumps trip off.
[
Which ONE of the following describes how the Automatic Depressurization.
system is affected?
- a. Depressurization will stop and can be recommenced by depressing Channel A & B manual initiation pushbuttons
- b. Depressurization will stop and a low pressure ECCS pump must be restarted to recommence the depressurization
- c. Depressurization will stop and can only be reestablished by i
manually opening SRV's
- d. Automatic depressurization continues without interruption i
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REACTOR OPERATOR Page 31 QUESTION: 028 (1.00)
The reactor has scrammed from 100% power due to a loss of offsite
. power. The following conditions exist:
All emergency diesel generators started and tied to their respective emergency bus.
All low pressure ECCS pumps are running.
Reactor pressure is cycling with relief valve actuation.
The Reactor is shutdown.
Reactor water level is 186.5 inches, decreasing at 10 inches / min.
RCIC has isolated.
HPCS has tripped.
l Drywell pressure is 1.50 psig, increasing at 0.25 psig/ min.
J L
Which ONE of the following describes the response of the Automatic l
Depressurization System (ADS), if plant conditions remain as stated and no operator action is taken?
- a. ADS will automatically initiate in 2 minutes 36 seconds.
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- b. ADS will automatically initiate in 7 minutes 24 seconds.
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- c. ADS will automatically initiate in 17 minutes.
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- d. ADS will automatically initiate in 18 minutes 45 seconds.
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f REACTOR OPERATOR Page 32 QUESTION: 029
(,1. 0 0 )
The control switches for SRV F051G on Panels P601 and P631 have been selected to the OFF position.
Which of the following SRV mode (s) of operation are disabled?
a.
Low-Low Set and ADS.
- b. Relief and ADS.
- c. Relief only.
- d. ADS only.
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REACTOR OPERATOR Page 33 QUESTION: 030
(,1. 0 0)
Which ONE of the following signals from the Off-Gas Post-Treatment Radiation Monitoring System will initiate an AUTOMATIC ISOLATION of the Off-Gas Discharge to the main stack (N64-F632)?
- a. Hi-Hi trips on Channel A AND B.
- b. Hi-Hi trip on Channel A OR Hi-Hi trip on Channel B.
- c. Hi-Hi trip on Channel A AND Downscale trip on Channel B.
- d. Downscale trip on Channel A AND downscale trip on Channel B.
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' REACTOR OPERATOR Page 34 QUESTION: 031 (1.00) i Perry is at 100% power when a loss of feedwater event occurs causing reactor water level to decrease to 100 inches.
HPCS fails 1
to initiate, but RCIC automatically initiates and reactor water level slowly increases to Level 8.
+
Which ONE of the following describes the AUTOMATIC RCIC system response?
(NO operator action is taken.)
- a. RCIC isolates and the isolation must be manually reset when Level 8 clears.
- b. RCIC turbine trips and the turbine trip must be manually reset after the Level 8 clears.
- c. RCIC turbine trip signal is generated. The turbine trip will automatically clear at Level 2 decreasing.
- d. RCIC turbine steam supply (F045) valve shuts and the valve automatically reopens at Level 2 decreasing.
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REACTOR OPERATOR Page 35 QUESTION: 032 (1.00)
The Refuel platform is over the core and the HOIST LOADED indicator is NOT on, the Mode Switch is in Refuel and one control rod is selected and partially withdrawn.
Which ONE of the following conditions will prevent reverse motion of the i
Refuel platform?
t
- a. Selecting a different Control Rod.
b Loading the auxiliary platform hoist.
c.
Placing the Mode Switch in STARTUP.
D.
Refuel floor HI-HI Radiation trip.
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REACTOR OPERATOR-Page 36 QUESTION: 033
(,1. 0 0 )
Which ONE of the following is the preferred method of venting the containment to maintain primary containment pressure below the Primary Containment Pressure Limit?
- a. From the RHR Loop A Containment Spray Spargers to the Fuel Handling Building.
- b. Through the Combustible gas control system to the Fuel Handling Building.
- c. Though the Containment Purge system to the Fuel Handling Building.
- d. Through the Fuel storage, reactor well, and separator storage well skimmers to the fuel handling building.
i REACTOR OPERATOR Page 37 QUESTION: 034 (1.00)
While deliberately lowering water level to decrease reactor power during an ATWS the operator is directed to stop lowering level if certain conditions are met.
j Which ONE of the following is one of these conditions?
- a. Reactor power decreases to 4%.
- b. All SRV's are closed.
Drywell pressure decreases below 1.68 psig, c.
- d. Standby Liquid Control has been initiated.
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REACTOR OPERATOR Page 38 QUESTION: 035 (1. 00)
Concerning the Reactor Recirculation Pump se'11s, failure of only the inner (number 1) pump seal is indicated by an outer (number 2) seal pressure 1
and a(an) 2 in staging flow.
(1)
(2) a.
INCREASE INCREASE b.
INCREASE DECREASE c.
DECREASE INCREASE l
- d. DECREASE DECREASE 4
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REACTOR OPERATOR Page 39 i
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QUESTION: 036
(,1. 00) f SOI-M14, " Containment Vessel and Drywell Purge System," contains a precaution to ensure charcoal filter temperature remains below 300 degrees F.
Which ONE of the following describes the reason for this precaution?
a.
Prevents the airborne release of gaseous radioactive iodine, b.
Prevents automatic initiation of charcoal filter deluge system.
c.
Prevents humidity buildup in the charcoal filter, d.
Prevents spontaneous combustion of the charcoal filter.
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m REACTOR OPERATOR Page 40 F
QUESTION: 037
(,1. 00)
Select the choice below that completes the following.
Following the paralleling of the Division 1 Diesel Generator with its respective bus, Diesel Generator parameters are as follow:
Frequency 60 hz.
Voltage 4200 volts.
100 KVAR.
300 KW.
SOI-R43, Division 1 and 2 Diesel Generating Operating System, requires the operator to establish a lagging power factor.
If the operator places the generator voltage regulator to the increase position and the indicated KVARs decrease, the diesel generator's present power factor is and in order to establish a lagging power factor, the operator must a.
lagging; continue to increase the generator's output voltage
- b. lagging; decrease the generator's output voltage c.
leading; continue to increase the generator's output voltage d.
leading; decrease the generator's output voltage l
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s REACTOR OPERATOR Page 41 QUESTION: 038
(,1. 0 0 )
Which ONE of the following is indicated by the illumination of the white light above the Standby Diesel Generator's GOVERNOR CONTROL SWITCH?
- a. Governor control is at the local engine control panel only.
- b. Governor control is at the Control Room diesel control panel only.
- c. The governor is changing position to adjust diesel speed / frequency.
- d. The governor is changing position to adjust diesel generator KW load.
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Page 42 QUESTION: 039 (1.00)
Following an ATWS, SLC is initiated.
Which ONE of the following defines a condition by which the operator is allowed to consider the reactor shutdown and no further boron injection is necessary?
- a. 473 pounds mass of boron has been injected into the reactor vessel.
- b. 825 pounds mass of boron has been injected into the reactor vessel,
- c. All control rods are inserted except that 6 control rods are between positions 02 and 06.
- d. All control rods are inserted except that one control rod is fully withdrawn.
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REACTOR OPERATOR Page 43 QUESTION: 040
(,1. 0 0)
The following plant conditions exist:
Reactor power:
75%.
Reactor pressure:
985 psig steady Suppression pool temperature:
91 degrees F.
Suppression pool level:
18 feet 2 inches.
Inadvertently opens (Control Switch in AUTO)
Which ONE of the following is the required operator action?
- a. First, take the SRV control switch from AUTO to OFF; if the SRV remains open, then immediately remove the SRV solenoid control power fuses.
1 i
- b. First, take the SRV control switch from AUTO to OPEN, then back to l
AUTO.
If the SRV remains open, then immediately remove the SRV solenoid control power fuses.
- c. First, enter PEI-T23, Containment Control, and initiate suppression pool cooling, then commence lowering suppression pool level, then l
continue efforts to close the SRV.
- d. First, enter PEI-B13, RPV Control, and immediately initiate a reactor l
scram by placing the reactor mode switch to SHUTDOWN, then continue efforts to close the SRV.
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b REACTOR OPERATOR Page 44 QUESTION: 041
(,1. 00)
In accordance with SOI-E12, if Suppression Pool Clean Up is in operation through the Suppression Pool Return Line Bypassing RHR "A",
RHR "A" is NOT allowed to be running in the Test Mode or the i
- a. Minimum Flow Mode to prevent the loss of minimum flow to the RER pump.
- b. Minimum Flow Mode to prevent the loss of flow to the SPCU pump.
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- c. Suppression Pool Cooling Mode to prevent the loss of minimum flow to the RHR pump.
- d. Suppression Pool Cooling Mode to prevent the loss of flow to the SPCU pump.
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i REACTOR OPERATOR Page 45
+
QUESTION: 042 (1.00)
A fire occurred in the diesel generator room while operating the Division II diesel.
Division 2 DG was shutdown, diesel generator room CO2 initiated and 20 minutes later the Fire Brigade Leader reports the fire is out and requests that supply fans M43-C001B and 1M43-C002B be started to allow access to the room.
i
- Which ONE of the following actions is required in order to start the supply fans?
- a. Take the 1M43-C001B and 1M43-C002B control switches to the START position.
- b. Take the 1M43-C001B and 1M43-C002B control switches to OFF to reset the logic, and then back to ON.
- c. Depress the CO2 Initiate Override pushbutton, then start the 1M43-C001B and 1M43-C002B fans.
- d. Dispatch a PPO to the local disconnect to reset the supply fan breakers, then start the 1M43-C001B and 1M43-C002B fans.
a
REACTOR OPERATOR Page 46 QUESTION: 043 (1.00)
Which ONE of the following signals will cause the P86 Nitrogen Supply System Containment Isolation Valve (F002) to automatically close?
- a. Reactor vessel water level low-level 2.
- b. Reactor vessel water level low-level 1.
l
- c. Low Nitrogen Storage Tank pressure.
- d. High nitrogen system flow (indicative of system rupture).
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i REACTOR OPERATOR Page 47 f
QUESTION: 044 (1.00) f The M25/26, Control Room Ventilation System, is lined up with the "A" train operating in the NORMAL Mode, and the "B" train in STANDBY.
All switches are in the proper position for this mode of operation.
Which ONE of the following would result in BOTH trains of M25/26 operating in the EMERGENCY RECIRC Mode?
- a. Repositioning BOTH of the Mode Selector Switches to the EMERGENCY RECIRC position.
- b. The high smoke concentration alarms for the supply and return ducts are received.
- c. A High Control Room airborne radiation signal is received.
- d. Repositioning both Train Initiate Switches to ON.
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i REACTOR OPERATOR Page 48 QUESTION: 045 (1.00)
Select the choice that completes the following.
If there is not enough room in an ERIS value box to display the data and ERIS has good data, a asterisk will appear in the value box.
a.
Cyan
- b. White c.
Yellow
- d. Red
1 REACTOR OPERATOR Page 49 QUESTION: 046 (1.00)
The following plant conditions exist:
CRD Pump "B"
is in operation.
CRD Pump "A"
is tagged out for seal replacement.
Control rod 22-11 is at position 00 and valved out to repair a cracked weld on the accumulator.
Reactor Pressure is 995 psig.
Which ONE of the following actions is required if the CRD LEVEL HI/ PRESS LOW annunciator is received for rod 18-27 at position 00 and rod 38-23 at position 48?
I
- a. Immediately place the Reactor Mode Switch to SHUTDOWN.
- b. If an additional CRD LEVEL HI/ PRESS LOW annunciator is received for a withdrawn rod, immediately place the Reactor Mode Switch in SHUTDOWN.
- c. Within 20 minutes, verify CRD pump "B" is operating by withdrawing at least one control rod one notch and then re-inserting the rod.
- d. Immediately verify CRD pump "B" is operating by inserting at least one withdrawn control rod at least one notch.
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h REACTOR OPERATOR Page 50 QUESTION: 047 (1. 00)
The reactor is operating at full power when an INADVERTENT scram occurs.
Which ONE of the following is the approximate pressure applied to the control rods after the accumulators discharge?
a.
600 psig b.
1000 psig c.
1400 psig d.
1800 psig i
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i REACTOR OPERATOR Page 51 I
QUESTION: 048- (1.00) i I
A plant shutdown is in progress when the Hot Surge Tank Level indication goes off-scale high.
The operator is unable to secure flow to the hot surge tank
)
by closing the hot surge tank level control valves.
Which ONE of the following describes the operator action that must be taken to prevent overpressurizing the hot surge tank?
- a. Trip the Reactor Feed Pumps and the Feedwater Booster Pumps,
- b. Trip the Main Turbine and secure extraction steam to feedwater heater number 4.
- c. Trip the Hotwell Pumps and the Condensate Booster Pumps,
- d. Manually scram the reactor, secure all feed and condensate pumps, except for one hotwell pump, and throttle closed on the running hotwell pump's discharge valve.
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REACTOR OPERATOR Page 52 l
l QUESTION: 049
(,1. 00) l The following plant conditions exist:
Suppression pool temperature:
192 degrees F.
l Suppression pool level:
16 feet.
Containment pressure:
2.1 psig.
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RCIC suction path lined up to Suppression Pool.
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Which ONE of the following describes the limit on operating the l
Reactor Core Isolation Cooling (RCIC) system.
a.
The RCIC turbine speed should not exceed 2000 rpm.
- c. RCIC turbine operation may result in equipment damage.
- d. The RCIC turbine should be operated at reduced speed to limit pump flow to 350 gpm.
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REACTOR OPERATOR Page 53 i
QUESTION: 050 (1.00)
Suppression Pool temperature is monitored by the Containment Atmosphere Monitoring System (D23) and displayed on two meters on the Main Control Panel H13-P601.
Which ONE of the following describes the indication provided by these meters?
j
- a. The indication provided is an average of all Suppression Pool j
temperature points that are monitored by the CAM.
- b. The P601 meters display the same CAM points that are being plotted by the recorder on control room panel H13-P883.
- c. The operator must select the point being displayed by the meters on i
P601 by selecting the desired temperature point on P883.
- d. The operator must select the point being displayed by the meters on P601 by selecting the desired temperature point on P883. A high
]
temperature condition will automatically display the high temperature point on the associated division's meter on P601.
REACTOR OPERATOR Page 54 QUESTION: 051 (2. 00 )
MATCHING For the DC Electrical Distribution System, MATCH the loads in Column A with the appropriate power supply in Column B.
(Power supplies in Column B may be used once, more than once, or not at all.
Only one answer may occupy a space in Column A.)
(4 answers required at 0.50 each)
COLUMN A COLUMN B (Load)
(Power Supply)
- a. Main Turbine Emergency Bearing Oil 1.
125 VDC Bus EDIA Pump 2.
125 VDC Bus ED1B
- b. HPCS Logic 3.
125 VDC Bus ED1C c.
RHR B and C Logic 4.
125 VDC Bus D1A
- d. Div 1 Diesel Generator Controls 5.
125 VDC Bus D1B i
REACTOR OPERATOR Page 55 QUESTION: 052 (1.00)
An undervoltage condition (< 3010 VAC) exists due to a fault on bus EH11.
Which ONE of the following describes the plant conditions that must-be present in order for a loss of Off-site Power (LOOP) signal to be generated?
<75% voltage with no time delay on Bus EH12.
a.
b.
<75% voltage with no time delay on Bus EH13.
- c. <95% voltage for 15 seconds on Bus EH12.
- d. <95% voltage for 15 seconds on Bus EH13.
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REACTOR OPERATOR Page 56 QUESTION: 053 (1.00)
Which ONE of the following describes the response of the Fuel Pool Cooling and Cleanup System (G41) as a DIRECT result of reactor water level decreasing to below Level 17
- a. The isolation valves (G41-F280, F285, F290, and F295) for both G41 filter demins close.
- b. The standby G41 pump will automatically start if the control switch is in AUTO.
- c. The G41 Containment Isolation valves (G41-F100, F140, and F145) will close.
- d. The G41 filter demin bypass valve (G41-F360) will fail open and fully bypass the filter demins.
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REACTOR OPERATOR Page 57 QUESTION: 054 (1.00)
A-ground occurs just upstream of the preferred supply breaker for Bus EH13 which lowers bus voltage to 3650 VAC.
Three minutes later, the HPCS system and the HPCS Diesel Generator get a start signal from an inadvertent RPV t
Level 2 signal.
The HPCS Diesel Generator will:
L tie to the bus 15 seconds after receipt or the HPCS initiation a.
signal.
b.
tie to the bus 5 minutes after the ground occurs.
NOT tie to the bus because the initiation signal is not valid.
c.
r
- d. NOT tie to the bus because bus voltage remained above 75% of nominal.
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REACTOR OPERATOR Page 58 i
QUESTION: 055 (1.00)
The following conditions exist for the Inclined Fuel Transfer System (IFTS):
The Tube is Full and the Flap Valve is open.
Upper Upender is Vertical.
Carriage is at the RAISE LOW limit position.
Lower Upender is Inclined.
The system is powered up and neither bridge is in the IFTS area.
The Winch is NOT in motion.
Which ONE of the following describes the permissible operations for the IFTS system?
- a. The Refueling Bridge can enter the IFTS area.
- b. The Fuel Handling Bridge can enter the IFTS area in the Fuel Handling Building.
- c. The winch can be raised at slow speed using the " raise" or the " winch jog" pushbutton.
- d. The winch can be lowered using the " lower" pushbutton on the upper control panel.
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REACTOR OPERATOR Page 59 i
QUESTION: 056 (1. 00)
HPCS has automatically initiated due to receipt of BOTH Low Reactor Water Level AND High Drywell Pressure signals.
The HPCS initiation logic is reset:
a.
automatically when both initiation signals clear.
- b. manually after the high drywell pressure signal clears.
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- c. manually after the Low Reactor Water Level signal clears.
- d. automatically when Reactor Water level reaches level 8.
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REACTOR OPERATOR Page 60 QUESTION: 057 (1.00)
Which ONE of the following will cause the HPCS minimum flow valve (E22A-F012) to open?
I Pump discharge pressure greater than 145 psig AND system flow less j
a.
than 725 gpm.
- b. Pump discharge pressure greater than 145 psig OR system flow less than 725 gpm.
- d. HPCS Pump breaker auxiliary contact closed AND system flow less than 725 gpm.
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REACTOR OPERATOR Page 61
-QUESTION: 058 (1.00)
Which ONE of the following describes the flow path for the inboard Main Steam Line Isolation Valve Leakage Control System (MSIV-LCS) while operating in the bleed-off mode for the "A" main steam line?
- a. E32-F001A and E32-F002A (Bleed Valves) are open.
E32-F003A (Depressurization Valve) is closed and the blower is operating and discharging into the Shield Building Annulus,
- b. E32-F001A, E32-F002A and E32-F003A are open, discharging into the Shield Building Annulus, i
- c. E32-F001A, E32-F002A and E32-F003A are open, discharging into the Drywell.
- d. E32-F001A and E32-F002A are open.
E32-F003A is closed and the blower is operating and discharging into the Drywell.
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REACTOR OPERATOR Page 62 QUESTION: 059
(,1. 00 )
The Reactor Recirculation Pumps have just been shifted to fast speed during a reactor startup to rated power.
Immediately after the pump shift, the "LPCS OUT OF SERVICE" alarm annunciates.
Investigation reveals that the alarm is due to a LPCS line break.
The alarm is due to excest.ive differential pressure between the LPCS Spray Sparger and the:
i
- b. vessel downcomer region.
c.
RHR "B" LPCI injection nozzle.
d.
above core plate pressure tap.
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REACTOR OPERATOR Page 63 QUESTION: 060 (1.00)
The following conditions exist for the Reactor Recirculation Pump Motor breakers after a transient occurred:
Breaker 1A/B Closed Breaker 2A/B Closed i
Breaker 3A/B Open Breaker 4A/B Open Breaker SA/B Open Which ONE of the following plant conditions would cause this breaker configuration?
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- a. RPV water level decreased to +129 inches.
- b. Total Feedwater flow decreased to 2.5 Mlb/hr.
- c. RPV pressure increased to 1083 psig for 5 seconds.
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- d. Steam dome to bottom head drain delta T increased to 8 degrees F.
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REACTOR OPERATOR Page 64 QUESTION: 061 (1.00)
)
Initially the following plant conditions exist-Reactor Power 65%
Rod Line.
105%
Total Core Flow 52 Mlb/hr Reactor Recirculation Flow Control LOOP Manual The "A" Recirculation Loop flow controller fails, causing the "A" flow control valve to close.
Core flow decreases from 52 Mlb/hr to 43 Mlb/hr.
Which ONE of the following is the required IMMEDIATE action in accordance with ONI-B33-1, Reactor Recirculation Flow Control Malfunction, as a result of these plant conditions?
- a. Insert CRAM rods per FTI-B02, Control Rod Movements, to get below the 100% rod line and the thermal power versus core flow limits.
- b. Exit the shaded areas of the Power to Flow map by increasing flow in the "B" Recirculation Loop.
F
- c. Commence an immediate reactor shutdown in accordance with JOI-8, Shutdown By Manual Reactor Scram.
- d. Immediately scram the reactor by arming and depressing the RPS MANUAL SCRAM CH A, B,
C, and D pushbuttons.
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REACTOR OPERATOR Page 65 QUESTION: 062 (1.00)
The design change mechanism used to initiate minor changes / revisions to an issued Design Change Package (DCP) is a (an):
- a. Engineering Design Change Request.
- b. Field Change Notice.
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- c. Field Clarification Request.
- d. Plant Modification Package.
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REACTOR OPERATOR Page 66 5
QUESTION: 063 (1.00)
" HOT WORK" is required to perform maintenance on electrical equipment.
Which ONE of the following is the maximum voltage allowed to perform this work?
l a.
120 volts i
b.
300 volts c.
480 volts
- d. 750 volts i
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i REACTOR OPERATOR Page 67 QUESTION: 064 (1.00)
With regard to Emergency Diesel Generator, which ONE of the following terms is used to define any signal, intentional or unintentional, that causes the diesel generator unit to start and/or load, except those initiated during the process of troubleshooting during normal plant operation?
a.
Bona Fide Signal.
- b. Non-Valid Test.
- c. Valid Test and Success.
- d. Valid Demand.
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REACTOR OPERATOR Page 68 I
i QUESTION: 065 (l.00)
Which ONE of the following describes a correct valve verification method?
- a. To verify that a valve is full closed, turn the hand wheel in the open direction 1/8 to 1/4 turn, then in the close direction until.the valve is closed as verified by the position indication and firm tightness.
- b. Verify a manually operated locked valve is full closed by ensuring that the locking device is intact and verify valve position by the position indication or stem position.
Verify a manually operated valve is full open by turning the c.
handwheel in the open direction until no further movement indicates the valve is full open.
- d. Verify a throttle valve's position by manual adjustment of the valve position and confirming the position with the remote position indication provided.
REACTOR OPERATOR Page 69 l
QUESTION: 066 (1.00)
Which ONE of the following communications systems is specifically designed for reporting emergencies to the Control Room?
- a. Public Addres's System (PA) Line 1.
- b. Plant Radio System Frequency F2.
- c. Public Address System (PA) Line 5 i
- d. Private Branch Exchange (PBX) Phone System.
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i REACTOR OPERATOR Page 70 QUESTION: 067 (1.00)
Due to a toxic gas leak into a confined space, a rescue operation is required to remove a maintenance worker from the confined space.
Which ONE of the following plant personnel (by title) should be notified to-take charge of the rescue activities on-the-scene?
- a. Plant Safety Coordinator.
- b. Maintenance Work Supervisor.
- c. Fire Brigade Leader.
- d. Health Physics Supervisor.
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-REACTOR OPERATOR Page 71 QUESTION: 068 (1.00)
Which ONE of the following conditions requires the use of EMERGENCY DEPRESSURIZATION?
Drywell average air temperature is 210 degrees F.
a.
- b. Reactor Water Level cannot be determined.
Suppression Pool level at 26 feet with RPV pressure at 600 psig.
c.
j
- d. Offsite radioactivity release rate approaches or exceeds the release rate that requires an ALERT.
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REACTOR OPERATOR Page 72 l
l QUESTION: 069 (1.00)
Following a LOCA, the following plant conditions exist:
RPV Pressure 50 psig Drywell Temperature 287 degrees F Containment Temperature 255 degrees F RPV Level Indication:
- 1) Narrow Range 165 inches
- 2) Shutdown Range 200 inches
- 3) Upset Range 185 inches
- 4) Wide Range 175 inches Which ONE of the following level instrument (s) are providing a valid level l
indication?
- a. Narrow and Upset Ranges.
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- b. Shutdown and Wide Ranges.
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- c. Only the Shutdown Range.
- d. Only the Wide Range.
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I-REACTOR OPERATOR Page 73 QUESTION: 070 (1. 00) l The plant is operating at 50% power when, for reasons undetermined, l
. Suppression Pool level commences to rapidly decrease.
Assuming no other abnormal conditions exist, which ONE of the following would require a reactor scram be initiated by procedures?
- a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after level drops below 18.0 feet.
i
- b. If Suppression Pool temperature is maintained below 110 degrees F, a
scram is not required.
- c. When Suppression Pool level drops to 16.5 feet.
- d. When Suppression Pool level drops to 14.25 feet.
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REACTOR OPERATOR Page 74 QUESTION: 071 (1.00)
At the Division 1 Remote Shutdown Panel, the Control Transfer Switch (S10) has been placed in the EMERG position for the SRV's F051C, F051D, and F051G.
At the Division 2 Remote Shutdown Panel, the Transfer and Control Switches for SRV's F051C and D have been taken out of the CONTROL ROOM position to the OFF position and the Transfer and Control Switch for SRV F051G is still in i
the CONTROL ROOM position.
Which ONE of the following describes the response of SRV's F051C, D, and G if a transient causes reactor pressure to rise to 1140 psig?
- a. All three of the SRV's will open,
- b. Only SRV's F051C and D will open.
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- c. Only SRV F051G will open.
- d. None of the SRV's will open.
REACTOR OPERATOR Page 75 f
QUESTION: 072 (1.00)
Which ONE of the following sets of valve solenoids receive power from 125 VDC?
- a. Scram Pilot and Alternate Rod Insertion Solenoid valves.
b.
Backup Scram and Scram Discharge Volume Pilot Solenoid valves.
- c. Scram Discharge Volume Pilot and Scram Pilot Solenoid-valves.
- d. Backup Scram and Alternate Rod Insertion Solenoid valves.
6
REACTOR OPERATOR Page 76 1
QUESTION: 073 (1.00)
A reactor startup is in progress pulling to 50% rod density.
Group 1 has been fully withdrawn.
All group 2 rods are at notch position 12.
While continuing the rod withdrawal, the operator " misreads" the pull sheet and selects a rod in group 3 for withdrawal.
Which ONE of the following describes the response of the RC&IS to this event?
- a. Withdrawal of the rod is immediately blocked.
- b. Withdrawal of the rod is blocked when the rod reaches notch position 14.
- c. Withdrawal of the rod is blocked when the rod reaches notch position 2.
- d. Withdrawal of the rod until full out at which time a rod block will be generated.
I
- i 7
-,., + = - - - - - -, - =. -, - -
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REACTOR OPERATOR Page 77 i
QUESTION: 074 (1.00)
Which ONE of the.following conditions would result in the "CNTMT Spray B Start Signal Received" annunciator?
(Assume that the Containment Spray Initiation Logic is in the normal standby mode.)
- a. LPCI has AUTO initiated for 10 minutes, drywell pressure is 1.5 psig and containment pressure is 11.0 psig.
- b. LPCI has Auto initiated for 10 minutes, drywell pressure is 8.0 psig i
and containment pressure is 6.0 psig.
- c. LPCI has AUTO initiated for 5 minutes, drywell pressure is 8.0 psig, I
containment pressure is 6.0 psig, and the CNTMT Spray B Manual i
Initiation switch has been armed and depressed for greater than 35 seconds.
- d. LPCI has AUTO initiated for 5 minutes, drywell pressure is 1.5 psig, and containment pressure is 11.0 psig, and the CNTMT Spray B Manual i
Initiation Switch has been armed and depressed for greater than 35 seconds.
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REACTOR OPERATOR Page 78 QUESTION: 075 (1. 00)
Which ONE of the following statements concerning the Steam Seal System DOES accurately describe the operation of the system?
- a. The Steam Seal System provides steam to seal the shaft glands of the Main Turbine and Reactor Feedpump control valves.
- b. The Steam Seal Exhaust System collects leak off from glands on the Main Turbine stop and control valves to prevent release of radioactive steam into the Turbine Building.
- c. The Steam Packing Exhauster is cooled by the Condensate System, but only 25% of the condensate flow passes through the Steam Packing Exhauster tubes.
- d. The Steam Seal Header is directly supplied from the main steam header or 8th stage extraction steam and is controlled by an automatic pressure control system.
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REACTOR OPERATOR Page 79 i
1 QUESTION: 076 (1.00) i Which ONE of the following conditions will automatically close the SJAE-suction valves?
- a. Low steam supply pressure, less than 40 psig.
- b. Low offgas recombiner inlet temperature, less than 250 degrees F.
- c. Low second stage steam flow, less than 9000 lbm/hr.
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- d. Low intercondenser level, less than 6 inches.
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REACTOR OPERATOR Page 80 QUESTION: 077 (1.00)
Testing of the SRVs is in progress.
Plant conditions:
Reactor mode switch position:
STARTUP Reactor coolant temperature:
540 degrees F.
Reactor power:
2%.
Suppression pool temperature:
111 degrees F.
(has exceeded t
90 degrees for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)
Suppression pool level:
17 feet 8 inches t
Which ONE of the following describes the required operator action (s)?
Place the reactor mode switch to SHUTDOWN, and place at least one RHR a.
loop in suppression pool cooling mode.
l
- b. Reduce suppression pool temperature to less than 90 degrees F. within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, If suppression pool level is not restored to within limits within 12 I
c.
hours, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- d. Stop all testing which adds heat to the suppression pool and restore the average temperature to less than 90 degrees F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
)
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REACTOR OPERATOR Page 81 QUESTION: 078 (1.00)
Which ONE of the following is cooled by the Stator Water Cooling System?
- a. Alterrex Exciter Power rectifiers.
- b. Generator hydrogen coolers.
- c. Exciter duplex cooler,
- d. Hydrogen seal oil cooler.
4
REACTOR OPERATOR Page 82 L
QUESTION: 079 (1.00)
Which ONE of the following Area Radiation Monitors is covered by Perry Technical Specifications.
q
- a. Personnel Air Lock detector.
- b. Refueling Bridge detector,
- c. Reactor Water Cleanup Filter /Demin Area detector, d.
Fuel Preparation Pool detector.
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i REACTOR OPERATOR Page 83 QUESTION: 080 (1.00)
During a plant shutdown for an upcoming refueling outage, the following plant parameters are observed:
P Reactor Mode Switch:
SHUTDOWN Reactor Level:
+200 inches Reactor Pressure:
100 psig Rx Coolant Temp.:
327 degrees F NO outstanding ALCOs At this time the U.S.
directs the S.O.
to place RHR "A" loop in the Shutdown Cooling Mode.
The S.O.
questions the U.S. by stating that RHR "A" must be maintained in the LPCI Standby Mode.
The U.S.
tells him that he is not correct.
Which ONE of the following describes who is correct and the reason?
a.
S.O.
- LPCI "A" mode is required to be operable for Operational Condition 3.
b.
U.S.
- One LPCI subsystem of the RHR system may be aligned in the Shutdown Cooling Mode because reactor vessel pressure is less than 135 psig.
]
- c. U.S.
- Only one train of RHR is required to be operable in the LPCI mode in Operational Condition 3.
- d. U.S.
- LPCI "A" mode is administratively declared inop and the 7 day LCO is entered thereby allowing RHR "A" loop to be placed in the Shutdown Cooling Mode.
REACTOR OPERATOR Page 84 QUESTION: 081 (1.00)
The plant is operating at 55% reactor power on the 75% rod line with the reactor recirculation system in Loop Manual when a " Heater 1A Level High"
~
annunciator is received.
The operator observes that reactor power has increased by 10% and feedwater temperature has decreased by 20 degrees F.
Which ONE of the following describes the required IMMEDIATE operator action (s)?
- a. Manually scram the reactor by depressing the manual scram pushbuttons l
and take actions per the Reactor Scram procedure.
- b. Reduce reactor power to less than or equal to 62% by reducing recirc flow to not less than 35 Mlbm/ hour and monitor core thermal limits.
- c. Reduce reactor power to 35% by decreasing recirculation flow to not less than 42 Mlbm/ hour and inserting rods to below the 70% rod line.
J d.
Reduce reactor power to 55% by decreasing recirculation flow.
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REACTOR OPERATOR Page 85 QUESTION: 082 (1.00)
Initial Plant Conditions:
Alternate Pressure Regulator channel available.
l Operator observes the following:
F Annunciators alarming:
APRM A/E UPSCALE TRIP /INOP ROD BLOCK APRM UPSCALE RPV pressure increasing Which ONE of the following operational situations could cause the above indications while operating at 85% of rated thermal power?
- a. Maximum combined' flow limiter fails high.
b.
"A" pressure regulator failure - open, then one minute later, the "B"
pressure regulator slowly fails closed.
"A" pressure regulator failure - closed, then one minute later, the c.
"B" pressure regulator slowly fails open.
- d. During the power increase from 65% to 85% Rx power, the turbine Load i
Set setpoint was never increased.
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REACTOR OPERATOR Page 86 i
QUESTION: 083 (1.00)
Which ONE of the following lists the design MAXIMUM INTERNAL pressure for the Drywell and Containment?
- a. Drywell 30 psig and Containment 30 psig.
- b. Drywell 30 psig and Containment 15 psig.
- c. Drywell 21 psid and containment 30 psig.
- d. Drywell 21 psig and containment 15 psig.
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REACTOR OPERATOR Page 37 QUESTION: 084 (1.00)
Which ONE of the following is NOT a function or purpose of PEI-B13, RPV Control?
- a. Cooldown the RPV to cold shutdown.
- b. Shutdown the reactor.
5 c.
Protect safety-related equipment in the Containment /Drywell.
- d. Maintain adequate core cooling.
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REACTOR OPERATOR Page 88 i
QUESTION: 085 (1.00)
Prior to a manual scram, the plant is at 100% rated thermal power with the Feedwater Master Level Controller in THREE ELEMENT CONTROL and its tape set inches.
at 201 Which ONE of the following statements describes the response of the Feedwater Level Control System following the scram?
- a. Upon receipt of the scram signal, the level demand signal will be 196 inches for 10 seconds and then decrease to 178 inches.
- b. Upon receipt of the scram signal, the level demand signal will be 201 inches for 10 seconds and then decrease to 178 inchec.
- c. When level reaches 178 inches, the level demand signal will be 196 inches for 10 seconds and then decrease to 178 inches.
- d. When level reaches 178 inches, the level demand signal will be 201 inches for 10 seconds and then decrease to 178 inches.
)
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REACTOR OPERATOR Page 89 QUESTION: 086 (1.00)
Following a transient, RPV Flooding is being executed.
Emergency Depressurization is in progress.
Plant conditions are as follows:
l l
Reactor is NOT shutdown.
l RPV pressure is 600 psig.
2 SRVs are OPEN.
l Which ONE of the following describes the condition of core cooling and any operator action that may need to be taken?
- a. The core is adequately cooled by steam flow and/or submergence irrespective of whether any water is being injected into the RPV.
- b. The core is adequately cooled by steam flow and/or submergence so l
long as a source of water is being injected into the RPV.
- c. The core is inadequately cooled due to insufficient steam flow and the operator must <>en another SRV to increase steam flow through the core.
- d. The core is inadequately cooled due to insufficient steam flow and the operator must take action to lower RPV pressure to 500 psig or i
slightly less.
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REACTOR OPERATOR Page 90 l
OUESTION: 087 (2.00) 1 MATCHING MATCH the correct reactor water level setpoint in Column B to the appropriate i
Action in Column A. (The water level setpoints in Column B may be used once, more than once, or not at all.
Only one answer may occupy a space in Column A.)
(4 answers required at 0.5 each)
COLUMN A COLUMN B (Action)
(Setpoint)
Level 1
- b. HPCS injection valve closes 2.
Level 2 c.
Recirculation pumps transfer 3.
Level 3 to LFMG 4.
Level 4 d.
AEGTS auto start logic 5.
Level 5 i
6.
Level 7 l
7.
Level 8 l
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REACTOR OPERATOR Page 91 QUESTION: 088 (1.00)
Which ONE of the following is the MAXIMUM pressure in the RPV steam dome that
~
can be reached without exceeding a Safety Limit?
The reactor coolant system pressure, as measured in the reactor vessel steam dome, shall not exceed:
- a. 1250 psig b.
1325 psig c.
1375 psig d.
1500 psig b
6 s
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REACTOR OPERATOR Page 92 QUESTION: 089 (1.00)
Which ONE of the following describes an approved alternate method of decay j
heat removal that can be used if the normal shutdown cooling lineup is lost 1
and cannot be reestablished while in Operational Condition 4?
- a. Operate HPCS to circulate coolant between the suppression pool and the reactor vessel via head vent.
- b. Operate one loop of RHR in the Suppression Pool Cooling Mode and circulate the reactor coolant between the suppression pool and the reactor vessel with the Low Pressure Core Spray System via two open Safety Relief Valves (SRV).
- c. Operate the Condensate System Hotwell Pumps to circulate water between the main condenser and the reactor vessel via the MSIVs.
- d. Operate LPCS to maintain level while dumping to radwaste from Reactor Water Cleanup (RWCU).
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REACTOR OPERATOR Page 93 QUESTION: 090 (1.00)
Which ONE of the following conditions is required to be met during refueling operations in operational Condition 5?
- a. At least 22 feet 10 inches of water shall be maintained over the top of the Reactor Pressure Vessel flange.
- c. The Containment Building overhead crane may be used to handle control rods in the RPV.
- d. The reactor shall be subcritical for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to movement of irradiated fuel in the vessel.
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REACTOR OPERATOR Page 94 I
QUESTION: 091 (1.00)
The plant is shutdown in Operational Condition 4.
RHR Loop A is in the Shutdown Cooling Mode maintaining coolant temperature 100 to 140 degrees F.
Reactor recirculation pump "B" is tagged out for maintenance.
Reactor water level is being maintained 190 to 210 inches by Shutdown Range Level indication.
For an unknown reason, reactor recirculation pump "A" tripped off and the Unit Supervisor directs entry into the ONI-E12-2, Loss of Decay Heat Removal.
Which ONE of the following conditions required the entry into ONI-E12-27 Shutdown Range water level indication is NOT accurate because a.
Shutdown Range Water Level instrument calibration conditions assume reactor recirculation pumps are in operation.
- b. Unit Supervisor, as required in Technical Specifications, declares both shutdown cooling mode loops cf RHR inoperable due to the loss of all recirculation pumps.
RHR "A" shutdown cooling flowrate decreases from 7000 gpm to 3500 gpm c.
due to loss of both recirculation pumps.
- d. Reactor coolant temperature cannot be accurately determined because reactor water level is less than 250 inches by Shutdown Range Level indication.
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REACTOR OPERATOR Page 95 QUESTION: 092 (1.00)
During the execution of PEI-D17, Radioactive Release Control, the Heater Bay Building HVAC System is restarted, if not running.
Which ONE of the following is the PRIMARY reason for restarting the system?
- a. Maintains a positive pressure in the Turbine Building and Heater Bay I
to prevent radioactive in-leakage, i
- b. Provides a filtered and monitored release path through the offgas Building Exhaust System to reduce radioactive releases from the Heater Bay.
Insures the Turbine Building and Heater Bay atmosphere are released c.
to the elevated, monitored release point in the Heater Bay Building HVAr system.
d.
Provides a filtered release path to reduce the radiation levels released from the Heater Bay.
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REACTCR OPERATOR Page 96 QUESTION: 093 (1.00)
NCC Pump "A" is running with BUS XH11 LOCA BYPASS keylock switch in BYPASS when it is determined that the LPCS system must be run to provide adequate core cooling.
Which ONE of the following describes the operator action (s) for these plant conditions?
- a. No action required, NCC is allowed to remain in operation.
b.
Turn NCC Pump "A" to the OFF position.
c.
Secure NCC Pump "A" only if NCC Pump "B" can be started.
- d. Open ISOLATING BRKR EH1116, and place BUS XH11 LOCA BYPASS keylock switch in NORM.
REACTOR OPERATOR Page 97 QUESTION: 094 (1.00)
The following plant conditions exist:
Reactor Power is 100%.
Narrow Range Channel "B"
is selected.
DC Bus D-1-A is faulted and deenergizes.
Which ONE of the following describes the consequences of FAILING to complete the immediate action that transfers Reactor Feedwater Pump Turbine (RFPT) control from automatic to manual for these plant conditions?
(Assume no further operator actions.)
- a. RPV water level increases continuously and-causes a reactor scram, but the Main Turbine will NOT trip on high water level.
- b. RPV water level increases until the Main Turbine trips on high water level, but the reactor scram will NOT occur due to the loss of the DC
- bus,
- c. RPV water level increases until the RFPTs trip on high water level and the reactor scrams when water level decreases to Level 3.
- d. RPV water level increases and then stabilizes at a higher water level when level error overrides the flow error signal on "A" RFPT.
tw
REACTOR OPERATOR Page 98 QUESTION: 095 (1.00)
High Pressure Core Spray Pump (HPCS) and the Motor Feed Pump (MFP) were manually started during a loss of feedwater transient and recovered RPV level.
Which ONE of the following describes the plant response when RPV water level increases to the Level 8 setpoint?
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REACTOR OPERATOR Page 99 l
l QUESTION: 096 (1.00) l A step in ONI-N62, Loss of Condenser Vacuum, states "If thermal power is less than 5% and vacuum cannot be maintained, the mechanical vacuum pump may be used to draw a vacuum".
Which ONE of the following is the reason for the 5% power limitation?
i
- a. Prevents an excessive Off-Gas stack release.
b.
Prevents an unmonitored release path.
Prevents the isolation of the Off-Gas System on high flow.
c.
i d.
Prevents the possibility of a hydrogen detonation.
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REACTOR OPERATOR Page100 QUESTION: 097 (1.00)
Select the choice that completes the following.
When referring to the ALARA concept, the term " Collective Unit Dose" describes the total occupational radiation exposure received by:
- a. any one individual at the Perry Plant.
- b. all personnel on a specific RWP.
- c. any one individual on a specific RWP.
I
- d. all personnel assigned to the Perry Plant.
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(********** END OF EXAMINATION **********)
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. REACTOR OPERATOR-Page101 ANSWER:
001 (1.00) i C.
REFERENCE:
Perry SDM B21 NBPI Lesson Plan OT-3036-001-B21(INST)
Learning Objective B.2.b 216000K307 [3.9/4.1]
216000K307
..(KA's)
ANSWER:
002 (2.00)
.i
- a. 3 and 5
- b. 2 and 3
- c. 2 and 3 d.
3 and 5 (8 required at 0.25 ea)
REFERENCE:
Perry SDM PS2 Page 7 Lesson Plan OT-3036-003-P51/52 Learning Objective E I
223001K101 [3.7/3.9]
223001K101
..(KA's) l ANSWER:
003 (1.00) l C.
4
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I Page102 REACTOR OPl:RATOR
REFERENCE:
-Lesson Plan OT-3036-003-C51 Iaarning Objective B.1 1
215005A107 [3.0/3.4]
t 215005A107
..(KA's)
ANSWER:
004 (1.00) b.
REFERENCE:
Perry SDM C61 pg 11 Lesson Plan OT-3036-002-C61 Learning Objective E.1 l
295016A108 (4.0/4.0]
-)
295016A108
..(KA's)
ANSWER:
005 (1.00)
C.
REFERENCE:
Perry Off Normal Instruction ONI R25-1 Page 7 Lesson Plan OT-3036-M43 Learning Objective F 262001K302 (3.8/4.2]
262001K302
..(KA's)
J ANSWER:
006 (1.00) b.
REACTOR OPERATOR page103
REFERENCE:
Perry Nuclear Power Plant Integrated Operating Instruction IOI-3 pg 2 201002G010 [3.9/3.9]
201002G010
..(KA's) l ANSWER:
007 (1.00) d.
REFERENCE:
Perry Administrative Procedure PAP-1401, Rev 6, Page 6 Lesson Plan OT-3039-001-06 Learning' Objective D 294001K102
[3.9/4.5]
l 294001K102
..(KA's)
ANSWER:
008 (1.00) b.
REFERENCE:
PAP-1402, Rev 9, Page 5 Lesson Plan OT-3039-001-06 Learning Objective D 294001K102
[3.9/4.5]
294001K102
..(KA's)
RNSWER:
009 (1.00)
C.
I 1
1 REACTOR OPERATOR Page104
.i i
REFERENCE:
l Perry Technical Specifications Section 1.0 Definitions Lesson Plan OT-3037-004-07 Learning Objective A.3 i
215005G006
[2.9/3.8]
215005G006
..(KA's) 1 ANSWER:
010 (1.00) 4 a.
l
REFERENCE:
J Perry, AEGTS, M15, pg 9, 10, and 22, and Fig. M15-2 Lesson Plan OT-3036-002-M15-00 Learning Objectives C, E,
F 261000K401
[3.7/3.8]
j l
261000K401
..(KA's)
I ANSWER:
011 (1.00) c.
REFERENCE:
i l
OT-3036-003-R43/48 Learning Objective K SOI-R43, Section 7.5, Rev. 8 Perry ONI-R10, " Station Blackout" 295003A102
[4.2/4.3]
295003A102
..(KA's)
ANSWER:
012 (1.00) b.
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REACTOR-OPERATOR Page105 l
j
REFERENCE:
Perry PAP 0110 j
Lesson Plan OT'3039-004-01 Learning Objective C 294001A103
}
i 294001A103
..(KA's)
ANSWER:
013 (1.00) t a.
REFERENCE:
Perry PAP 0514, Attachment 2
. Lesson Plan OT-3039-004-02 l
Learning Objective C i
Wote:
Facility to verify appropriate 294001K105
[3.2/3.7]
294001K105
..(KA's)
ANSWER:
014 (1.00)
C.
REFERENCE:
Perry SDM C95 page 8 Lesson Plan OT-3036-C95-00 Learning Objective C.2 294001A115 i
294001A115
..(KA's)
ANSWER:
015 (1.00) c.
1 l
REACTOR OPERATOR Page106
REFERENCE:
PAP 0512, Rev 3, pg 12 and 13
~
lesson Plan OT-3039-004-02 Learning Objective A 294001K103
[3.3/3.8]
294001K103
..(KA's)
ANSWER:
016 (1.00) a.
REFERENCE:
OAP-0103, " Shift Relief and Turnover", page 8.
294001A103
[2.7/3.7]
294001A103
..(KA's) i ANSWER:
017 (1.00) d.
REFERENCE:
IOI-9 page 15 and 31, 1
SDM B21-NBPI Lesson Plan OT-3036-001-B11 (INST)
Learning Objective B.2.b 295031K201
[4.4/4.4]
295031K201
..(KA's) i ANSWER:
018 (1.00) l i
b.
1 i
t l
REACTOR' OPERATOR Page107 l
REFERENCE:
i Tech Spec 3.4.1.3 SDM B33, pg 3 frated recirc pump flow = 42,000 gpm)
Lesson Plan OT-3036-002-B33 Learning Objective J.3 302001G005
[3.4/4.2]
l 202001G005
..(KA's)
ANSWER:
019 (1.00)
C.
REFERENCE:
i f
SDM C41-SLCS page 10 and Fig. C41-7 Lesson Plan OT-3036-C41-01 Learning Objective F i
211000A402
[4.2/4.2) 211000A402
..(KA's)
ANSWER:
020 (1.00) d.
REFERENCE:
1 Perry SDM N32/C85 page 2-13 Lesson Plan OT-3036-N32/C85-00 Learning Objective H.S 241000A201
[3.5/3.7) 241000A201
..(KA's)
-ANSWER:
021 (1.00) d
-~
REACTOR OPERATOR Page108 t
l
REFERENCE:
ONI-PS2, Rev 3, pg 8 and 9 Lesson Plan OT-3036-002-N27 Learning Objective H 295019K203
[3.2/3.3]
295019K203
..(KA's) i i
ANSWER:
022 (1.00)
}
d.
REFERENCE:
SDM B21(NS4) page 12, 13, and 38 Lesson Plan OT-3036-B21(NS4)-00 Learning Objective E 295020A206
[3.4/3.8]
295020A206
..(KA's) l
' ANSWER:
023 (1.00) l C.
REFERENCE:
Perry SDM E-51 RCIC page 14 and 15 Lesson Plan OT-3036-E51-01 Learning Objective D
'217000A301
[3.5/3.5]
217000A301
..(KA's)
ANSWER:
024 (1.00) 1 d.
REACTOR OPERATOR Page109
REFERENCE:
- Perry SDM B21-(NS4), pg 15 and Table 2, pg 28 Lesson Plan OT 3036-B21(NS4)-00 Learning Objective G.4 239001K201
[3.2/3.3]
239001K201
..(KA's)
ANSWER:
025 (1.00) d.
REFERENCE:
Perry SDM P54 (WTR), pg 16 and 17 Lesson Plan OT-3036-004-P54 (WTR)
Learning Objective D.1.a and b ONI-P54, Rev 3, pg 1 286000A301
[3.4/3.4]
286000A301
..(KA's)
ANSWER:
026 (1.00) d.
REFERENCE:
Perry SDM C71, pg 26 and 27 and Fig. C71-12 Lesson Plan OT-3036-003-C71 Learning Objective B 212000A212
[4.0/4.1]
212000A212
..(KA's)
ANSWER:
027 (1.00) d.
i
~
I l
REACTOR OPERATOR Pagel10
REFERENCE:
Perry SDM B21C,- Figure B21C-5 Lesson Plan OT-3036-001-B21C Learning Objective E.1
'218000K601
[3.9/4.1]
218000K601
..(KA's)
ANSWER:
028 (1. 00) d.
REFERENCE:
Perry SDM B21C, figure B21C-5 Lesson Plan OT-3036-001-B21C Learning Objective E.1 Note:
Distractor derivation:
a.
105 sec. time delay plus time to reach Level 3 (178")
b.
105 sec. time delay plus time to reach Level 2 (130")
c.
Time to reach Level 1 (16.5")
218000K501
[3.8/3.8]
218000K501
..(KA's)
ANSWER:
029 (1.00)
C.
REFERENCE:
Perry SDM B21/N11, pg 17 Lesson Plan OT-3036-003-B21/N11, Learning Obj. E.1 Learning Objective E.1 218000K105
[3.9/3.9]
218000K501
..(KA's)
- 1 i
l
-REACTOR OPERATOR Page111 l
l ANSWER:
030 (1.00) d.
REFERENCE:
Perry SDM N-64 page 17 Lesson Plan OT-3036-002-N64 Learning Objective L.6 I
295017A107
[3.4/3.6]
i 295017A107
..(KA's)
ANSWER:
031 (1.00) d.
t
REFERENCE:
Perry SDM E51 page 13 Lesson Plan OT-3036-E51-01 Learning Objective E
.t 217000A301
[3.5/3.5]
i 217000A301
..(KA's)
'l ANSWER:
032 (1.00)
C.
REFERENCE:
. Perry SDM F15 Page 14 and SDM C11 Page 51 l
234000A301
[2.6/3.6)
-1 234000A301
..(KA's) 1 j
i l
1 REACTOR OPERATOR Page112 1
i ANSWER:
033 (1.00) d.
REFERENCE:
PEI-T23-2 lesson Plan OT-3402-002-09
(
Learning Objective C l
295024A118
[3.6/3.6]
l 295024A118
..(KA's)
ANSWER:
034 (1.00) i a.
i a
REFERENCE:
Lesson Plan OT-3402-02-11 Obj. C t
295037A201
[4.2/4.3]
l 295037A201
..(KA's) i ANSWER:
035 (1.00) a.
REFERENCE:
Perry SDM B33, pg. 5 Lesson Plan OT-3036-002-B33 Learning Objective O.2 202001A210 [3.5/3.9) i 202001A210
..(KA's) f L
r,
i REACTOR OPERATOR Page113 i
ANSWER:
036 (1.00)
[
a.
i
REFERENCE:
Perry SOI-M14, page 1 Lesson Plan OT-3036-002-M14 Learning Objective F.1.b
- Note:
Facility review to ensure "d"
is not an arguably correct answer.
223001G010 [3.2/3.6]
l l
223001G010
..(KA's)
ANSWER:
037 (1.00)
C.
REFERENCE:
Perry SDM R43 pg 18 and Fig. R43-2 Lesson Plan OT-3036-003-R43/48 Learning Objective B.2 and B.4 264000A401 [3.3/3.4]
264000A401
..(KA's)
' ANSWER:
038 (1.00) b.
l
]
REFERENCE:
SDM R43 pg 17 i
264000A404 [3.7/3.7]
264000A404
..(KA's) i 9
y, w
^
REACTOR OPERATOR Pagel14 ANSWER:
039 (1.00) d.
REFERENCE:
t OT-3402-002-03, RPV Power Control, pg 16, 22, 25, and 26 295015A202
[4.1/4.2]
i r
295015A201
..(KA's)
ANSWER:
040 (1.00) a.
REFERENCE:
Perry CNI-B21-1, "SRV Inadvertent Opening / Stuck Open."
PEI-T23 AND PEI-B13 Lesson Plan OT-3037-005-05 Learning Objective B.23 295026A201 295026A201
..(KA's)
ANSWER:
041 (1.00) d.
REFERENCE:
Lesson Plan OT 3036-E12 System Description Manual E12 SOI-E12, Residual Heat Removal System, Page 3 Lesson Plan OT-3036-E12-02 l
Learning Objective I 219000K101 [3.8/3.9]
219000K101
..(KA's)
h REACTOR OPERATOR Page115 ANSWER:
042 (1.00)
C.
REFERENCE:
System Description Manual M43, pg 6 Lesson Plan OT-3036-M43-00 Learning Objective D.1 288000A401 [3.1/2.9]
288000A401
..(KA's)
RNSWER:
043 (1.00) a.
REFERENCE:
Perry SDM P86, pg 5 and 6' Lesson Plan OT 3036-001-P86 Learning Objective E 223002A302 [3.5/3.5]
223002A302
..(KA's) i RNSWER:
044 (1.00)
C.
REFERENCE:
Perry SCM M25/26, pg 11, 13, Table M25/26 and Table M25/26-11.
Lesson Plan OT 3036-M25/26-00 Learning Object.ive B.3 290003A301 [ 3. ~3/3. 5]
I 29 0003 A's 01
..(KA's) i
. ~.
. REACTOR OPERATOR Pagel16 l
ANSWER:
045 (1.00) b.
REFERENCE:
Perry SDM C95, pg 8 Lesson Plan OT-3036-C95-00 Learning Objective C.2 294001A115 [3.2/3.4) 294001A115
..(KA's)
ANSWER:
046 (1.00) d.
REFERENCE:
OT-3037-004-02 Learning Objective E.15 295022G010 [3.7/3.5)
)
295022G010
..(KA's) 4 ANSWER:
047 (1.00) t b.
f
REFERENCE:
1 Perry SDM C11 i
Lesson Plan OT-3036-005-C11 l
Learning Objective D j
201003A205 [4.1/4.1) i 201003A265
..(KA's)
I i
REACTOR OPERATOR Page117
. ANSWER:
048 (1.00) c.
REFERENCE:
Perry SDM N21/N61 Lesson Plan OT-3036-002-N21/N61 Learning Objective E.1.a 256000A101 [2.9/2.9]
256000A101
..(KA's)
ANSWER:
049 (1.00) c.
REFERENCE:
Perry System Description Manual Chapter E51.
OT-3402-002-01, Obj. D 295026G012
[3.8/4.5]
295026G012
..(KA's)
ANSWER:
050 (1.00) c.
REFERENCE:
Lesson Plan OT 3036-D23 System Description Manual D23, pg 7 223001A109 [3.5/3.6]
i l
223001A109
..(KA's)
I I
l J
REACTOR OPERATOR Page118
. ANSWER:
051 (2.00)
- a. 5
- b. 3 i
c.
2 d.
1 (4 answers required at 0.50 each)
REFERENCE:
Lesson Plan OT-3036-R42 System Description Manual R42
.263000K201 [3.1/3.4]
263000K201
..(KA's) f RNSWER:
052 (1.00) a.
REFERENCE:
Lesson Plan OT-3036-R10 System Description Manual R10 System Description Manual R43, pg 12 and 13
}
262001A203 [3.9/4.3]
262001A203
..(KA's) f ANSWER:
053 (1.00) a.
L L
I
{
REACTOR OPERATOR Pagel19-
REFERENCE:
i
. Lesson Plan'OT-3036-G41 l
System Description Manual G41, pg 13 233000K408 [2.6/2.8]
233000K408
..(KA's) s t
ANSWER:
054 (1.00) a.
REFERENCE:
Lesson Plan OT-3036-E22B System Description Manual E22B l
264000K107 [3.9/4.1]
264000K107
..(KA's)
ANSWER:
055 (1.00) a.
REFERENCE:
System _ Description Manual F42, pg 10, 11, and 14 295023G006 [3.4/3.6]
295023G006
..(KA's)
ANSWER:
056 (1.00)
C.
t 1
i i
i REACTOR OPERATOR Page120
REFERENCE:
i Lesson Plan OT 3036-E22A System Description Manual E22A, pg 16
{
i 209002G001 [3.7/4.0) 209002G001
..(KA's) i ANSWER:
057 (1.00) l l
a.
REFERENCE:
Lesson Plan OT-3026-E22A-System Description Manual E22A, pg 23 209002G007 [3.4/3.6]
209002G007
..(KA's)
ANSWER:
058 (1.00) a
REFERENCE:
Lesson Plan OT-3036-E32 System Description Manual E32, pg 2 239003A401 (3.2/3.2]
239003A401
..(KA's)
ANSWER:
059 (1.00) a.
l l
.,i
.w J
P REACTOR OPERATOR Page121
REFERENCE:
Lesson Plan OT-3036-E21 System Description Manual E-21, pg 23 309001A205 [3.3/3.6]
209001A205
..(KA's)
ANSWER:
060 (1.00) c.
REFERENCE:
l Iasson Plan OT-3036-B33 System Description Manual B33, pg 23-26 202001K414 [4.0/4.1]
202001K414
..(KA's) 1 ANSWER:
061 (1.00) d.
REFERENCE:
Lesson Plan OT-3036-B33 System Description Manual B33 ONI-B33-1, Rev.
3, pg 2 295001A201 [3.5/3.8]
295001A201
..(KA's)
ANSWER:
062 (1.00) b.
REACTOR OPERATOR Pagel22
REFERENCE:
Perry PAP-0301
~
Lesson Plan OT-3039-03 Learning Objective D KA 294001A101
[2.9/3.4]
294001A101
..(KA's)
ANSWER:
063 (1.00) b.
REFERENCE:
Perry PAP-0504, Rev.
4, pg 6 and 12 Lesson Plan OT-3039-03 Learning objective C 294001K107 [3.3/3.6) 294001K107
..(KA's)
.l ANSWER:
064 (1.00) d.
REFERENCE:
Perry PAP-1705, Rev.
2, pg 3 and 4 Lesson Plan OT-3039-03 Learning Objective D 294001A103 [2.7/3.7)
)
l 294001A103
..(KA's)
ANSWER:
065 (1.00) b.
REACTOR OPERATOR Pagel23
REFERENCE:
Perry PAP-0205 Lesson Plan 3079 241000K101
[3.7/3.7) 241000K101
..(KA's)
ANSWER:
066 (1.00)
C.
l REFERENCE-Perry PAP-0202, Rev 2, pg 3a 241000104
[3.1/3.2]
241000A104
..(KA's)
ANSWER:
067 (1.00) c.
REFERENCE:
PAP-0516, Rev 2, pg 5
[3.2/3.4) i 294001K114
..(KA's)
ANSWER:
068 (1.00) b.
1 REACTOR OPERATOR Page124
REFERENCE:
PEI-B13 Lesson Plan OT-3402-12 Learning Objective C.1 KA 295031K301
[3.9/4.2]
295031K301
..(KA's)
ANSWER:
069 (1.00) b.
REFERENCE:
PEI-B13, PEI-SPI Fig la, 2a, 2b, 2c Lesson Plan OT-3402-07 Learning Objective C KA 295027G012
[4.3/4.6]
o 295027G012
..(KA's)
ANSWER:
070 (1.00) d.
1
REFERENCE:
PEI-T23 and PEI-B13 (Emergency Depressurization)
Lesson Plan OT-3402-05 i
Learning Objective C KA 295030G011
[4.3/4.5]
a 295030G011
..(KA's) 1 ANSWER:
071 (1.00)
C.
l I
i
]
I REACTOR OPERATOR Page125
REFERENCE:
SDM-C61, pg 11,
K4 295016K201
[4.4/4.5]
4 295016K201
..(KA's)
ANSWER:
072 (1.00) d.
REFERENCE:
SDM-C71, pg 3, 4,
5 SDM-C22, pg 3 KA 295004K203
[3.3/3.3]
i 295004K203
..(KA's) i i
ANSWER:
073 (1.00) a.
REFERENCE:
SDM-C11 (RCIS), pg 18 Lesson Plan OT-3036-C11 (RCIS)
Learning Objective G i
KA 201004A305
[3.5/3.7]
f 201004A305
..(KA's)
{
t ANSWER:
074 (1.00)
C.
i t
I
?
i w
'tve
s l
REACTOR OPERATOR Pagel26 i
REFERENCE:
SDM-E12, pg 27,, 67, and Fig. E12-13 Lesson Plan OT-3036-E12 l
Learning Objective F.2 l
KR 203000K410
[3.9/4.1) 203000K410
..(KA's)
' ANSWER:
075 (1.00) b.
REFERENCE:
SDM-N33, pg 3, 4,
and 5 Lesson Plan OT-3036-N33 Learning Objective B and C KA 245000G004
[3.1/3.2) 245000G004
..(KA's)
ANSWER:
076 (1.00) l C.
REFERENCE:
SDM-N62, pg 9, 10 and Table N62-2 Lesson Plan OT-3036-N62 Learning Objective D KA 271000A115 (2.7/2.8) 271000A115
..(KA's)
ANSWER:
077 (1.00) a.
l
REACTOR OPERATOR Pagel27 i
REFERENCE:
T.S.
3.6.3.1 Lesson Plan OTJ3037-05 Learning Objective B.23 KA 295030G008
[3.4/4.4]
I 295030G008
..(KA's)
ANSWER:
078 (1.00) a.
REFERENCE:
SDM-N43, pg 1 Lesson Plan OT-3036-N43 Learning Objective B KA 245000G007
[3.5/3.6]
245000G007
..(KA's)
ANSWER:
079 (1.00) d.
REFERENCE:
T.S.
3.3.7.1-1 Lesson Plan OT-3037-07 Learning Objective B.1.H KA 272000G005
[2.9/3.9]
272000G005
..(KA's)
ANSWER:
080 (1.00) b*
REACTOR OPERATOR Pagel28
REFERENCE:
T.S.
3.5.1 Lesson Plan OT~3037-04 i
Lean.ing Objective B.4 i
KA'205000G005
[3.5/4.4]
205000G005
..(KA's)
' ANSWER:
081 (1.00) d.
REFERENCE:
ONI-N36 Lesson Plan-OT-3036-N36 Learning Objective F KA 295014G010
[4.0/3.9) 295014G010
..(KA's)
ANSWER:
082 (1.00) b.
REFERENCE:
ONI-C85-1, Rev 3, pg 1 I
Lesson Plan OT-3036-N32/C85 Learning Objective K
--KA 241000A203
[4.1/4.2) i 241000A203
..(KA's)
ANSWER:
083 (1.00) b.
i REACTOR OPERATOR Page129
REFERENCE:
T.S.
5.2.2 Lesson Plan OTJ3037-08 Learning Objective D.1 KA 295024K101
[4.1/4.2]
295024K101
..(KA's)
ANSWER:
084 (1.00) c.
REFERENCE:
.\\
PIE INTRO Lesson Plan OT-3402-01, pg 61 Learning Objective E 1
)
KA 295025G012
[3.9/4.5]
295025G012
..(KA's)
ANSWER:
085 (1.00) d.
REFERENCE:
SDM-C34, pg 7 NOTE:
SDM C34 indicates that 196 inches is normal level, but SDM B21 indicates that 201 inches is normal.
KA 295006K202
[3.8/3.8]
295006K202
..(KA's) i
' ANSWER:
086 (1.00) a.
REACTOR OPERATOR Page130
REFERENCE:
PEI-B13, RPV Flooding Lesson Plan OTJ3402-002-13, pg 14 KA 295025G012
[3.9/4.5]
295025G012
..(KA's)
_ ANSWER:
087 (2.00) a.
2 b.
7 c.
3 d.
1 (4 required at 0.5 each)
REFERENCE:
SDM-B21 (NBPI), Table 2 KA 295009K203
[3.1/3.2]
295009K203
..(KA's)
ANSWER:
088 (1.00) b.
REFERENCE:
T.S. 2.1.3 and Bases Lesson Plan OT-3037-02 Learning Objective B KA 295025K105
[4.4/4.7]
295025K105
..(KA's)
' ANSWER:
089 (1.00) b.
r REACTOR OPERATOR Page131
REFERENCE:
ONI-E12-2, Rev 4 Lesson Plan OT'3036-E12 Learning Objective L KA 295021A104
[3.7/3.7) l t
295021A104
..(KA's)
ANSWER:
090 (1.00) a.
REFERENCE:
l T.S.
3.9.8 Lesson Plan OT-3037-06 Learning Objective C.16 KA 295023G003
[2.9/3.8]
I 295023G003
..(KA's)
ANSWER:
091 (1.00) d.
REFERENCE:
ONI-E12-2, Rev 4, pg 2 j
KA 295021K102
[3.3/3.4]
295021K102
..(KA's)
A ?3"'"Ch.
092.
(1.00) i 1
~
w-
~
REACTOR OPERATOR Page132
REFERENCE:
Lesson Plan OT-3402-15, pg 6 Learning Objective C Note:
Offgas Bldg. is plausible distractor because it'normally receives discharge from SJAE and Recombiner areas of the Turbine Bldg.
SDM M36, pg 6.
295033K203 [3.7/3.9) 295033K203
..(KA's)
ANSWER:
093 (1.00) a.
REFERENCE:
OM4C, PEI-SPI Lesson Plan OT-3402-16 Learning Objective B Note:
Facility to ensure answer is correct.
295018K202 [3.4/3.6]
295018K202
..(KA's)
ANSWER:
094 (1.00) a.
REFERENCE:
ONI-R42-4, pg 1-3 Lesson Plan OT-3036-R42 Learning Objective F 295004G010 [3.2/3.4]
295004G010
..(KA's)
REACTOR OPERATOR Page133 ANSWER:
095 (1.00) b.
REFERENCE:
SDM-E22A SDM-C34 Lesson Plan OT-3035-E22A Learning Objective F.3 295008A106 [3.4/3.5]
295008A106
..(KA's)
ANSWER:
096 (1.00) d.
REFERENCE:
ONI-N62 Lesson Plan OT-3036-N62 l
Learning Objective F 295002G007 [3.2/3.2]
i 295002G007
..(KA's)
ANSWER:
097 (1.00) d.
j
REFERENCE:
i PAP-0118-Lesson Plan OT-3039-004-02 Learning Objective D 294001K104 [3.3/3.6]
294001K104
..(KA's)
' REACTOR OPERATOR Page 1
ANSWER KEY
~
b i
MULTIPLE CHOICE 018 b
001 c
019 c
002 MATCHING 020 d
i 3)(
021 d
a b
2j3 022 d
c 2j 3 023 c
d 36 024 d
3 MULTIPLE CHOICE 025 d
003 c
026 d
j 004 b
027 d
005 c
028 d
006 b
029 c
007 d
030 d
008 b
031 d
009 c
032 c
010 a
033 d
011 c
034 a
012 b
035 a
013 a
036 a
014 c
037 c
015 c
038 b
016 a
039 d
017 d
040 a
t
REACTOR OPERATOR Page 2
ANSWE.R KEY 041' d
059 a
042 c
060 c
043 a
061 d
044 c
062 b
045 b
063 b
046 d
064 d
047 b
065 b
048 c
066 c
049 c
067 c
050 c
068 b
051 MATCHING 069 b
a 5
070 d
b 3
071 c
c 2
072 d
d 1
073 a
MULTIPLE CHOICE 074 c
052 a
075 b
053 a
076 c
054 a
077 a
055 a
078 a
056 c
079 d
057
'a 080 b
058 a
081 d
?'!
.I
-REACTOR OPERATOR Page 3
l A N.S W E R KEY i
?
I
+
082 b
083 b
i 084 c
085 d
086 a
087 MATCHING h
a 2
b 7
)
c 3
i d
1 MULTIPLE CHOICE 1
088 b
089 b
t 090 a
i 091 d
l l
092 c
j 093 a
094 a
095 b
I J
-096-d
)
097 d
i I
i
.-.