IR 05000213/1996009
| ML20128R179 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/10/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20128R167 | List: |
| References | |
| 50-213-96-09, 50-213-96-9, NUDOCS 9610210321 | |
| Download: ML20128R179 (213) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION 1 Docket No.: 50-213 Report No.: 96-09 License No.: DPR-61 Licensee: Notheast Nuclear Energy C Facility: Connecticut Yankee Atomic Power Station (Haddam Neck)
Location: Haddam and Waterford, CT Dates: August 19 - 2d,1996 l
Chief Examiner: P. Bissett, Senior Operations Engineer / Examiner, Region I i Examiners: S. Barr, Operations Engineer / Examiner. Region i F. Jaggar, NRC Consultant Examiner J. Prell, Senior Operations Engineer / Examiner, Region l l
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Approved By: Glenn W. Meyer, Chief Operator Licensing and Human Performance Branch Division of Reector Safety .
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9610210321 961010 PDR ADOCK 05000213 V PDR
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EXECUTIVE SUMMARY Connecticut . Yankee Atomic Power Station inspection Report No. 50-336/96-09 Ooerations i
i The six reactor operator (RO) candidates and six senior reactor operator (SRO) candidates i were well prepared for the written and operating examinations. Simulator performance by ,
the candidates, including communications, was generally very good. All twelve candidates j passed their examinatio '
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l REPORT DETAILS 1. Operations 05 Operator Training and Qualifications 05.1 Reactor Operator and Senior Reactor Operator initial Examinations Scope The examiners administered initial licensing examinations to six senior reactor operator (SRO) candidates and six reactor operator (RO) candidates in accordance
! with NUREG-1021, " Examiner Standards," Revision 7. t the six SRO candidates,
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three were SRO instant (SROl) candidates and three wen SRO upgrade (SROU)
candidates, Qbservations and Findinas
The results of the SRO and RO examinations are summarized below: 'l SRO Pass / Fail RO Pass / Fail Total Pass / Fail Written 6/O 6/O 12/O Operating 6/O 6/0 12/0 Overall 6/0 - 6/0 12/0 Haddam Neck training and operations staff reviewed the written examination and assisted in the validation of the operating examination during the week of August 5,1996.- The staff was very cooperative and helpful throughout the entire !
validation process and provided high quality comments and recommendations on the proposed examination. Their involvement helped to ensure the technical accuracy l of the examination. ' All Haddam Neck personnel involved in the validation process
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signed security agreements to ensure that the proposed examinations were not compromised.
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j The operating examinations were conducted from August 19 through i
August 23,1996. The operating examinations consisted of 2 simulator scenarios and 10 JPMs for the RO candidates; 2 simulator scenarios and 5 JPMs for the SROU candidates, and; 3 simulator scenarios and 10 JPMs for the SROI candidate All JPMs were followed up with two system-related questions. All candidates were also examined concerning administrative requirements of the Haddam Neck facility.
l The written examinations were administered on August 24,1996. The written examinations consisted of 100 multiple choice questions for both the SROs and ROs. The training department was provided a copy of the as-administered written examinations immediately after the examination administration, as an opportunity to provide comments for any validity issues with the examination questions. No i formal comments, deletions, or corrections, however, resulted from this review.
I Based on the grading of the written examination, the following questions were l missed by more than half of the applicants, indicating a weakness in the general
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understanding of the subject.
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RO14/SRO13 Expected HPSI pump discharge pressure during a design basis '
LOC !
-RO19/SRO23 Magnitude of RCS temperature change due to rod movement at BO RO3 Effects of electrical breaker control during a loss of DC control power.
- RO36 Deenergization of DC emergency lighting following a station blackou RO40 RCS leakage classification I i
ROSO Response of RCPs to a loss of a DC bu ,
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RO89 incorporation of TPCs into NOP SRO39 Basis for having 2 CW pumps in operation during a radioactive liquid releas j SRO49 Required TS actions following a loss of MCC 1 l l
l SRO75 Shift Manager actions subsequent to a control room evacuation.
( SRO89 Procedure for exiting a RCA in which alpha contamination is
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Job performance measures were appropriately performed by all candidates during the walkthrough portion of the operating exam. All candidates appeared very knowledgeable of the purpose and location of plant equipmen I Simulator performance by the candidates was, for the most part, very goo '
Communications evaluations for all four crews ranged from acceptable to very good. The examiners noted that as time progressed through each scenario, i communications between crew members became more direct, succinct, and to the l point. One generic concern arose during the conduct of the simulator scenario
! portion of the examination. In this particular instance, two control rods remained stuck out following a reactor trip. In two instances, the RO candidates failed to bring this condition to the attention of the SRO. Followup discussion indicated that they were indeed aware of the condition, however did not feel that it was of such importance that the SRO needed to be interrupted and made aware of the situatio The examination team disagreed with this reasoning based on the fact that
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instances may occur in which multiple rods may remain stuck out and may factor in subsequent decision making on the part of the SRO. The examiners stated that all crew members should always be aware of present plant conditions. Facility representatives acknowledged the examiner's concern and stated that this area would be revisited during the next training cycl , Review of UFSAR commitments A recent discovery of a licensee operating their facility in a manner contrary to the updated final safety ananlysis report (UFSAR) description highlighted.the need for'a special focused review that compares plant practices, procedures and /or parameters to the UFSAR descriptions. While performing the preexamination activities discussed in this report, the inspectors reviewed applicable portions of the l UFSAR that related to the selected examination questions or topic areas. The i
particular areas looked at were Section 13.5, concerning plant procedures and Section 12.3, concerning radiation protection design features. No discrepancies were identified as a result of this revie Conclusions i
All of the twelve candidates were well prepared for both the written and operating that were administered. As a result, all 6 ROs and 6 SROs passed the examinations and were issued licenses. Crew communications were, for the most part, very good during the simulator portion of the examination. Licensed operator training personnel and operations personnel were extremely helpful in their efforts to ensure that the examination contents were valid and performance based. There were no l post-written exam comments provided to the NRC by Haddam Neck training I
representatives. Also, the simulator scenarios progressed as expected during the examination week. Overall, this indicated that a thorough review was performed by both operations and training personnel during the preexam review week.
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V. Manaaement Meetinas XI Exit Meeting Summary On August 23,1996, the examiners discussed their observations from the examination with Haddam Neck management. The examiners discussed generic applicant performance, including the concern with operator control board awarness as detailed in paragraph 5. above. The examiners also expressed their appreciation for the cooperation and assistance that was provided during both the preparation and examination week. Haddam Neck personnel present at the exit meeting included the following:
R. McBeth Connecticut Yankee Assistant Training Supervisor F. Nygard Connecticut Yankee Senior Operator Instructor J. Smith Northeast Utilities Manager, Operator Training i J. Stanford Connecticut Yankee Operations Manager j
Attachments:
l 1. RO Written Examination w/ Answer Key 2. SRO Written Examination w/Anwer Key i
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l U. S. NUCLEAR REGULATORY COMMISSION
- SITE SPECIFIC EXAMINATION SENIOR OPERATOR' LICENSE REGION 1 CANDIDATE'S NAME:
FACILITY: Haddam Neck REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 96/08/24 INSTRUCTIONS TO CANDIDATE:
Use the answer sheets provided to document your answers. Staple this cover 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 start CANDIDATE'S TEST VALUE SCORE %
100.00 % TO~ J 5 FINAL GRADE l
All work done on this examination is my ow I have neither given nor received ai Candidate's Signature
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SENIOR REACTOR OPERATOR Page 2 ANSWER SHEET Multiple Choice (Circle or X your choice)
-If you change your answer, write your selection in the blank.
l MULTIPLE CH0 ICE 023 a b c d 001 a b c d 024 a b c d 002 a b c d 025 a b c d 003 a b c d 026 a b c d 004 a b c d 027 a b c d 005 a b c d 028 a b c d 006 a b c d 029 a b c d 007 a b c d 030 a b c d 008 a b c d 031 a b c d 009 a b c d 032 a b c d 010 a b c d 033 a b c d 011 a b c d 034 a b c d 012 a b c d 035 a b c d 013 a b c d 036 a b c d 014 a b c d 037 a b c d l 015 a b c d 038 a b c d 016 a b c d 039 a b c d 017 a b c d 040 a b c d 018 a b c d 041 a b c d 019 a b c d 042 a b c d 1 020 a b c d 043 a b c d l 021 a b c d 044 a b c d a
022 a b c d 045 a b c d
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SENIOR REACTOR OPERATOR Page 3 ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
t 046 a b c d 069 a b c d l 047 a b c d 070 a b c d 048 a b c d 071 a b c d l
I 049 a b c d 072 a b c d j
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050 a b c d 073 a b c d
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051 a b c d 074 a b c d 052 a b c d 075 a b c d j _ _ _
053 a b c d 076 a b c d l
l 054 a b c d 077 a b c d 055 a b c d 078 a b .c d l 056 a b c d 079 a b c d 057 a b c d 080 a b c d
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058 a b c d 081 a b c d l
059 a b c d 082 a b c d 060 a b c d 083 a b c d 061 a b c d 084 a b c d 062 a b c d 085 a b c d 063 a b c d 086 a b c d 064 a b c d 087 a b c d 065 a b c d 088 a b c d l 066 a b c d 089 a b c d j
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l SENIOR REACTOR OPERATOR Page 4 ANSWER SHEET Multiple Choice (Circle or X your choice).
If you change your answer, write your selection in the blan a- b c d 1 093 a b c d 094 a b c d l
095 a b c d
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096 a b c d 097 a b c d 098 a b c d 099 a b c d l
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100 a b c d l
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! Page 5 l 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 penaltie . After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own end you have not received or given assistance in completing the examination. This must be done after you complete the examinatio . 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 room to avoid even the appearance or possibility of cheatin . Use black ink or dark pencil 0NLY to facilitate legible reproduction . Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer shee . Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND 00 NOT WRITE ON THE BACK SIDE OF THE PAGE.
i 7. The point value for each question is indicated in parentheses after the questio . If the intent of a question is unclear, ask questions of the examiner onl l l
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l Page 6 9. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper.
l l 10. To pass the examination, you must achieve a grade of 80% or greater, ,
l 11. There is a time limit of four (4) hours for completion of the examination.
( 12. 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 l denied or revoked.
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SENIOR REACTOR OPERATOR Page 7 QUESTION: 001 (1.00)
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Which ONE (1) of the following methods is used to reset a Differential Fault on the Diesel Generator?
a. Press the EG Normal Stop Pushbuttons and ECP Alarm Rese b. Reset the 87X Lockout Relay on EG breaker cubicle and close the Exciter Field Breaker inside the excitation cabinet, c. Take the EG breaker control switch on the Diesel Aux Board in the control room to the TRIP position and release to the AUTO positio '
d. Take the diesel output breaker control switch on the excitation panel to the TRIP position and release to the AUTO positio !
QUESTION: 002 (1.00) ;
A loss of all AC power has o
REGION 1
CANDIDATE'S NAME: ;
> l j FACILITY: Haddam Neck
L REACTOR TYPE: PWR-WEC4 i DATE ADMINISTERED: 96/08/24 INSTRUCTIONS TO CANDIDATE:
Use the answer sheets provided to document your answers. Staple this cover 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 start CANDIDATE'S TEST VALUE SCORE % ,
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100.00 % TOTALS FINAL GRADE All work done on this examination is my ow I have neither given nor received ai Candidate's Signature
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- REACTOR OPERATOR Page 2 l ANSWER SHEET
Multiple Choice (circle or X your choice)
If you change your answer, write your selection in the blan MULTIPLE CH0 ICE 023 a b c d ._
001 a b c d 024 a b c d
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002 a b c d 025 a b c d
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003 a b c d 026 a b c d
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004 a b c d 027 a b c d
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005 a b c d 028 a b c d
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'. 006 a b c d 029 a b c d
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007 a b c d ___
030 a b c d 008 a b c d _
031 a b c d 009 a b c d 032 a b c d 010 a b c d 033 a b c d 011 a b c d 034 a b c d
012 a b c d ___
035 a b c d 013 a b c d 036 a b c d
, 014 a b c d ___
037 a b c d 015 a b c d ___
038 a b c d 016 a b c d 039 a b c d
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017 a b c d 040 a b c d l 018 a b c d 041 a b c d
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019 a b c d 042 a b c d
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020 a b c d 043 a b c d
021 a b c d ___
044 a b c d
022 a b c d 045 a b c d
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REACTOR 00ERATOR Page 3 ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blan a b c d 069 a b c d 047 a b c d 070 a b c d 048 a b c d 071' a b c d 049 a b c d 072 a b c d 050 a b c d 073 a b c d I
i 051 a b c d 074 a b c d
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052 a b c d 075 a b c d 053 a b c d 076 a b c d 054 a b c d 077 a b c d _
055 a b c d 078 a b 'c d 056 a b c d 079 a b c d 057 a b c d 080 a b c d 058 a b c d 081 a b c d
059 a b c d 082 a b c d 060 a b c d 083 a b c d 061 a b c d 084 a b c d 062 a b c d 085 a b c d 063 a b c d 086 a b c d 064 a b c d 087 a b c d l 065 a b c d 088 a b c d
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( 066 3 b c d 089 a b c d 067 a b c d 090 a b c d
, 068 a b c d 091 a b c d t
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REACTOR OPERATOR-Page 4 ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
092 a b c d 093 a b c d'
094 a b c d 095 a b c d 096 a b c d 097 a b c d 098 a b c d 099 a b- c d ____
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100 a b c d -
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Page 5 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 i and could result in more severe penaltie . 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 received or given assistance in completing the examination. This must be done after you complete the examinatio . Restroom trips are to be limited and only one applicant at a time may i leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheatin . Use black ink or dark pencil 0NLY to facilitate legible reproduction . Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer shee ;
6. Mark your answers on the answer sheet provide USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAG . The point value for each question is indicated in parentheses after the questio . If the intent of a question is unclear, ask questions of the examiner only.
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i Page 6 9. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer ' sheets. In addition, turn in all scrap pape . To pass the examination, you must achieve a grade of 80% or greate . There is a time limit of four (4) hours for completion of the examinatio . When you are done and have turned in your examina. tion, leave the i
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 revoke l
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REACTGR OPERATOR t' age 7 QUESTION: 001 (1.001 Which ONE (1) of the following methods is used to reset a Differential Fault on the Diesel Generator?
a. Press the EG Normal Stop Pushbuttons and ECP Alarm Rese b. Reset the 87X Lockout Relay on EG breaker cubicle and close the Exciter Field Breaker inside the excitation cabine c. Take the EG breaker control switch on the Diesel Aux Board in !
the control room to the TRIP position and release to the AUTO positio I d. Take the diesel output breaker control switch on the excitation {
panel to the TRIP position and release to the AUTO positio I QUESTION: 002 (1.00)
A loss of all AC power has occurred, but the diesels are not runnin An operator dispatched to investigate reports a START FAILURE alarm on all diesel control panels. The operator then depresses the normal shutdown pushbuttons and resets the engine control panel alarm. What effect does this have on the diesel?
a. Prevents diesel start for 11.5 minute b. Causes another start attempt, c. Prevents diesel start until the start failure lockout is rese d. Aligns the diesel for a manual start attemp .
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QUESTION: 003 (1.00)
What effect'does a loss of DC control power have on a 4 KV breaker?
a. Control room operation is lost, but breakers can be operated !
locally by manual spring charging and actuation of operating l
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mechanisms.
t l b. Stored energy breakers can be operated from the control room; solenoid operated breakers can only be operated locall c. Stored energy breakers can be locally closed or opened; solenoid operate'd breakers can only be locally opened.
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manual spring charging for local operatio l i !
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Which of th.a following describes an interlock for operation of RCS loop isolation valves?
a. Loop T-cold may not be more than 20 deg F below any other loop T-cold in order to open that loop's cold leg isolation valve, b. Loop T-cold must be within 32 deg F of all loops ave i-cold in order to open that loop's isolation valve c. The cold leg isolation valve cannot be opened in a loop with a running RCP unless the bypass valve is open as well, d. Loop T-ave must be within 12 deg F of T-ave of the other loops i to open that loop's isolation valves.
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REACTOR OPERATOR Page 9 QUESTION: 005 (1.00)
Which of the following describes steam generator level response if the controlling level channel fails LOW 7 a. Level increases until overfill protection is actuated at 74%,
resulting in reactor tri b. Level initially increases, then stabilizes above progra c. Level will continue to control at the same setpoint value since SGWLC will automatically select an alternate level channe d. Level will ' irol 5% below setpoint at the level deviation setpoin QUESTION: 006 (1.00)
Why is it necessary to have a Low Temperature Overpressure Protection !
system? I l
i a. At low RCS temperature, RHR is placed in service - RHR design j pressure is lower than RCS design pressur '
b. At low RCS temperature, the RCS can fail at substantially lower ,
pressure than it would fail at normal opercting temperatur I c. At low RCS temperature, pressure transients are faster due to the ineffectiveness or unavailability of pressurizer spra d. At low RCS temperature, differential expansion may bind pressurizer safeties, requiring an alternate powered overpressure system.
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REACTOR OPERATOR Page 10 QUESTION: 007 (1.00)
What effect does a loss of Semi-Vital 120 VAC have on the performance of FR-H.1?
a. Loss of semi-vital power may CAUSE entry into FR-H.1 by creating a common mode failure to start of all auxiliary feed pump I b. Initiation of feed and bleed cooling may be hampered because one pressurizer PORV would be inoperabl c. Mitigation may be hampered because two main feed regulating valves fail shu ,
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d. Initiation of feed and bleed cooling would be prevented because BOTH PORVs are inoperabl l QUESTION: 008 (1.00)
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l Which of the following is a backup source for containment spray? !
a. Service water b. Fire water c. Demineralized water d. Primary makeup water l
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REACTOR OPERATOR Page 11 I
QUESTION: 009 (1.00)
What interlock protects the RHR system from overpressurization?
a. RHR cannot be placed in service unless LTOP is arme b. RHR isolation valves cannot be opened if RCS pressure is over 400 psi c. RHR suction valve will not open if loop 1 or 2 T-hot is over 325 deg d. RHR isolation valves auto close if pressure exceeds 380 psi QUESTION: 010 (1.00)
What is the allowable deviation of pressurizer level from program, and how soon must level be restored to within this tolerance following a transient or power maneuver? I a. +/- 5%; I hour l b. +/- 2%; 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> c. +/- 5%; 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> d. +/- 2%; I hour QUESTION: 011 (1.00)
The plant is in hot standby. What is the RCS pressure safety limit, and how quickly must pressure be reduced if this limit is exceeded?
a. 2335 psig; 30 mi b. 2435 psig; 5 min, c. 2585 psig; 30 mi d. 2735 psig; 5 mi . . . . -_ _- - . .
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QUEST' 0N: 012 (1.00)
The plant is operating at 100% when the following occurs:
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LD-TCV-113A shifts to the VCT position.
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LD-TCV-113B automatically closes isolating fow to R2 Which ONE (1) of the following events woulu initiate these actions?
a. VCT level reached 87%.
b. Excessive letdown flow through the demineralizer c. CCW temperature control valve (CC-TCV-112) for the NRHX failed close d. Letdown pressure at the demineralizers exceeded 200 psi QUESTION: 013 (1.00)
What is the purpose of the RCP #1 seal bypass valve?
a. Ensures adequate flow to #2 & #3 RCP seals when #1 seal leakoff is lo b. Provides additional cooling flow for the lower bearing under certain condition c. Allows meeting minimum leakoff flow criteria for pump starts at low RCS pressure, d. Diverts hot water flowing past thermal barrier to VCT if seal injection is lost.
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REACTOR OPERATOR P. age 13 i
QUESTION: 014 (1.00)
A design basis LOCA has occurred and SI has initiated. As the RWST pumps down, an auxiliary operator is dispatched to verify normal operation of the HPSI pumps. What should the operator observe for HPSI pump discharge pressure?
a. 1300 - 1450 psi b. 800 - 1000 psi l c. 230 - 320 psig
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d. 40 - 60 psi QUESTION: 015 (1.00)
The main steam header pressure transmitter PT-1203 has failed low during :
a reactor trip / turbine trip from 100% power. How will tha HPSD system pressure control valves respond during the trip?
a. PCVs will remain closed following the tri b. PCVs will open and remain full open following the tri c. PCVs will fully open and remain open once Tave is greater than 545 degress d. PCVs will fully open when Tave is greater than 545 degrees F, then ramp close as temperature decreases from 544 degrees F to full close at 535 degrees .
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REACTOR OPERATOR Page 14 QUESTION: 016 (1.00)
l Which of the following describes the difference in operation of the pressure control valves versus the temperature control valves in the i high pressure steam dump system?
a. The temperature control valves trip open sequentially as temperature error increases; the pressure control valves !
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modulat I b. The pressure controller signal is disabled until Tave decreases below 535 degrees F following a reactor tri c. The pressure control valves respond to the auctioneered high signal from either the pressure or temperature controller I d. All valves respond to the pressure controller; only the temperature control valves respond to the temperature l I
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l What is the difference between the high pressure and low pressure steam '
dump systems? I a. The high pressure steam dump system controls plant temperature and pressure following a trip; the low pressure steam dump system is used for cooldow b. The high pressure steam dump system is used for pressure and temperature control; the low pressure steam dump is a turbine overspeed protection syste c. The low pressure steam dump system backs up the high pressure steam dump system by dumping steam from the high pressure turbine exhaus l d. The low pressure steam dump system operates below 20% power as indicated by turbine first stage pressure; the high pressure system operates above 20%.
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QUESTION: 018 -(1.00)
The plant is operating at 100% power. A loss of both generator air side seal oil pumps occurs. What provides seal oil under these conditions?
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a. Main oil pum b. Standby seal oil pump auto start c. DC oil pum d. Turning gear oil pump after required turbine tri . QUESTION: 019 (1.00)
Tave is 535 degrees F at beginning of life conditions. Which ONE (1) of the following actions will force Tave to increase to 536 degrees F?
a. Move Bank B control rods from about 280 steps to about 283 step b. Move Bank B control rods from about 283 steps to about 280 step ,
c. Move Bank B control rods from about 310 steps to about 313 step d. Move Bank B control rods from about 313 steps to about 310 steps.
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i REACTOR OPERATOR Page 16 QUESTION: 020 (1.00)
i In which of the following circumstances would RCPs be run without meeting normal start criteria?
a. Initial start when filling and venting RCS after a refueling outag b. CETs greater than 1200 deg F in FR- c. Recovery from feed and bleed cooling in FR- d. RCS depressurization in E- I
I QUESTION: 02] (1.00) !
i After the completion of the first 4 steps of E-0, when must the RCPs be l i
tripped in the event of a loss of all component cooling pumps? Immediately When bearing temperatures exceed 180 deg Within 5 minute If minimum seal injection flow cannot be maintaine l QUESTION: 022 (1.00)
The plant is operating at 90% power. You observe generator load, Tave, and steam pressure decrease slightly while nuclear power increase Which of the following could cause these indications?
a. Lowering condenser vacuu b. One HPSD valve failing open, c. Loss of a feedwater heater string.
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d. Turbine control valve drifting shut.
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QUESTION: 023 (1.00) !
The aux feed system provides high discharge header temperature alarm What is the significance of such an alarm? It indicates a pump being run for an excessive time against shutoff hea It indicates terry turbine shaft seal leakage into the pum It indicates check valve backleakage and possible pump vapor bindin It indicates inadequate pump cooling flo !
QUESTION: 024 (1.00)
l The plant is operating at 75% with rods in AUTO during a load ascensio A continuous rod withdrawal initiates. Which of the following describes how this will affect the variable lower pressure trip (VLPT) setpoint? The setpoint will decrease because of RCS pressure increase l The setpoint increases because RCS pressure decreases after pressurizer spray initiate The setpoint increases because Tave increases, The setpoint increases because of shifts in QPTR and AF .
A 4 e<-,-+ - -- n-~m A --n-4a4 -- m- e
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REACTOR OPERATOR Page 18 QUESTION: 025 (1.00) i l
A reactor trip has occurred from 100%. The turbine has not tripped i either automatically or manually. What is the next required action?
l Trip the turbine locall l Shut the main steam trip valve Manual runbac Manual safety injection.
QUESTION: 026 (1.00)
The plant was operating at 100% when a reactor trip and safety injection occurred. The following conditions exist: 4
- SI on low pressurizer pressur Pressurizer level initially went to zero, then came back on scale and rapidly climbed to 100%
- RCS pressure is 1100 psig and slowly decreasin Containment radiation channels are alarmin Which of the following would cause these indications?
a. Small cold leg LOC b. Pressurizer PORV failed ope c. Small hot leg LOC d. Steamline brea _
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REACTOR OPERATOR Page 19 QUESTION: 027 (1.00)
The plant is at 85% power. The R0 notices that the rods are driving in, and that RCS temperature has ramped down from 552 degrees F to 535*F and that steam header pressure is decreasing. What is the most probable cause for this transient?
a. Pressurizer pressure increasin b. T-hot failed hig c. First stage pressure failed low, d. NI channel failed hig QUESTION: 028 (1.00)
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A RCP can be operated without seal injection water during abnormal l conditions provided:
a. The pressure differential across the labyrinth seal exceeds 60 inches wate b. RCP seal leakage is 7 gpm or less.
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REACTOR OPERATOR Page 20 QUESTION: 029 (1.00)
Which of the following statements best describes the operation of the demineralizer bypass valve, LD-TCV-113A7 a. Normally bypass the demineralizers when letdown temperature is less than 140 degrees b. Auto control of the valve is provided from TC-111 (letdown temperature out of the regenerative heat exchanger).
c. On a loss of containment air, the valve fails to the demineralizer positio d. Valve repositions to the VCT when letdown temperature increases to 140 degrees F.
QUESTION: 030 (1.00)
Why are there baskets full of tri-sodium phosphate located adjacent to the containment sump?
a. Decrease pH of sump water to prevent boric acid induced corrosion damage to carbon steel components in containment after a LOC b. Decrease pH of sump water to minimize corrosion induced H2 !
generation in containment post accident condition I c. Increase pH of sump water to minimize fouling of containment !
spray nozzles and RHR heat exchanger heat transfer surfaces, which will be unaccessible for maintenance following a LOC d. Increase pH to minimize the possibility of corrosion cracking in certain metal components following a LOC l
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I REACTOR OPERATOR Page 21 QUESTION: 031 (1.00)
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When pumping down the containment sump, where is the sump liquid pumped to? ;
a. Aerated drains tanks, b. Primary drains tan c. Volume control tank, d. Waste test tan !
QUESTION: 032 (1.00)
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An unrecoverable loss of control air is in progress. Which of the 4 following components must be tripped or closed by the operators to 1 prevent damage to that component?
a. Terry Turbine b. Main Steam Trip and Bypass Valve c. Main Turbine, d. Reactor Coolant Pumps.
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QUESTION: 033 (1.00)
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A plant trip has resulted from a loss of control air. Which of the following is a method for controlling plant temperature?
a. Through nitrogen backup to the atmospheric relief for each S b. Through nitrogen backup to a common atmospheric dump for all SG c. Through rolling the main turbine with steam supplied through MS trip valve bypass valve d. Through secondary feed with AFW pumps and bleed through blowdow l I
QUESTION: 034 (1.00) j
l When do you trip the reactor during a loss of control air?
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a. 90 psig decreasing b. 80 psiq decreasing c. 65 psig decreasing
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d. 50 psig decreasing QUESTION: 035 (1.00)
Why must level in a ruptured steam generator be fed greater than 7%?
a. To prevent chemical dryout on uncovered tube b. To maximize available heat transfer are c. To allow RCS depressurization without depressurizing the SG.
i d. To ensure dilution of RCS activity by mixing with clean l secondary water.
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REACTOR OPERATOR Page 23 l
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- QUESTION
- 036 (1.00)
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Following a station blackout, how long does the operator have to deenergize DC emergency lighting?
a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, b. Within 1 1/2 hour l c. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, d. Within 2 1/2 hour i
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QUESTION: 037 (1.00)
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Which of the following is not a means of reducing RCS presssure in E-37 a. Normal spra b. Aux spra c. Pressurizer PORV d. Secure heaters and reduce pressurizer leve QUESTION: 038 (1.00)
The plant is at 100% power with all systems in AUT What is your first action in response to a continuous rod insertion?
a. Place rods in manual and withdraw to their original position.
l b. Verify no T-ave /T-ref deviatio c. Place rods in manual, adjust turbine load to match Tave & Tre d. Place rods in manual, trip the reactor if motion continues.
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QUESTION: 039 (1.00) f l
l The plant is operating at 80% power. A rod drop occur How is plant temperature stabilized?
a. Allow automatic rod withdrawal to compensate for the' insertio b. Dilut ;
c. Manually reduce turbine loa d. Manually withdraw rods OR reduce load at SCO's discretio l
l QUESTION: 040 (1.00)
Leakage past the reactor vessel flange 0-rings is detecte How would this leakage be classified?
a. Pressure boundary leakag b. Identified leaPege, c. Uncontrolled leakag d. Unidentifed leakag QUESTION: 041 (1.00)
Which of the following are the parameters on the Safety Limit curve?
a. Outlet temperature, RCS pressure, % powe b. RCS pressure, inlet temperature, RCE flo c. % power, inlet temperature, RCS flow, d. RCS pressure, inlet temperature, % powe . - . . = . _ _ - - - - - - . ..
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l REACTOR OPERATOR Page 25 QUESTION: 042 (1.00) j Whose authorization is required to perform a reactor startup following a safety limit violation?
a. NRC b. Manager Technical Support c. Chief Nuclear Officer d. Outage Manager QUESTION: 043 (1.00) i Why must the normal charging path be isolated to establish aux spray?
a. To prevent runout of the inservice charging pum b. To prevent excessive diversion of seal injection flo c. To ensure flow goes to the pressurh9r rather than the loop d. To prevent steam blowback into the loop QUESTION: 044 (1.00)
There is a fire in the control roo PORVs have started to cycle spuriousl What action is required?
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a. Shut the block valves, b. Reduce RCS pressure to try to keep the PORVs shut, c. Place the SB-1 switches for the PORVs in the CLOSE positio d. Initiate safety injection.
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l QUESTION: 045 (1.00)
How is shutdown margin verified to be within limits with the plant at 100% power?
a. Perform a shutdown margin calculation per the Technical Requirements Manua b. Verify shutdown banks are fully withdraw c. Verify a'll control rods are above insertion limit d. Verify boron concentration is sufficient to ensure 2000 pcm SDM in the event of a trip which places the plant in the HZP ARI conditio QUESTION: 046 (1.00)
What is the purpose of the pressure compensation input to rod control?
a. This turbine first stage pressure signal is used in conjunction with flux compensation to generate a rate of power mismatch input for rod speed and direction calculatio b. This pressurizer pressure compensation signal provides an anticipatory temperature input since plant pressure responds l faster than loop RTDs.
c. This direct input from turbine first stage pressure to rod control provides an anticipatory temperature input by bypassing the signal processing delay associated with T-ref calculatio d. This pressurizer pressure compensation allows fine tuning of the l nuclear flux input to adjust for fluctuations due to variations in void fraction due to nucleate boiling.
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REACTOR OPERATOR Page 27 QUESTION: 047 (1.00)
The plant has been shutdown for one week and is at is at mid-loop for maintenance. Two steam generators are drained for inspection; the other two are at normal shutdown level. A loss of RHR occurs. How long until core uncovery?
a. Less than I hour, b. Approximately 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> c. Approximately 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> d. More than 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> QUESTION: 048 (1.00)
What is the reason for checking RCS pressure when initiating emergency boration in FR-S.1?
a. To ensure PORVS/ Safeties are maintaining RCS pressure within limits, b. To determine if action is necessary to ensure pressure is low enough for charging to inject boro c. To check for conditions requiring charging pump tri d. To determine if RCS depressurization is required to use Si as an alternate injection path.
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l QUESTION: 049 (1.00)
! Which of the following lists 3 of the inputs to rod control?
l a. Tave, Tref, Delta- b. Power range deviation drawer rate signal, Tave, Tre c. Rate of change of difference between NI power and Turbine power, Tave, Tref, d. Tave, Tref, generator load.
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l QUESTION: 050 (1.00)
i During RCS draindown to midloop, indicatioas of an air bound in-service l RHR pump are observed. What action.is required?
l a. STOP the running pump and START the standby pum b. STOP the running pump.
l c. Commence raising level; maintain the RHR pump in service for l core cooling.
! d. Halt draindown, reduce RHR flow until cavitation indications clear.
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i QUESTION: 051 (1.00)
What parameter determines Rod Insertion Limits?
a. Mega-watts thermal power b. PRNI nuclear power
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c. Turbine first stage pressure d. Tave
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REACTOR OPERATOR Page 29 QUESTION: 052 (1.00)
When must the plant be tripped in response to a loss of condenser vacuum?
a. If decreasing condenser vacuum cannot be stabilized with a second set of air ejector b. Less than 21.5 in Hg vacuum, c. If decreasing vacuum is due to a clogged waterbox tubeshee d. When decreasing vacuum has blocked steam dump actuatio QUESTION: 053 (1.00)
Post-LOCA, CD 1/2 and one other radiation monitor can be used to determine if severe fuel damage has occurred. The other monitor is:
i a. R-31, Containment Manipulator Crane '
b. R-32, Containment Charging Floor I c. R-37, Containment Hatch d. R-14A, Stack Monitor ,
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l QUESTION: 054 (1.00) I Which of the following radiation monitoring channels are isolated by an HCP signal?
a. Rll, R12
- b. R15, R16A & B c. CD-1 & 2, R-32
l d. R-14A, R-31 I
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QUESTION: 055 (1.00)
What is the maximum temperature indication available from the CETs, and what temperature reading would require use of FR-C.1? I a. 2300 deg F; 1200 deg F b. 2000 deg F; 1000 deg F c. 1800 deg F; 900 deg F d. 1200 deg F; 700 deg F l l
QUESTION: 056 (1.00)
The plant is at midloo A loss of all AC occur What method is available for RCS makeup?
a. Terry turbines powered from house heating ste b. Gravity feed from RWS c. Diesel fire pump d. Portable generator power for desired pump QUESTION: 057 (1.00) ,
Why is the turbine tripped in the event of an ATWS7 a. To prevent turbine overspee :
b. To conserve SG inventory against the possibility of a loss of I all fee l l
c. To prevent SI from excessive cooldown.
I d. To shift steam load to the steam dumps, which will modulate
! closed with boration or manual rod insertion.
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QUESTION: 058 (1.00)
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Which of the following is NOT an available method to verify reactor trip l during a station blackout?
j a. Neutron flux decreasin l l
b. Rod bottom lights li !
c. Intennediate rarae startup rate negative.
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d. Source range startup rate negative.
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l QUESTION: 059 (1.00) ;
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The plant is at 100% power with all systems in AUT The upper detector for PRNI channel 4 fails low. If channel 4 is selected for input to rod i control, how will the rod control system respond?
a. Rods will step in until the flux rate signal decays.
b. P.ods will step in continuously due to NI vs turbine power mismatc c. Rods will not mov d. Rods will step out (until a rod stop is reached) due to anticipated temperature erro I l
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! QUESTION: 060 (1.00)
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A plant transient occurs. You observe the followin One rod bottom light energize Associated IRPI indicates the rod at zer T-ave above T-ref and increasin No initial pressurizer pressure or level decreas Which of the following would cause these indications?
a. Dropped rod with rods in MANUA b. Dropped rod indication due to failed low IRP c. Dropped rod with rods in AUT d. Dropped rod with failure of turbine to run bac QUESTION: 061 (1.00)
The plant is operating at 100% power. One RCP trips, but the reactor scram breakers do not open. With no operator action, which of the following indicates the plant response?
a. AFW ac'uation t
S. Main steamline isolation c. SI d. Main feed isolation l
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REACTOR OPERATOR Page 33 QUESTION: 062 (1.00) l i
When operating at 100%, the following indications occur:
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HI-LO seal water return flow annunciato #3 RCP seal water return pegged hig Labryinth seal dP indicates negative 30 inche ,
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Lower bearing temperature indicates 150 degrees F and increasing !
rapidl j What actions are require Reduce power below P-8, then trip the pum Shut #3 seal return valve commence a rapid shutdown if lower bearing'
temperature does not stabilize within 5 minute ,
1 Trip the pum i Trip the reactor, then trip the pum I QUESTION: 063 (1.00)
Which combination of RCPs gives the most spray flow?
a. I and 2 b. 1 and 3 c. 2 and 3 d. 3 and 4
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QUESTION: 064 (1.00)
The plant is at 100% power when RCS Tave fails low. What effect does I this have on final pressurizer level?
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I a. Level decreases because T-ave determines program leve !
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c. Level is unaffected because T-ref determiner program leve I l
d. Level increases because rods start stepping ou l
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QUESTION: 065 (1.00)
Which of the following states actions that should be completed prior to evacuating the control room due to a fire?
a. Trip the reactor and turbine, safety injec b. Trip the reactor and turbine, place PORV SB-1 switches in clos c. Trip the reactor and turbine, commence emergency boratio d. Trip the reactor, turbine, and RCPs; initiate aux fee QUESTION: 066 (1.00)
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The control room has been evacuated. A0P 3.2-50 " Operations Outside the Control Room" has been completed. Plant cooldown is in progress. How is cooldown rate monitored?
a. L' west loop Tav b. Steam generator saturation temperature, c. CETs and loop Tc.
I t d. CETs and SG saturation temperatur j i
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I REACTOR OPERATOR Page 35 QUESTION: 067 (1.00)
I What is the response of the main feed reg valves to a turbine trip from 100% power?
a. They remain as i b. They fully open, then close when aux feed initiate c. They fully open, then close when Tave decreases below 545 degrees d. They trip shut with the turbine trip, but may be reopened if above 545 degF.
i QUESTION: 068 (1.00)
An SI with loss of offsite power has occurre Which of the following will not automatically start?
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REACTOR OPERATOR Page 36 QUESTION: 069 (1.00)
The DC bus breaker supplying the C vital inverter trip What effect does this have on the associated instrument bus?
a. C bus transfers to its backup inverte l b. C inverter transfers to "B" 125 VDC bu c. C bus is deenergize d. C inverter transfers to its backup AC source QUESTION: 070 (1.00)
Which of the following provides an alternate direct suction source for the AFW pumps?
a. Condensate storage tank b. Main condenser hotwell c. Fire main d. Primary water storage tank QUESTION: 071 (1.00)
Where do the terry turbine aux feed pumps exhaust to?
a. Main condenser b. Gland exhaust condenser c. Atmosphere d. Floor drain system
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QUESTION: 072 (1.00)
i What effect does a loss of control air have on the aux feed system?
a. Main feed bypass valves fail ope b. Main feed bypass valves fail open; turbine AFW pumps steam admission valves fail open resulting in pump star c. Main feed bypass and turbine AFW steam admission valves fail shu d. Main fed bypass valves fail shut; turbine AFW pump steam i admission valves fail open resulting in the pumps running in j recirculatio j
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QUESTION: 073 (1.00)
Which ONE (1) of the following events will result from the Boric Acid l Flow control valve BA-FCV-1128 failing closed during automatic makeup to the VCT7 a. Decrease in shutdown margi b. Inadvertent boration from the RWS c. Inadvertent boration from the BAM d. Loss of suction to the BA pump .
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REACTOR OPERATOR Page 38 QUESTION: 074 (1.00)
Given the following conditions:
1. The plant is in MODE . One (1) source range neutron flux monitor is out of servic . The source range audio count rate drawer is out of servic . Core alterations are in progres Which ONE (1) of the following technical specification action statements should be implemented?
a. Suspend'all operations involving positive reactivity change b. Emergency borate the RCS until a boron concentration of 2150 ppm is establishe c. Immediately evacuate the refueling area until the audio count rate is returned to service, d. Immediately determine remaining source range neutron flux monitors are operable by performing SUR 5.1-0A, " Steady State Operational Surveillance - Mode 6."
QUESTION: 075 (1.00)
During normal operation, a low level alarm on the spent fuel pool (SFP)
al arms . It is decided to raise the level to the normal band. Which ONE (1) of the following is the preferred method of raising the level in the SFP?
a. Align the purification pump to take a suction on the RWS b. Align the purification pump to take a suction on the RWST, and isolate the SFP purification system, c. Direct water from the charging blender directly to the SFP cooling syste d. Line up the primary water header to the SF ._ _ . . . . _ . - - - . - . . . - . - .-
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QUESTION: 076 (1.00)
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Which ONE (1) of the following conditions indicates an adverse
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containment at the present time?
a. Containment dose rate is 1 X 10E4 R/h b. Containment pressure is 7 psi c. Containment temperature'is 200 degrees F.
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d. Containment integrated dose is 1 X 10E3 R.
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! QUESTION: 077 (1.00)
{' The reactor is critical at lE-2% power. Vital inverter 8 output breaker trips open resulting in a loss of vital bus Which of the following will result?
a. Loss of SR2, WR2, PR2 nuclear instrument channels.
l b. Reactor trip due to deenergization of WR2. instrument channel.
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c. Reactor trip due to deenergization of SR2 instrument channel.
j d. Reactor trip due to indicated WR High SUR.
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QUESTION: 078 (1.00)
L Given the following conditions:
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1. The plant is being shutdown to HOT STANDBY due to a steam
[ generator tube leak.
i Which ONE (1) of the following procedurally does NOT require a reauor
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t m and entry into E-0, " Reactor Trip or Safety injection?"
l a. When leakage exceeds 40 gpm.
! b. When all available charging pumps are running and letdown has j automatically throttled to minimum.
-[ c. When letdown flow combined with the tube rupture flow exceeds i charging pump capacity and pressurizer pressure cannot be
, maintained.
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i d. When charging flow reaches maximum output with all available
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charging pumps running.
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} QUESTION: 079 (1.00)
l 3 A high containment pressure (HCP) signal causes valve operations which l
) isolate certain radiation monitors. Which of the following: (i) lists
, radiation monitors isolated on a HCP signal, and (ii) correctly states 1 whther these monitors may or may not be unisolated prior to reset of the HCP signal?
a. SG blowdown, letdown; may be unisolated prior to HCP rese b. Containment particulate and gas, SG blowdown; may not be ,
unisolated prior to HCP rese ;
c. Containment particulate and gas, SG blowdown, letdown; may be ,
unisolated prior to HCP rese '
d. Containment particulate and area radiation; may not be unisolated prior to HCP rese . ~ .. . - _ _ . _ - -- . - .. - .. -
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QUESTION: 080 (1.00)
Assuming no operator action, how will the reactor coolant pumps (RCP)
respond to a reactor trip due to a loss of DC Bus B/BX?
a. RCPs 1 & 3 will trip 52 seconds after the turbine trip, while RCPs 2 & 4 will remain running on offsite powe b. RCPs 1, 2, 3, will shutdown 52 seconds after the turbine trip,
- while RCP 4 will remain running on offsite powe c. All four RCPs will automatically trip at the time of the turbine tri d. All four RCPs shutdown 52 seconds after the turbine trip.
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QUESTION: 081 (1.00)
, While operating at 100% power, an operator receives a "C" and "D" Vital l
AC Trouble alarm and no other alarms. Upon investigation, it is determined that the "C" inverter failed. Why was power not lost to Vital "C" loads?
a. Vital inverter "C" static switch transferred to inverter "D" output.
I b. Vital inverter "C" static switch transferred to MCC-12 CVT l suppl c. Vi.. . invert:r "C" crosstie switch transferred to inverter "0" outpu d. Vital inverter "C" static switch transferred to inverter "A" output.
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REACTOR OPERATOR Page 42 QUESTION: 082 (1.00)
E0P 3.1-48 " Cavity Seal Failure," immediate action states that in the l event of a cavity seal failure accident, the irradiated fuel assembly i being moved outside the core envelope should be stored. Which one of the following is a " stored location" as defined in E0P 3.1-4 a. Lowered to the bottom of the refueling cavity and unlatche b. Suspended from the refueling machine and latched, c. Lowered to the bottom of the transfer canal in a predetermined spot, and unlatche d. Placed into the fuel transfer car with fuel transfer car in the vertical and unlatched.
QUESTION: 083 (1.00)
The following plant conditions exist:
1. Cold shutdow . RCS temperature at 150 degrees . B RHR pump runnin . B and C CCW pumps runnin The plant experiences a total loss of offsite power. Which of the following indicates the necessary operator action (s) in order to maintain CCW cooling to the RHR heat exchangers?
a. Verify one (1) CCW pump automatically sequences onto each emergency diesel generato b. Verify that the CCW pumps automatically start on low discharge pressure after the 480 busses are reenergized from their respective emergency diesel generator c. Manually start a CCW pump after verifying its associated 480V bus reenergize d. Reset the 480V bus undervoltage lockout relay for the CCW pump to be started, and then start the CCW pum _ _ - .. . . ___ . _ . __ .. . _ _ _ _ .
.
. 1 REACTOR OPERATOR Page 43 QUESTION: 084 (1.00)
Given the following conditions:
1. All fire system components are in their normal opeerating alignmen . Fire system pressure decreased to 75 psig due to a leak and has subsequently beeen restored to 125 psi . Assume no operator actions have been take Which ONE (1) of the following describes the operating status of the l Fire system?
Pressure Maintenance Electric Pump Diesel Pump Pump ON ON ON ON OFF 0FF FF ON ON t FF 0FF 0FF
!
QUESTION: 085 (1.00)
Given the following conditions:
1. The plant is in MODE 2 at 3% power and slowly increasin . Tavg indicates 523 degrees F.
! Which ONE (1) of the following actions complies with Technical Specification 3.1.1.6, " Minimum Temperature for Criticality?"
a. Restore Tavg to 525 degrees in 15 minute ,
b. Restore Tavg to 530 degrees in 30 minute c. While the RCS Tavg is less than 535 degrees, log savg once per l 30 minutes.
d. While the RCS Tavg L ~2ss than 535 degrees, log Tavg once per
,
hour.
,
_ . . __ _ - - _ - _ . _ _ _ - _ . _ _ _ ._ _ _ _ . . _ _ _ _ . . . _ _ . . . _ _ _ _ _ . _
.
REACTOR OPERATOR Page 44 l
l l QUESTION: 086 (1.00)
Which ONE (1) of the following is an indication of an intersystem LOCA through the core deluge check valves?
a. RWST level is decreasing faster than HPSI/LPSI injection flo b. RWST temperature is increasing.
l c. HPSI pump amp meters indicate less than 115 amp d. LPSI pump discharge pressure is less than 405 psig.
( QUESTION: 087 (1.00)
l The plant is operating at 100% power. Service water pressure is 5 psig l above its low pressure alarm setpoint. CCW surge tank level is steadily increasing. Which of the following would be the source of leakage?
a. Waste gas compressor seal, b. RCP thermal barrier.
l c. Regenerative heat exchanger.
'
d. CCW heat exchanger.
l l
l l
. . . - - .. - . . . _. - - . , - _ . . . _ - - - .
.
.
REACTOR OPERATOR Page 45 I
QUESTION: 088 (1.00)
Using the following list of safety requirements, breaker operating equipment and protective equipment, determine which one of the following describes the MINIMUM requirements when racking in a breaker for a circulating water pump?
1. A CONVEX clearance 2. Large rackout crank 3. Face shield 4. Orange flash jacket 5. High voltage gloves ,
6. Rubber mat to stand on l 7. Safety glasses
'
a. 1, 5 and 6 b. 2, 3, 4, 5 and 7 c. 2, 3, 4, 6 and 7 d. 2, 3, 4, 5, 6, and 7 QUESTION: 089 (1.00)
In accordance with ACP 1.2-6.4 " Temporary Procedure Changes (TPC),"
within how many days (excluding any extensions) should a TPC be incorporated in an N0P upon approval of the TPC?
a. 30 days b. 60 days c. 90 days d. 120 days
.,
t
_ - - . - - . - - - - _ _ _ _ _ . -
.
.
REACTOR OPERATOR Page 46 QUESTION: 090 (1.00)
With the plant operating in Mode 1, WHICH ONE (1) of the following activities is allowed when only ONE (1) licensed operator is present "at the controls," per N0P 2.0-7, " Operations Department Shift Staffing Requirements?"
l a. Use the rest room facility.
l
'
b. Initiate a surveillance on the diesel auxiliary boards.
l c. Check the inside of the ICC cabinets.
l d. Acknowledge alarm on the L.P. Steam dump control pane QUESTION: 091 (1.00)
!
You have been assigned to perform a valve lineup. As part of your pre-I job brief you are notified that there is ALPHA contamination in your l work are The RWP also is annotated that ALPHA contamination is i l
present. Once you have completed your job task, how do you exit the !
RCA?
l a. Perform an automatic frisk using the PCM-1, then exit the RC b. Perform an automatic frisk using the PCM-1, then a manual frisk
,
using an RM-14/HP210, then exit the RCA.
!
l c. Perform a manual frisk using a Ludlum-177/43-2, then exit the RCA.
i d. Perform an automatic frisk using the PCM-1, then a manual frisk l using a Ludlum-177/43-2, then exit the RCA.
l l
.. . . . ..
-- . . - . ..
\
.
REACTOR OPERATOR Page 47 l
l QUESTION: 092 (1.00)
Given the following conditions:
1. The plant is in H00E . A routine containment entry is planne WHICH ONE (1) of the following is the MINIMUM number of personnel that I are required for the containment entry? '
a. Two (2)
b. Three (3)
c. Four (4)
d. Five (5)
"
.
QUESTION: 093 (1.00)
Which of the following correctly describes a purpose or condition of a No-Tag designation?
a. Can remtin active only for a period of up to two (2) week b. Can only be requested by CONVE c. Notes a temporary operating restrictio d. May be used as required within an approved clearance boundary t aid in ensuring that the valve is incorporated into the system
- restoration when the tags are cleare
,
,
.. .-- . . . - _ _ . _ _ _ _ _ . _ _ _ _ _ _ . . . . . _ . .. . _ . _ . _ . _
.
.
REACTOR OPERATOR Page 48 QUESTION: 094 (1.00)
A radiation monitor has come into alarm. According to A0P 3.2-2, High Activity Level, what action can the operator take to clear the alarm?
a. Raise the alarm limit slightly above the iioicated leve b. Raise the alarm limit to two (2) times backgroun c. Raise the alarm limit up to the maximum setpoin d. Raise the alarm limit up to one and a half (1.5) times backgroun QUESTION: 095 (1.00)
WHICH ONE (1) of the following is the MINIMUM number of plant personnel required to man the fire brigade per N0P 2.0-7, " Operations Department Shift Staffing Requirements?"
a. Four (4) which CANNOT include those required for safe shutdown i of the plan :
b. Four (4) which CAN include those required for safe shutdown of ,
the plan l l
c. Five (5) which CANNOT include those required for safe shutdown l of the plan '
d. Five (5) which CAN include those required for safe shutdown of the plan . ._. . .
. .. . _ _ _ _ . . - . - _ . _ _ . . _ . . . _. . _ . _ _ _ .. _ =
.
.
REACTOR OPERATOR page 49
QUESTION: 096 (1.00)
A generator hydrogen leak is occurring. Which of the following is the lowest hydrogen concentration that would be an explosive / fire hazard?
a. 1%
b. 3%
c. 5%
d. 7%
l l
QUESTION: 097 (1.00)
WHICH ONE (1) of the following is NOT TRUE in regard to independent verification of valve positio a. If a discrepancy is discovered while independently verifying a valve position, one shall immediately contact their supervisor for resolutio b. Observation of the relative height of a valve stem may be used as the sole determinant of a valve's positio c. Independendent verification requirements may be waived by the shift supervisor if excessive radiation exposures would resul d. During valve lineups requiring independent verification, two qualified operators may work together; however, each operator must verify valve / breaker position, including locked status, if applicabl .
'
_ _
__ _ _ _ _ - . _ _ _ . _ __ . _ .
I REACTOR OPERATOR Page 50 QUESTION: 098 (1.00)
~
Which ONE (1) of the following individuals is NOT permitted to operate reactor controls under the instruction or supervision of a licensed I operator?
'
a. A licensed reactor operator who recently failed a NRC .
administered senior reactor operator upgrade examinatio l l
b. A reactor engineer doing rod motion checks following a I refuelin I
'
i c. A licensed reactor operator whose license has become inactive per the requirements of 10CFR5 I d. A nuclear system operator enrolled in a current license training course to obtain ana operator license and has received the necessary trainin l QUESTION: 099 (1.00)
Which ONE of the following is the MINIMUM number of shifts that a l licensed individual must actively perform operator functions to maintain l a license in an active status? Assume eight (8) hour shifts are in i
effec a. Five (5) shifts per calendar quarte b. Five (5) shifts per calendar year.
l c. Seven (7) shifts per calendar quarte d. Seven (7) shifts per calendar year.
l
!
f i
_ _-. _ ___..-. . _ . _ _ _ _ . .. . -_____ ____._. _ ._- - _ . _ . .____ __ _ . ._ -
~
.
.
.
REACTOR OPERATOR Page 51 QUESTION: 100 (1.00)
An attempt to start a reactor coolant pump (RCP) was made at 1045, but the pump was stopped before it reached full spee Which ONE (1) of the following is the earliest time that an attempt to restart the RCP can be made?
a. 11:00 b. 11:15 c. 11:30 l
'
d. 11:45 f
l t
i
(********** END OF EXAMINATION **********)
!
__ - _ - __ - _ _ _ _ _ _ _ - _ _ - _ - _ _ - _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ ____ ____ -__ __-_ - -_ _ _. _ _ _ _ - - _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ .-_-_-___________ _-__-_______ _ ____
55 .m 50 #
W F og o 45 A / 5 o
40 l Y p -M
-
~
/p
-
x 35 " # & n o
f e-= ~
Time to Core Uncovery 30 "
/ -
r** *
C (Ilours) 8 y ar8F p
-
w 20 g / _s -"
'
p b*# 5$_$ .
f- ac~
o" :: ::
-- =
<
Y _ __ .
~
m e-e-W#
'
gg 7u .,n' _
$
p e-e4M ct r '
g 0-m"","","P P P P P P H 0 s-5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 ;;
Shutdown Time (Days) E-o- MidLocp 0 SG for Reflux -o- MidLoop 2 SG for reuux -+- MidLoop 4 SG for reflux-e- MidLoop 1 SG for reflux -m- MidLoop 3 SG for reflux n
.E @z l
Note: Initial RCS temperature is assumed to be 140* w y
$
,
O M to
. .
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ _ _ . _ _
.
.
O
.
- l REACTOR OPERATOR Page 52 ANSWER: 001 (1.00)
i REFERENCE:
HN exam bank QID: 16053 (3.1/3.5]
064000A304 ..(KA's)
ANSWER: 002 (1.00) REFERENCE:
PIB 72 pg 120-121
[2.8/3.2]
064000K405 ..(KA's) ,
ANSWER: 003 (1.00) .
.. ..
.. _ _ _ _
. - -. . . - . . - . . . - . . - - - . . . . _ . . _ . - - . - . _ _ . . . - . . . . _ . . . . - . - . . - - . _ . - . . . . - - .
.
REACTOR OPERATOR Page 53
. REFERENCE:
.
i 4KV PIB ch 64 '
[3.5/3.7)
.
063000K302 ..(KA's)
ANSWER: 004 (1.00)
a.
)
REFERENCE:
,
'
PIB ch [3.8/3.9]
002020G001 ..(KA's)
ANSWER: 005 (1.00) REFERENCE:
PIB ch 81 pg 33
.[3.4/3.6]
035010A203 ..(KA's)
.,, . __ . , , . . .. _
-- . . , - ,
l
.
l
-
REACTOR OPERATOR Page 54 l
.
'
ANSWER: 006 (1.00)
l b.
l
,
REFERENCE:
PIB 2.4 pg 7 l
t
[3.8/4.1]
l
010000K403 ..(KA's) )
l ANSWER: 007 (1.00) l l
l b.
l REFERENCE:
PIB ch [4.0/3.8]
- 010000A403 ..(KA's)
l l
'
ANSWER: 008 (1.00)
b.
I l
,
l l
l
.-. _ _ _ _ _ . _ . _ . . _ . _ _ . .
, _ _ _ . _ . . .. . _ _ - . _ _ . _ _ _ ~ . . _ _ . _ . . . . - _ . - _ _ _ _ _ . _
.
-
i t
REACTOR OPERATOR Page 55
,
i
,
! REFERENCE:
.
[4.2/4.3)
026000K401 ..(KA's)
t l ANSWER: 009 (1.00)
b.
- REFERENCE
PIB ch 6 pg 15
[3.2/3.5]
005000K407 ..(KA's)
!
l ANSWER: 010 (1.00)
l REFERENCE:
l T.S. 3. [3.2/3.8]
,
011000G005 ..(KA's)
I l
l
.
k
- .,
_ . . . _ . _ _ _ . . _ . _ _ _ _ . . . . . _ .
- . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . . _ _ . _ . . . . . . . _ _ _ _ _ . _ _ . . . _ _ _ _ .
.
.
.
REACTOR OPERATOR Page 56 l ANSWER: 011 (1.00)
1 REFERENCE:
l
!
T.S. 2.1.2 l
,
[3.2/3.8)
l l
'
010000G005 ..(KA's)
l ANSWER: 012 (1.00)
l l
.
C.
i
!
REFERENCE:
'-
LP L00400
[3.6/3.1]
004010A401 ..(KA's)
ANSWER: 013 (1.00)
b.
!
i
!
l
, - . . , _ . . _ . . . , .- _ . , . - - . _ - . _ . _ . _ . . . . _ ,
__ _ _ . , - . - . - _ - . . _ _ _ . . . . . . . - _ . . _ _ _ _ . . - _ . _ . _ . _ . _ _ _ _ _ - . _ . _ _ - _ . . . _ . .
.
'
REACTOR OPERATOR i Page 57 t REFERENCE:
.
PIB ch 2.2 pg 32
!
(2.8/2.8]
003000A109 ..(KA's)
l ANSWER: 014 (1.00) !
REFERENCE:
PIB ch 5 pg 142 (pump curve, tn' il flow limited to 2000 gpm/Pp by i n, . t . ion line throttle valves,
[2.6/2.9]
006000K613 ..(KA's)
l
'
ANSWER: 015 (1.00)
- d.
I e
)
k i
'
. _ _ , . - . . _ _ . _-.
_ _ . - _. . , _ _ _ . . . -, . , _ - - . _ . . .
. . _ . . . _ . _ _ _ . _ . _ . _ . . . _ . .__ _.._ .._.._ _ -= _ -_.. _ _.__._ _ . _ _ . _ -
.
- - . .. . . .
.
l
.
REACTOR OPERATOR Page.58 l 1
!
- REFERENCE
'
I LP.REF: SECSYS L01700 PROC REF: ANN 4.4-1 l
l l- [2.7/2.9]
l
!
041020K603 ..(KA's)
l i
!
ANSWER: 016 (1.00) .
REFERENCE:
l PIB ch 17 i
[3.7/3.9)
l 041020K417 ..(KA's)
l ANSWER: 017 (1.00)
b.
1.
.
.
l
!
l l
i l
l
- -
_
. . . _ _ .- . . . . . _ _ . _ _ . . _ . _ _ _ . _ _ . _ _ _ . _ _ . . . _ . _ _ . . . _ . _ . _ _ _ _ _ . _ . . . . _ _ . . . _ _ _ _ _ _ . . .
!
.
~
!
REACTOR OPERATOR Page 59 REFERENCE:
PIB ch 25 1
'
.
[2.8/2.9]
,
i l 041020GG04 ..(KA's)
l
' ANSWER: 018 (1.00) REFERENCE:
>
l i
PIB ch 23/26 i
i
[2.5/2.6]
! 045050G004 ..(KA's) !
l l
l ANSWER: -019 (1.00)
,
.
l l
-
!
l a.
i
,
REFERENCE:
HN exam bank QIDL 16087 1
!
[3.4/3.8]
i
000024K101 ..(KA's)
-
I l
!
, . . _
_
...
- -. - .... -... - ...-. - - . - . . .- - -
i REACTOR OPERATOR Page 60 ANSWER: 020 (1.00) i I
!
REFERENCE:
i FR- [4.0/4.4]
000074K311 ..(KA's)
ANSWER: 021 (1.00) , REFERENCE:
j A0P l
[3.6/3.5]
000026G010 ..(KA's)
ANSWER: 022 (1.00)
. ;
- - - - . . - - . - . - . , . - . - - . - - - . - . . - - . . - - - - . . . . - . . . -.
l l *
\
.
l REACTOR OPERATOR Page 61 'l l
l REFERENCE:
[3. 3 /3.'6] .
039000A205 ..(KA's) l l
l ANSWER: 023 (1.00) REFERENCE:
PIB ch 21
[2.7/3.0]
061000A206 ..(KA's)
ANSWER: 024 (1.00) REFERENCE:
.
l ANSWER: 025 (1.00)
l t
l J
b.
t t
!
l l
l
_ __ _ _ __ ,
- . .. - _ _ - - - .- - . - - . . - . . _ . - . . - . . . . . . _ . . . . - - - . . . . - -
,
_
.
.
REACTOR OPERATOR Page 62
.
) REFERENCE:
j- E-0
,
[2.8/2.9)
.
j 045000G014 ..(KA's)
i fNSWER: 026 (1.00) REFERENCE:
[4.1/4.2]
010000A203 ..(KA's)
ANSWER: 027 (1.00) REFERENCE:
LP-ROD-010C, Rod Control System, pages 35-37; E0-11 N0P2.2-1 85% 552 degrees Tave att 6
[3.2/3.6]
'001000K565 ..(KA's)
._ _ . _ . _ . _ _ . . _ . _ _ . _ . _ _ _ . . _ . _ _ . . _ . . . . . _ _ _ . . _ . _ _ _ _ _ . . _ . _ . _ . . _
.
l
l REACTOR OPERATOR l Page 63 ANSWER: 028 (1.00) REFERENCE:
LP-CY-0P-LO-PRISYS-LOO 220, Reactor Coolant Pump, page 22: EO-6
[3.4/3.4)
003000A107 ..(KA's)
!
ANSWER: 029 (1.00)
! -
i d.
! i t I
!
.
REFERENCE:
l LP-CVC-01-C,. Chemical and Volume Control System, page 16: E0-3 i
- [3.2/3.1)
l l
l l 004000K404 ..(KA's)
l ANSWER: 030 (1.00)
d.
,
. . > _ _ . _ . . . . . _ - . . . . . . _ _ . . . . _ . .
.
-
I REACTOR OPERATOR Page 64 REFERENCE:
I l
PIB'ch 5 pg 21 TS basis B 3/4 5.4 pg. 5-2 and UFSAR pg. 6.1-2
!
[3.2/3.4]
026000G004 ..(KA's)
l ANSWER: 031 (1.00) REFERENCE:
l PIB ch 12
[2.7/2.9]
068000K107 ..(KA's)
ANSWER: 032 (1.00) . I
REFERENCE:
E0P 3.1-34 l [2.9/3.4] l l !
000065K303 ..(KA's)
l
- , , -
.. . . . - .. .. . . - . . - . . - . . - . . . . . - _ . . . . . . . . . . - _ - -
.-- , . . _ . . - . .
.
.
. REACTOR OPERATOR Page 65 ANSWER: 033 (1.00) '
- REFERENCE
MS sys desc, E0P 3.1-34
[2.9/3.1)
j 000065G007 ..(KA's)
i ANSWER: 034 (1.00)
d.
REFERENCE:
E0P 3.1-34
,
[3.6/4.2]
.i 000065A206 ..(KA's)
ANSWER: 035 (1.00)
.
C.
a
. . -
'
I
.
d
1 l
'
REACTOR OPERATOR e
Page 66
-
i
,
REFERENCE:
i I
- ;
- .E-3 background 4
!
~
l
[4.2/4.5]
,
1 i i
000038K306 ..(KA's)
,
}
I ANSWER: 036 (1.00)
i i
- a.
I i
- REFERENCE
!
!
!
, LP REF: L3201 ECA-0.0
.
[3.5/3.9)
000055A104 ..(KA's)
ANSWER: 037 (1.00) .
.- _ _ . _ . _ . _ . . _ _ _ _ . - . _ . . _ - - . . . . . . _ _ . . . . _ _ _ . . . . . _ _ _ _ _ _ . _ . - . _ . . _ _ . _ _ . . .
_ .
!
1 .
l t-
-
l' ' REACTOR OPERATOR Page 67 REFERENCE:
l E-3-i l'
[4.3/4.1) '
000038A104 ...(KA's)
'
!
ANSWER: 038 (1.00) l i I
REFERENCE: t
! l AOP 3.2-23 l
l
[3.7/3.8]
001050G001 ..(KA's)
ANSWER: 039 (1.00) REFERENCE:
A0P 3.2-23
[3.2/3.7]
000003K101 ..(KA's)
l
[ . i
'
l l .
REACTOR OPERATOR Page 68
!
l ANSWER: 040 (1.00)
b.
r i
REFERENCE:
l l TS 3.4.6.2
[3.6/4.1]
002020G005 ..(KA's)
l l
ANSWER: 041 (1.00)
d.
t l
REFERENCE:
TS [3.6/4.1]
002020G005 ..(KA's)
ANSWER: 042 (1.00)
a.
!
,.... .. . -. .. - --
! -
!
! ..
i ~ REACTOR OPERATOR-Page 69 I
REFERENCE:
'
T.S. 2.0 j [3.6/4.1]
- 002020G005 ..(KA's)
i-
.l
. ANSWER: 043 (1.00)
!
- REFERENCE
CAF
[3.4/3.4]
004000K117 ..(KA's)
ANSWER: 044 (1.00) REFERENCE:
^j A0P 3.2-57
[3.3/3.7]
l l
000067G010 ..(KA's)
!
.
!
!
O
l l
REACTOR OPERATOR Page 70 l
l ANSWER: 045 (1.00)
c.
l l REFERENCE:
,
[4.3/4.7)
001000K504 ..(KA's)
l ANSWER: 046 (1.00) REFERENCE:
PIB ch 80 pg 27
[3.7/3.9)
001000A104 ..(KA's)
ANSWER: 047 (1.00)
b.
!
_. _. . _ . - - _ _ . . _ . . _ - . . . _ . . _ . _ . _ _ . . _ __ . - _ _ _ . . _ _ _ _ . . . _ .__ _
. ,
.
REACTOR OPERATOR Page 71 REFERENCE:
l N0P 2.4-10 Att PROVIDE ATT l-7 AS REFERENCE
,
[3.4/3.6]
000025G007 ..(KA's)
ANSWER: 048 (1.00)
b.
l REFERENCE:
Background for FR- [4.2/4.4]
,
000024K302 ..(KA's)
l ANSWER: 049 (1.00) REFERENCE:
PIB ch 8 [3.2/3.4]
i l 001000K104 ..(KA's)
i l
!
l l
l
- - . . . - - - . - _ . . - - . . ~ . - . . - . - - . . ~ . . . ~ . . - . . ~ _ - . . . . . - - ..
. !
.
REACTOR OPERATOR' ~'
P, age 72 ANSWER: 050 (1.00)
I l b.
i REFERENCE:
I i
A0P 3.2-12.pg. 2,6 l
l N0P2.4-10, pg. 12 '
.[3.4/3.7]
l 000025A207 ..(KA's) 1
.
.
ANSWER: 051 (1.00)
a.
! REFERENCE:
Figure 8.1, TRSCO
[4.3/4.7)
001000K504 ..(KA's)
ANSWER: 052 (1.00)
!
, b.
l
, _ _
.. .. _ - . - ..-..- .. .-. .-.. .. --. .- _.. - - ..- -. ..- -.. - .-... ..~. . . .
+
.
.
, REACTOR OPERATOR- Page 73 l REFERENCE:
A0P 3.2-33 .
J -
[3.9/4.1]
000051A202 ..(KA's)
ANSWER: 053 (1.00)
1 REFERENCE:
LP REF:LO8200
[3.4/3.6]
072000A101 ..(KA's)
ANSWER: 054 (1.00) REFERENCE:
PIB ch 82
[3.3/3.6]
072000K401 ..(KA's)
.
.
.
.
REACTOR OPERATOR Page 74 ANSWER: 055 (1.00) REFERENCE:
status trees
[3.7/3.9]
017020A101 ..(KA's)
ANSWER: 056 (1.00) REFERENCE:
A0P 3.2-12
[3.9/4.3]
000025K101 ..(KA's)
ANSWER: 057 (1.00) . .- - . . .
. . . _ . . - - - . . . - . - . . - . . . . . . - . . . . . - - - _ - -
.
.
~
!
REACTOR OPERATOR Page 75 i
REFERENCE: .
,
,
,
FR-S.1 background.
i
- [4.2/4.3]
- 000029K306 ..(KA's)
i ,
i-
- ANSWER
- 058 (1.00)
-
b.
i i
REFERENCE:
ECA-0.0; loss of power to RP .
[4.2/4.5]
000029K301 ..(KA's)
ANSWER: 059 (1.00) REFERENCE:
facility bank question 3 )
l l
[3.1/3.1]
015000K103 ..(KA's)
. . - . _ _ _ _ _ . _ . . - . . . _
.- . . _ . _ . - . _ . . _ . _ _ . . . . _ . . _ . . . . . _ _ . . _ . _ _ - . . _ . . . - _ . . _ _ _ _ _ . _ _ . _ . . _ _ . _ .
.
.
.
REACTOR OPERATOR Page 76 ANSWER: 060 (1.00)
i REFERENCE:
A0P 3.2-23
[3.6/4.1]
014000A203 ..(KA's)
l l
ANSWER: 061 (1.00) ,
,
l i l
i REFERENCE:
l TS 3. [3.7/4.1]
000015K102 ..(KA's) -
ANSWER: 062 (1.00) q l j
i
i
.
,-
.- . .- .- . . . . . - . . - - . . - - . _ - . . - - . - - . . . - . . - - - , _ - . - . . . . - - . . . . . . . .
l .
.
REACTOR OPERATOR Page 77 REFERENCE:
.
l A0P 3.2-17, fac Q98
[3.5/3.6]
000015G0ll ..(KA's)
ANSWER: 063 (1.00)
l REFERENCE:
bank q69 ;
!
i i
l
-[3.6/3.7] l
,
010000K103 ..(KA's) l
\
'
ANSWER: 064 (1.00) REFERENCE:
.
PIB [3.4/3.8]
- 000028A202 ..(KA's)
a i
I
.. - --
. .. .... _ . _ . . . _ . . . _ . _ . - _ . . _ _ . _ . . . . _ _ . . . . _ _ _ . - . _ _ . . . . ~ . _ _ . _ . . . _ _ - _ . . _ _ . _
,
. . l
'
REACTOR OPERATOR Page 78 ANSWER: 065 (1.00) l REFERENCE:
,
A0P 3.2-50 ;
[4.1/4.2] ;
000068G010 ..(KA's)
ANSWER: 066 (1.00) .
REFERENCE:
bank q72'
E-
[4.0/4.2]
000068A203 ..(VA's)
ANSWER: 067 (1.00)
.
C.
I
-
i
,
I i
)
i t
, . _ _ - -
. . _ _ _ . .
. . . . . _ _ . _ . _ . . . . . _ . . _ _ . _ _ . . . . . _ . _ . _ . . - - _ . _ . - .._ _ _. _ .. .
-
-
. a
-
!
REACTOR OPERATOR ~ Page 79
, REFERENCE:
l
,
l .
L PIB ch 19 L [3.3/3.5]
!.
l l 059000K402- ..(KA's)
!
i l
l t
ANSWER: 068 (1.00)_
I i REFERENCE:
'
PIB ch 5
[4.1/4.2]
Ol3000A302 ..(KA's) ,
ANSWER: 069 (1.00) REFERENCE:
PIB ch 67
[4.0/4.3]
f, 000057A219 ..(KA's)
i
.
l
. - -_.. - - . . - - - - .. - .. . .... .. . - . . - .. - - . .-.- . . - . . . . ... . ~ . - . - . - _ . - - - . - ,
A
.
.
a
'
REACTOR OPERATOR Page 80 ANSWER: 070' (1.00)
i I ,
l REFERENCE:
.
PIB ch 21
[3.9/4.2]
061000K401 ..(KA's) !
ANSWER: 071 (1.00) ., REFERENCE:
!
PIB ch 21
[2.7/2.8]
061000 Kill ..(KA's)
ANSWER: 072 (1.00)
a.
. , . - . . , , - . . - -._ --.. = . , . - - .-, , ,
- - . - - ,
. _ m. _ _ __ __ . _ - . . . _ . . _ . . . - . . . . . _ _ . . . . . . . _ _ _ -. . . . - - _ _ --. _ . . .
'
l
,
~
\
REACTOR OPERATOR Page 81 REFERENCE:
PIB CH 21
'
[3.2/3.6]
\
- l l 061000A202 ..(KA's)
ANSWER: 073 (1.00) REFERENCE:
- HN 11/94 exam l CY-0P-LO-A0P-L2201, pg. 20 of 26
.
[3.1/3.6]
000022A203 ..(KA's)
!
ANSWER: 074 (1.00)
l t
l REFERENCE:
- HN 11/94 exam l
[2.8/3.3]
000032G008 ..(KA's)
i
!
.
. . ..= = -
-
)
i l
.
REACTOR OPERATOR Page 82 .
l L
,
,
ANSWER: 075 (1.00)
I I l REFERENCE:
HN 11/94 exam
]
[2.9/3.1] l j 033000A302 ..(KA's)
!
ANSWER: 076 -(1.00)
! REFERENCE:
HN'11/94 exam I [3.7/3.9]
0000llG007 ..(KA's)
ANSWER: 077 (1.00)
i I'
a.
I F
I I . - - . _ _ . _ . --- _ , . _ . _ _ - - _
. . _ -_ . - . . _ .- _-_ .
_ . _ . . _ . . _ _ . _ _ _ . _ _ _ _ _ _ . _ . _ _ .
\ .
l-
.
.
l REACTOR OPERATOR Page 83 REFERENCE:
HNil/94 exam
[3.0/3.5] -
,
000033A201 ..(KA's)
l
' ANSWER: 078 (1.00)
l Y REFERENCE:
i
!
' HN 11/94 exam A0P 3.2-31, pg. 4
[4.2/4.4]
>
l 000037X307 ..(KA's)
i ANSWER: 079 (1.00) )
,
i '
!
l REFERENCE:
E HN 11/94 exam
[3.0/3.1]
l 000061G009 ..(KA's)
i
- 1
,
._ _-. . _ _ . _ . . . . __ _ . _ - _ - - . _ . . - - . . . _ _ , _ _ _ _ _ __ __
.
l
..
REACTOR OPERATOR Page 84 ANSWER: 080 (1.00) ,
d.
l REFERENCE:
I HN exam bank ID 15333 l LP Ref:L3202, Proc. ref: 3.1-49
[3.5/3.9] l l
000058A203 ..(KA's) i l ANSWER: 081 (1.00) REFERENCE:
HN Exam bank 1D14372 LP REF: L1901, PROC REF: A0P 3.2-15
[3.2/3.7]
000057A206 ..(KA's)
ANSWER: 082 (1.00)
C.
l l
,
__ . . . . _ . . . . _ . _ _ _ . . - - _ _ . _ _ _ . _ _ . ... ___ . .._ _ _ -
._. .._ .
-
l
.
REACTOR OPERATOR Page 85 REFERENCE:
HN exam bank ID 15653
.
[3.7/4.1)
000036A303 ..(KA's)
ANSWER: 083 (1.00)
l C.
,
REFERENCE:
l HN exam bank ID 13274 LP REF: 590206, PROC REF: ECA- [3.5/3.6]
000056A206 ..(KA's)
l ANSWER: 084 (1.00)
l REFERENCE:
l HN exam 11/94 l
[3.3/3.3]
086000A401 ..(KA's)
l l
l l
_ _ . .
_. . . . _ - _ _ _ _ _ - . _ . .- _ _ _ _ - - . _ . _ _ . _ _ . _ . . _ . _ . _ . . _ - _ . - . - _ _ _ - . . _ . _ . . . .
- .-
.
.
.
-
.
REACTOR OPERATOR Page 86 i
ANSWER: 085 (1.00)
i s
a.
i
! REFERENCE:
! HN Exam .(1/94 I
i l
[3.6/4.1]-
i i
, 002000G005 ..(KA's)
\
i i
]
ANSWER: 086 (1.00)
!
.
b.
REFERENCE:
l HN exam 11/94 i
'
[3.5/3.8] j 000009A202 ..(KA's)
ANSWER: 087 ( l '. 00)
b.
.
-
, n,
. .
. . . . -- _ - - . . . . . . .
_ . - _
- . . _ . . . - - - .
.
.
REACTOR OPERATOR Page 87 REctPE9.E:
l AOP 3.2-10 l
.
[2.9/3.5]
l 000026A201 ..(KA's)
l ANSWER: 088 (1.00) REFERENCE:
l HN question bank ID 19130 l
[3.6/3.7] .
194001K107 ..(KA's)
ANSWER: 089 (1.00) REFERENCE:
ACP 1.2-6.4, pg. 9
[3.3/3.4]
194001A101 ..(KA's)
l
'
ANSWER: 090 (1.00) __ . _ , _ . - --
_ . _ _ . . . _ _ _ - . _ . _ _ _ _ - _ _ _ . _ _ _ . _ . . _ _ _ . _ _ _ _ _ _ _ _ - -
_ _ _ _ _ _ . . _ . _
.
-
REACTOR OPERATOR Page 88 REFERENCE:
1994 NRC exam N0P 2.0-7, " Operations Department Shift Staffing Requirements," pg. 2 and Att. 2
[2.7/3.9]
194001A109 ..(KA's)
ANSWER: 091 (1.00)
d.
l REFERENCE:
RPM 2.7-2, Personnel Monitoring, pg.1
[3.3/3.5]
,
l l
l 19400]K104 ..(KA's)
ANSWER: 092 (1.00) .
REFERENCE:
l l
WCM 2,4-7, Containment Access, Att. 1, pg. 1 NRC Exam
[3.1/3.4]
19400lK105 ..(KA's)
l
.
_. - _
.. . . . - - . . - . -. . . - . - . . . . . _ . . . - . - - _ - . . . - . . . - - . _ - . - -
l.
- .
- . REACTOR OPERATOR.
.
Page 89
!
i
- ANSWER
- 093 (1.00)
1.
l .
j REFERENCE:
'
i WCH2.4-1, Equipment Tagging, pg. 12 L
l'
.
!
[3.7/4.1]
+
i j- 19400lK102 ..(KA's)
'
,
ANSWER: 094 (1.00)
- d.
l
.
j REFERENCE:
} HN. exam bank QID: 16255 Check A0P 3.2-2 i
}
'
j
.
[2.8/3.4]
,.
j 194001K103 ..(KA's)
,
t
.
ANSWER: 095 (1.00)
s u
C.
I s
k s
i i
!
s J
I e
i i
_ ~ , . . - -. - ._ -.
_ _ . . _ _ _ . ~_ . _ _.____ ._ _.___._ _ __ _ __.__.._.._.-.. _ _ _ _ _ .__ _ _ .
.
! I
. 1 REACTOR OPERATOR Page 90 REFERENCE:
94 HN exam
[3.5/4.2]
i 19400lK116 ..(KA's)
l l
ANSWER: 096 (1.00)
C.
l l l
'
REFERENCE: ;
93 HN exam l [3.8/3.8] l 19400lK115 ..(KA's)
ANSWER: 097 (1.00)
! REFERENCE:
001 #170, pg. 2 & 3
[3.6/3.7]
.
19400lK101 ..(KA's)
l l
l
,. - - - . . - , . .- .. .. , ... -.
.- -- . . . . . . - - . _ - - . - - . _ . . . . - . _ ~ . . _ . - . . - . - ~ ~ . . . . - - - , . . . _ . - - . . _ . _ _ . . -
.
.
,
!
-
I REACTOR OPERATOR Page 91 i
I ANSWER: 098 (1.00)
a
' l REFERENCE:
ODI #1 pg., 12'
,
'
!
[2.8/4.1]
I 194001A111 ..(KA's)
ANSWER: 099 (1.00) REFERENCE:
ODI #157 pg., 1
[2.5/3.4] l 194001A103 ..(KA's)
ANSWER: 100 (1.00) .
- - _ ..
.
.
.
.
REACTOR OPERATOR Page 92 REFERENCE:
N0P2.4-2 Reactor Coolant Purip Operation, pg. 3
[3.4/3.4]
i l
l 194001K106 ..(KA's)
l l
- (********** END OF EXAMINATION **********)
l i
I
.
.
REACTOR OPERATOR Page 1 ANSWER KEY MULTIPLE CH0 ICE 023 c 001 b 024 c 002 b 025 b 003 c 026 b 004 a 027 c 005 c 028 d 006 b 029 d 007 b 030 d i 008 b 031 a l
009 b 032 d 010 a 033 b 011 d 034 d 012 c 035 c 013 b 036 a 014 b 037 d 015 d 038 b-016 c 039 c 017 b 040 b 018 a 041 d
019 a 042 a 020 b 043 c 021 a 044 c 022 b 045 c
.- _ _ _ . . . . _ . . _ _ . . _ _ . . . _ _ _ _ _ _ _ . _ _ _ _ . . . _ _ . _ _ _ . _ _ . _ . _ . _ _ . . _ . _ _ . . . . _ . _
.
&
REACTOR OPERATOR Page 2 ANSWER KEY 046 b 069 d 047 b 070 a 048 b 071 c 049 b 072 a 050 b 073 a 051 a 074 a i
1 052 b 075 d 053 c 076 b 054 a 077 a
!
l 055 a 078 ,b' 4 '
!
, 056 b 079 b
!
057 b 080 d 058 b 081 b l 059 c 082 c 060 b 083 c 061 b 084 c 062 d 085 a ,
- 063 d 086 b i
l 064 a 087 b
!
065 b 088 b 066 c 089 d 067 c 090 c 068 d 091 d
!
l l
l I _ . - . . _ _
..
.
.
REACTOR OPERATOR Page 3 ANSWER KEY l
.
092 b 093 d 094 d 095 c 096 c 097 b
098 b 099 c 100 b
.
(********** END OF EXAMINATION **********)
. . -. - .- - -- _ -. . . . . - - - -- . . - - . . . - _ .
.
l TEST CROSS REFERENCE Page 1 R0 Exam PWR Reactor ,
0rgan1 zed by Question Number I QUESTION VALUE REFERENCE 001 1.00 9000192 l 002 1.00 9000193 i
!
003 1.00 9000195 '
004 1.00 9000196 005 1.00 9000197 006 1.00 9000198 007 1.00 9000199 l 008 1.00 9000200 i 009 1.00 9000201 010 1.00 9000202 i 011 1.00 9000203 l 012 1.00 9000204 013 1.00 9000205
- 014 1.00 9000206 015 1.00 9000212 016 1.00 9000213 017 1.00 9000214 018 1.00 9000215 019 1.00 9000216 020 1.00 9000217 ;
021 1.00 9000219 i
- 022 1.00 9000220 023 1.00 9000222 024 1.00 9000223 025 1.00 9000224 026 1.00 9000225 027 1.00 9000227 028 1.00 9000228 029 1.00 9000229 030 1.00 9000230 l 031 1.00 9000231 !
032 1.00 9000234 l 033 1.00 9000235 034 1.00 9000236 l
, 035 1.00 9000237 036 1.00 9000239 037 1.00 9000240 038 1.00 9000241 039 1.00 9000242 040 1.00 9000244
. 041 1.00 9000245 042 1.00 9000246 043 1.00 9000248 044 1.00 9000249 045 1.00 9000250 046 1.00 9000251 047 1.00 9000253 048 1.00 9000254 ( 049 1.00 9000255
- . . . - . . . . --. - . _ . - . . - - . . - . .. -.-.- . . - . . . - . . . . - - . ..
,
'
.
'
.
l TEST CROSS REFERENCE Page 2
'
R0 Exam PWR Reactor Organized by Question Number
- QUESTION VALUE REFERENCE
,
050 1.00 9000256
~ 051 1.00 9000257 052 1.00 9000258 !
053 1.00 9000259
)
054 1.00 9000260 3 055 1.00 9000261 l 056 1.00 9000262
057 1.00 9000264 j
058 1.00 9000265 i
059 1.00 9000266
, 060 1.00 9000267 061 1.00 9000268 ,
l 062 -1.00 9000269 l 063 1.00 9000271 l 064 1.00 9000272
- 065 1.00 9000274
- 066 1.00 9000275 1 067 1.00 9000276
068 1.00 9000277
.
i 069 1.00 9000278 070 1.00 9000279 071 1.00 9000280
072 1.00 9000281 073 1.00 9000282
- 074 1.00 9000283 075 1.00 9000284 076 1.00 9000285 i 077 1.00 9000286 i
078 1.00 9000287 l 079 1.00 9000288 I
080 1.00 9000289
- 081 1.00 9000290
082 1.00 9000291 083 1.00 9000292 084 1.00 9000293 085 1.00 9000294 086 1.00 9000295 087 1.00 9000296 088 1.00 9000299 089 1.00 9000300 090 1.00 9000301 091 1.00 9000302 092 1.00 9000303 093 1.00 9000306 094 1.00 9000307 095 1.00 9000309 096 1.00 9000310 097 1.00 9000311 098 1.00 9000313
_ . ._ ._ . _ _ . _ . .. _ _ _ _ _ _ _ . . _ . _ _ _ . _ , . _ _ . - _ _ . _ _ _ _ . _ . . . . _ _ _ _ . . _ . _ _ _ _ _
e .
l
.
.
TEST CROSS REFERENCE Page 3 R0 Exam PWR Reactor l
Organized by Question Number QUESTION VALUE REFERENCE l
'
099 1.00 9000314 100 1.00 9000315
______
i
'
100.00
- ______
- ,
______
! 100.00 l
l
l i
!
!
i I
l
\
{
. ,_ _ __ _ _ _ __ - . . . _ . . . - - - , . . - _ _
- . _ .
_ .__ _ _ _ . .. ._ __ _
S
\
TEST CROSS REFERENCE Page 4 R0 Exam PWR Reactor 0rganized by KA Group PLANT WIDE GENERICS QUESTION VALUE KA 089 ~176U 194001A101 l 099 1.00 194001A103 090 1.00 194001A109 098 1.00 194001A111 097 1.00 19400lK101 093 1.00 19400lK102 094 1.00 194001K103 091 1.00 194001K104 092 1.00 19400lK105
,
100 1.00 194001K106 088 1.00 194001K107 096 1.00 19400lKil5 095 1.00 194001K116
______
PWG Total 13.00 '
'
PLANT SYSTEMS I
'
Group 1 l
QUESTION VALUE KA 04T ~TDU 001000A104 049 1.00 001000K104 051 1.00 001000K504
- 045 1.00 001000K504 027 1.00 001000K565 038 1.00 001050G001 028 1.00 003000A107 013 1.00 003000A109 ,
043 1.00 004000K117 029 1.00 004000K404 012 1.00 004010A401 068 1.00 Ol3000A302 059 1.00 015000K103 055 1.00 017020A101 067 1.00 059000K402 072 1.00 061000A202 023 1.00 061000A206 071 1.00 061000K111 070 1.00 061000K401 j 031 1.00 068000K107 053 1.00 072000A101 054 1.00 072000K401
______
PS-1 Total 22.00 l
l
. _ - - . _ _ . _ .._ - - - - - _ . _ _ - . _ _ - - - _ _ _ _ . _ _ . _ _ _ .- _ _ _ _ _ .
.
TEST CROSS REFERENCE Page 5
,
R0 Exam PWR Reactor 0rganized by KA Group PLANT SYSTEMS
- Group II
- VALUE QUESTION KA
, 085 I UU 002000G005 004 1.00 002020G001
- 041 1.00 002020G005 3 040 1.00 002020G005 042 1.00 002020G005 014 1.00 006000K613 026 1.00 010000A203
,' 007 1.00 010000A403 011 1.00 010000G005 063 1.00 010000K103 s 006 1.00 010000K403 010 1.00 011000G005 060 )
1.00 014000A203 '
030 1.00 026000G004 008 1.00 026000K401 '
075 1.00 033000A302 005 1.00
,
.
035010A203 1 1 022 1.00 039000A205 003 1.00 063000K302
001 1.00 064000A304 j 002 1.00 064000K405 084 1.00 086000A401
______
- PS-II Total 22.00
Group Ill j QUESTION VALUE KA
,
009 1.0D 005000K407
017 1.00 041020G004 016 1.00 041020K417 *
l
015 1.00 041020K603
- .
025 1.00 045000G014 018 1.00 045050G004
______
PS-Ill Total 6.00
______
______
PS Total 50.00 EMERGENCY PLANT EVOLUTIONS Group I
I
!
6
.
' TEST CROSS REFERENCE Page 6 R0 Exam PWR Reactor 0rganized by KA Group EMERGENCY PLANT EVDLUTIONS Group I ,
!
QUESTION VALUE KA l
062 T 6D F00015G0ll 061 1.00 000015K102 019 1.00 000024K101 048 1.00 000024K302 087 1.00 000026A201 021 1.00 000026G010 052 1.00 000051A202 036 1.00 000055A104 081 1.00 000057A206 069 1.00 000057A219 044 1.00 000067G010 066 1.00 000068A203 065 1.00 000068G010 020 1.00 000074K311
______
EPE-I Total 14.00 l
Group 11 QUESTION VALUE KA
039 1.00 000003K101 086 1.00 000009A202 076 1.00 0000llG007 073 1.00 000022A203 050 1.00 000025A207 047 1.00 000025G007 i
'
056 1.00 000025K101 058 1.00 000029K301 057 1.00 000029K306 l 074 1.00 000032G008 l 077 1.00 000033A201 078 1.00 000037K307 l 037 1.00 000038A104 035 1.00 000038K306 080 1.00 000058A203 079 1.00 000061G009
______
EPE-Il Total 16.00 Group 111 QUESTION VALUE KA l
064 1.00 000028A202
!
. - _ . _ . . - . . _ . _ _ . .. -- . . . . - - . - _ = . - . . - . . . - _ . - . . . - . - . - . . - .- -.-- ..
. .
'
TEST CROSS REFERENCE Page 7 R0 Exam PWR Reactor l 0rganized by KA Group l
l l
EMERGENCY PLANT EVOLUTIONS
Group III l
QUESTION VALUE KA
- 082 1.00 000036A303 ,
083 1.00 000056A206 I 034 1.00 000065A206 033 1.00 000065G007 032 1.00 000065K303
______
EPE-III Total 6.00
______
l
______
EPE Total 36.00
______
______
,
Test Total Ibb$bb
'
l
<
1
4
. - . . _
. , , . - . _ , _ , . ,