IR 05000317/1990007
| ML20055E913 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/07/1990 |
| From: | Eselgroth P, Prell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20055E910 | List: |
| References | |
| 50-317-90-07OL, 50-317-90-7OL, 50-318-90-07OL, 50-318-90-7OL, NUDOCS 9007130077 | |
| Download: ML20055E913 (164) | |
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JUL 0 21990
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-U.S. NUCLEAR REGULATORY COMMISSION REGION 1
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OPERATOR LICENSING EXAMINATION REPORT
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EXAMINATION REPORT NOS.: 50-317/90-07-(0L) and 50-318/90-07 (OL)
FACILITY DOCKET NOS.:
50-317 and 50-318-
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, FACILITY LICENSE N05.:.
LICENSEE: Calvert Cliffs Nuclear' Power Plant, Units l'and 2.
EXAMINATION DATES: May 7-10, 1990
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NRC EXAMINERS: J. Prell, Senior Operations Engineer i
G. Weale, Sonalyst Examiner
.I. Kingsley,,So lyst Examiner
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CHIEF EXAMINER:
(m/; N-l i
M/k8L
.J.
ell,'S%nfor Op'erations Engineer
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APPROVED BY:.
/fif v$df
[!7!9/)
FP.' Eselpoth, Chiet//PWR Section Dete
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SUMMARY: Written and operating examinations were administered to three Reactor.
.0perator. (RO)l and one Senior Reactor Operator (SR0)-Instant candidates.
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addition,:_aL retake ex. amination -.was. administered to one R0 candidate who'.had
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previously - failed the simulator portion of an initial examination. All five
^ candidates passed their, examinations and were issued licenses.
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9007130077 900607 v~
PDR ADOCK 05000317
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DETAILS n
TYPE OF EXAMINATIONi Initial
EXAMINATION RESULTS:
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-INITIAL l
R0 l
SRO-l TOTAL _.
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EXAM l
Pass / Fail l
Pass / Fail.
I Pass / Fail i
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WRITTEN'
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1/0 l
4/0-l
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_l-SIMULATOR l
- 4 / 0 l
1/ 0-l 5 /. 0 l
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!L l WALK:THROUGH l 3/0 l
1/0 l
4/0 l
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-l OVERALL l-4/0 l
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- Includes the RO retake exam results on the. simulator.
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PERSONS CONTACTED:
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Baltimore Gas and Electric Coapany
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- John Hill Supervisor Operations Training
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- Dave Holm Senior Operations Instructor
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- Kevin Nietman General SLpervisor-Nuclear Training
- Raymond Wenderlich General Supervisor-Nuclear Operations
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U. S. Nuclear Regulatory Commission i
- Jin Chung Regulatory Coordinator-NRR
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- Ivan~Kingsley Examiner-Sonalyst-i
- Jim Prell Senior Operations Engineer j
Ted Szymanski Senior Reactor Engineer-NRR (
- Gary Weale Examiner-Sonalyst
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- Denotes those present at the exit meeting conducted on May 10, 1990.
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3.
GENERIC WEAKNESSES:
The:following is a summary of generic weaknesses noted on the examina-tions. This information is provided to aid the licensee -in upgrading
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licensed operator training. No licensee response is required.
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-a.
An inconsistency'was noted between operator use of the Emergency Operating Procedures (EOPs) and their use of Abnormal Operating Procedures (A0Ps). When in the E0Ps, the Control Room Supervisor
.(CRS) assigns each Reactor Operator (RO) responsibility for perform-ing a particular paragraph in the E0P. While the operators are carrying out their responsibility, the CRS is able to maintain an overview of what is taking place in the plant. He is only interrup-ted when the operators complete their paragraph and give him their-findings. He then assigns them a new paragraph to complete and analyzes what they have found.
The CRS is thus in a.better position to= diagnose what is' happening in the plant and maintain the " big picture." When the operators are using the AOPs, the CRS is required to read each step of the procedure while the R0s are inrplementing them.- The CRS is therefore not able to develop and maintain a big
- picture of what is occurring.
The licensee acknowledged this observation and stated that it was due to the way the AOPs are formatted. The licensee stated they are in
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the process of rewriting their A0Ps to be consistent with their E0Ps.
When completed -the operators use of the A0Ps will be consistent with their use of the E0Ps.
b.
In many cases when alarms came in or abnormal plant responses were
.noted,- the operators waited for the appropriate procedure to. be retrieved and read before taking any type of diagnostic or immediate
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action. Dur:ng this time the plant often degraded further than-considered necessary. There are some standard actions which the operators could take to prevent these challenges which, after completion, could then be verified as meeting procedural requirements.
Some e' amples of these are manually transferring a failed pressurizer x
level or pressure channel to the other channel or manually. closing an open turbine bypass valve. The General Supervisor - Nuclear.0perations concurred with this NRC observation and stated that perhaps the -
operators had been oversensitized regarding the necessity of referring to procedures.
He then stated that Calvert Cliffs would look into identifying and providing operator guidance on those actions which could be performed prior to referring to the appropriate procedure.
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4.
SIMULATION FACILITY FIDELITY REPORT During the conduct of the simulator portion of the operating tests, it was observed that the Safety Parameter Display System (SPDS) had a permanent steam flow alarm indicated.
This alarm was unique to the simulator and i
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the operators had learned'to ignore it.
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. SUMMARY OF NRC COMMENTS MADE AT EXIT INTERVIEW:
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f A ~ summary of the week's activities was presented and discussed, including f
the-items presented above. Weaknesses and strengths of the training c
department, operating crews and plant procedures.were discussed.
Two of
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.the strengths noted by the exam team were:
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't a.
There has been a large improvement in the detail, format and consist-E ency of the E0Ps in the past two years and the use of them by the operating crews.
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b.
There has been an overall improvement in licensed operator candi-date performance during licensed examinations over the past two years. This was especially observable in the simulator exams, 6.
SUMMARY OF FACILITY COMMENTS AT THE EXIT INTERVIEW:
The facility acknowledged the. weaknesses identified in paragraphs 3. and 4.
They also. expressed their-appreciation for having the opportunity to review the written examinations prior to their being administered,
-i Attachments:
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Written Examination and' Answer Key (RO)
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Written Examination and Answer Key -(SRO)
-3.
-Facility Comments on Written Examinations and NRC's Response s
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ATTACHMENT 1 WRITTEN EXAMINATION AND ANSWER KEY (RO).
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U. S.-NUCLEAR REGULATORY COMMISSION
'e-REACTOR OPERATOR LICENSE EXAMINATION REGION
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l-FACILITY:
Calvert Cliffs 1--& 2 f
REACTOR TYPE:
PWR-CE DATE ADMINSTERED:
90/05/07 i
CANDIDATE:
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INSTRUCTIONS TO CANDIDATE:
m Points for each question are indicated in parentheses after the question.
The passing grade-requires at least 80% correct overall.
Examination Lpapers will be picked up_four red en: h:1f (4 +p44 hours af ter the
, examination starts.
i LCATEGORY; % -OF NUMBER VALUE.
TOTAL CORRECT CATEGORY
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(36'.00-36.00'
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS a
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PLANT SYSTEMS'(51%) AND PLANT-WIDE GENERIC
~ RESPONSIBILITIES (13%)-
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CORRECT OVERALL
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'All: work done.on'this examination is my own.
I have neither given
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L Candidate's signature
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NRC' RULES AND GUIDELINES. FOR LICENSE ; EXAMINATIONS ~
lDuring the_ administration of this examination the following rules apply:
1.LCheating on the' examination means an automatic denial of your application and eould result in more severe penaltica.-
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~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
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received or given assistance in completing the examination.
This must be done after you complete the examination.
13. Restroom. trips are to.be limited and only one candidate at a time-may leave.
You must avoid all contacts with anyone outside the examination rdom to avoid even the appearance or. possibility-of cheating.
4.;Use black ink or dark pencil only to facilitate legible reproductions.
S.--Print your name in the blank provided in the upper right-hand corner of
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the examination cover sheet.
6.
Fill-in the date on the cover sheet of the examination (if necessary).
7.-~You may write your answers on the examination question page or on a
' separate sheet of paper.
USE ONLY THE PAPER' PROVIDED AND DO NOT WRITE ON THE'BACK SIDE OF THE PAGE.
.8..If you write your answers on the examination question page and you need more space to answer a specific question, use a separate sheet of the paper provided.and insert it directly after the specific question.
DO NOT-WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
i 9.
Print your name in the upper right-hand corner:of the first page of each section of your answer sheets whether you use the examination question pages,or separate sheets of paper.
Initial each page.
10.-BeforeLyou turn in your examination, consecutively number each answer
' sheet, including any additional pages inserted when writing your answers on'the-examination question page.
11'.~-If you are using separate sheets, number each answer as to category and inumber (i.e. Plant Systems # 04, EPE # 10).-and skip at least 3 lines'
between answers to allow space for grading.
L12. Write-"End of Category-
" at the end of your answers to a category.
-13.; Start each category on a new page.
- 14.; Write '"Last Page" on the last answer sheet.
'15. 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 answer.
Write it out.
.16. The point value for each question is indicated in parentheses after the
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question.
The amount of blank space on an examination question page is NOT an indication of the depth of answer require '
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-- 17."Show all calculations; methods, or assumptions used to obtain an answer.
-18, LPartial: credit-may be given.' Therefore, ANSWER ALL PARTS OF THE QUESTION AND-DO' NOT -LEAVE ' ANY ANSWER BLANK.
NOTER partial credit will-NOT be given.on multiple' choice questions.
- 19.: Proportional grading will b5 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 worthJ0.25 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 deducted and your total credit.for that question will'be 0.80 instead of
~1.00'even though you got the four correct answers.
20. If the intent'of a question is unclear, ask questions of the examiner
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only.
21. When turning-in your examination,' assemble the completed examination with cxamination_ questions, examination aids and answer sheets.
In addition, turn in all scrap-paper.
22^.'To-pass the examination, you must achieve an overall grade of 80% or
_ greater.
^23.
There is a time limit of (4 1/2) hours for completion of the examination.
(or some other' time-if less than the full examination is taken.)
24. - When you are done and have turned in your examination, leave the examin-ation area as defined by the examinor.
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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EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page
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QUESTION: 01 (3.00)
EOP-7 (Station Blackout) lists five criteria that are used to confirm the existence of natural circulation (NC).
Each NC confirming criterion includes a plant parameter and a required condition for that parameter.
Two of the NC confirming criteria are the plant parameters Tcold and Thot, and the required condition for each is " Constant or decreasing." Fill in the foll'owing blanks with the OTHER three NC confirming criteria listed in EOP-7, including the parameter and the required condition for each.
(0.5 each part)
PARAMETER REQUIRED CONDITION a.
(1)
(2)
b.
(1)
(2)
c.
(1)
(2)
QUESTION: 02 (1.00)
Assume all systems have responded per design to a coincidental loss of the 500kV red and black buses with the plant at full rated power.
Which one of the following events can cause diesel generator overloading after the loss of off-site power?
a.
Reactor trip b.
SIAS actuation c.
Loss of power from SMECO (Southern Maryland Electrical Cooperative)
d.
Loss of power from DG 12 (*****
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QUESTION:'03 (1. 00 ) -
s-OI-16D(Component Cooling. System)Section III, Shifting Operating Pumps, contains the following Note:
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"Two component cooling water pumps should not be run for
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extended periods'with only one CC HX in service."
EWhic"hfone of the followingfis the reason for this Note?.
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Minimize possibility of accelerated tube erosion in on--
service CCW heat exchanger,
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Minimize possibility of one pump being at shutoff head if
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pump discharge pressures are not equal.
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Provide greater reliability since technical specification 13.7.3;1 requires both CCW loops to be operable.
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Minimize possibility of pump with higher discharge pressure
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reaching near-runout conditions.
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LQUESTION:LO4 (1. 00 )L
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Which'one of the following explains why the MSIVs'are required to be shut'at(thetstart of EOP-2 (Loss of-Offsite Power)?
- a.
Because mainisteam is not needed'since-the main turbine'has-
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sb.:
!Because the increased SG pressure in natural circulation increases the possibility.of a steam line rupture.
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Because the' automatic operation of the turbine bypass valves
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fcan cause excessive cooldown.
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Because the possibility of condenser overpressure is
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EMERGENCYcAND ABNORMAL PLANT EVOLUTIONS.
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. QUESTION: 05'
'(1.50)
FILL IN THE BLANKS -
a In:accordance with-AOP-7C (Loss of Component Cooling) if_ component
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' cooling water to the-RCPs is lost and CANNOT be restored for'
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minutes, the RCPs are required to be stopped.
Even before this; time _ elapses, however, if the temperatures on certain-or the pump-(c)-
' specifically the motor (b)
comppnents of an RCP, exceed their trip limits,
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that pump must be-stopped.
(0.5 each blank)
a
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(b)
(c)'
t QUESTION:.06:
(1.00),
If theill_ saltwater pump is started after the saltwater valves for
- the service. water heat-exchangers-have been overridden open per AOP-9A (Control' Room EvacuationLand. Safe Shutdown due to-a Severe
- Control' Room Fire), which 'one of the following explains why the ~ 11
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saltwater:pumpLdischarge valve must be-throttled?
a.-
LTo' prevent the possibility of runout on 11 saltwater pump.-
b.
To prevent excessive cooldown of the service -water system.
c.
- To prevent.long-term cavitation damage to 11 saltwater pump
. impeller.-
d.
To prevent excessive vibration of service water heat exchanger tubes.
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EMER::ENCY AND ABNORMAL PLANT EVOLUTIONS POgo. 7
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i 7 QUESTION: 07 (2.00)
Ifca: fire requires deenergizing one of the Unit i vital 480vac buCes-(11A, 11B, 14A OR 14B), the associated vital 480vac MCC may
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b], cross-tied to restore. power from the counterpart 480Vac bus.
Lict-the=FOUR (4) Unit i vital 480Vac MCCs (as designated in OI-27D,. Station Power 480-volt System) that may be cross-tied to
= restore power.
(0.50 each)
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(3)
(4):
-QUESTION: 08 (1.50)
IfLa; fuel. handling. incident in the containment building results in
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. atmosphere, the-containment radiation signal should actuate and the. containment purge isolation valves should automatically close-(if-not already closed).
List the THREE (3) other non-duplicate
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- systems / components listed in AOP-6D (Fuel' Handling Incident) that
- chould be operated '(if not already running) to reduce containment activity or prevent releasing this activity to the environment.
(0.5 each)
q 7(1)-
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QUESTION:1 09 (2.00).
'On.a reactor trip, if one CEA' fails to fully _ insert, EOP-0 (Post-
~_ Trip lImmediate; Actions) requires the operator to borate
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f(a)
ppm.
The-THREE:(3)' steps the operator is directed to Eperform to initiate this boration are:-
-(0.5 each blank)
(b),
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'(c).
and
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- QUESTION
- 10 (1. 00 ).
J-The plant has been operating at full rated power for more than two
. hile reviewing his panels, the-reactor. operator notes-weeks.
W that since his:last review, the. megawatt output meter has
" decreased by;about 25 MW, while reactor' power, Tref, and Tavg have remained constant.
Which one of the-following-is the most
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likely cause of-this unnoticed output power / reactor power mismatch?
. a ',
'A_ largo load' reduction on=the grid.
<b.
Alfeed-excursion causing increased SG. levels.
-c.;
'A-leaking SG code safety valve.
-d.;
An air: leak in.the. main condenser..
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EMERGENCY AND ABNORMAL PLANT' EVOLUTIONS-Pr.gD-9.
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QUESTION:. ll:
( 1. 00 ) -
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HIf RCS specific' activity exceeds the limits of Technical Sp;cification 3'.4.8,'the required action is to go to Hot Standby
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Jand reduce Tavg'to less than 500 degrees F.
Which one-of the'
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following is~the reason Tavg must be reduced to less than 500
d:grees F?
J c.-- 'This temperature has a saturation pressure that is below the lift pressureLof the main' steam safeties.
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b.
.This' temperature will contract small fuel defects and prevent
=further-release of fission products to the RCS.
'c..
. Reducing RCS temperature will increase the. efficiency of the
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CVCS letdown ion exchangers.
d.
Reducing RCS temperature :will ' increase the adherency of the-RCS-corrosion film'and minimize any crud burst in progress.
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' QUESTION: 12 (1.00)
For'a steam line rupture-inside containment, EOP-4-(Excess Steam
.Damand) requires maintaining the unaffected steam generator (SG)
'within'25 degrees F of core exit temperature while the'affected SG f,
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.is blowing down. nWhich'one of.the following is the reason for
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Emaintaining this 25' degrees F. differential?
a.
To maintain an adequate RCS subcooling. margin.
b b'-
To establish natural circulation flow'if RCPs must be l
' stopped.
~ c.
To prevent the plant cooldown rate from exceeding
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100 degrees F/hr.
d.
To limit RCS heatup after affected SG blowdown is complete.
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QUESTION: 13 (1.00)
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"If power-is lost =to 120vac vital instrument, bus 11 (1Y01), ESFAS
actuation cabinet-ZA.and ESFAS sensor cabinet ZD will be
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'dt;nergized.
When power is restored to 120vac vital instrument
bua 11 (1YO1),= the operator must ensure verbatim compliance with
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= thn.OI-34 (ESFAS System) procedure to return these cabinets to oparAtion. 'Which one of the following is the proper sequence to baffollowed'when-returning these cabinets to operation?
t Ec.
' Sensor (ZD) cabinet before actuation (ZA)' cabinet; bias power-(15vdc).before actuation power (28vdc)
-b..
" Sensor -(ZD)- cabinet before actuation (ZA) cabinet;. actuation'
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. power (28vdc) before bias power (15vdc)
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Actuation (ZA) cabinet before sensor (ZD) cabinet; bias power -
- (15vdc)1before-actuation power.(28vdc)-
Ed.,
7 Actuation : (ZA) - cabinet before sensor (ZD) cabinet; actuation
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power:(28vdc) before bias power (15vde)
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. QUESTION: 14-(1.00)
. Unit ~171s~ operating at rated load when a-shutdown group CEA drops.
11nto the coreL(fully = inserted).
Assuming the reactor does not
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. trip,. what' color status light (s) will be' illuminated-for'the
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-Amber only
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b.
Amber and green only
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c.
Amber, green, and blue only d..
' Amber', green, blue, and: red g
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EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page:11
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QUESTION: 15
. (1. 00)'
While responding to an_ actuation of annunciator C-43 (MAIN STEAM EFFL' RAD MONITOR), - the CRO observes that 11 SG rad monitor (RIC-5421)L is; indicating-below his shift-turnover grease mark.
What other ' indication should the CRO observe on -RIC-5421 to confirm the
" keep-alive" source has failed in this rad monitor?
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" QUESTION: 16 (1.00)
LUnit 2 is operating at 50 percent load during a load increase with 21 SGFP operating in automatic and 22 SGFP started and in standby.
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'21 SGFP trips resulting in a low S/G level-reactor trip and turbine trip.
Why does AOP-3G'(Malfunctions of MFW System)
croquireithe. operator to feed the S/Gs using the AFW system.instead
.of using 22 SGFP?
a.-
To minimize'the possibility of overfilling the.S/Gs.
b.
To minimize the possibility of water hammer in the main feedwater system.
c.;
To minimize the' possibility of thermal shock to the S/G feed 5:.
ring J-tubes.
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Jd ?
sTo ensureLthe'most' reliable source of feedwater-is'used to ib restore S/G' level.
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S' QUESTION: 17 (1.00)?
O tUnit 1 was manually' tripped'from rated load because of a slow
-uncontrollable decrease in RCS pressure.
A SIAS automatically
initiated a shortLwhile ago and current indications'are as J
follows:
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RCS~ pressure - 1600-psia and decreasing
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CETE-537 degrees F
. - 10 inches and decreasing
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Pressurizer level (LIC-110X)
. Pressurizer level (LIC-110Y) - > 360 inches Containment: pressure - 1.5 psig i
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~ Normal containment sump =- high level alarm l
Quench tank level - 28' inches and stable
' Quench; tank temperature - 100 degrees F and stable What failure could have caused the above events and indications?
a.:
A-pressurizer' reference leg has' ruptured, b.
A pressurizer spray valve has failed open.
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c.
A pressurizer'PORV has failed open.
d.-
A pressurizer heater well has ruptured.
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EQUESTION: - 18 '
(1.00).
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Unit 2 is. operating at rated-load with RCS boron: concentration'at 2800ippm:when a' reactor trip (no SIAS) occurs.
The RO determines
- thatJTWO'CEAs fail to fully insert and begins emergency boration.
fin accordance with (EOP-0) Post-Trip Immediate Actions, emergency.
,
sboration must. continue until.RCS boron concentration is at least:
a.
1000 ppm.
E b.
- .1200 ppm
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c.,
1700 ppm
- d.
2300 ppm L.
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QUESTION: 19 (1.00)
-Unit 2 is recovering from a LOCA in accordance with (EOP-5) Loss of Coolant Accident, with current conditions as follows:
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RCP status - OFF l
, RCS pressure
.1200 psia and decreasing Highest T-hot - 525 degrees F and stable Highest CET - 540 degrees F and stable RVLMS -'100 percent
^^
Pressurizer level --108 inches and increasing 11 S/G level - (-)85 inches and increasing 12 S/G 1evel -.(-)So inches and increasing Do. plant ~ conditions meet the criteria for throttling HPSI flow in cccordance with step M.4 of EOP-5 (attached)?
a.
Yes, but only if at least one S/G has a steaming path, a
b.
Yes,'but only if pressurizer level continues-to increase.
'c...
'No, because pressurizer level criteria is not satisfied.
d.
No, because subcooling criteria is not satisfied.
QUESTION: 20 (1.50)
List the alternate operator actions required by EOP-O (Post-Trip
<Immediate Actions) to insert the CEAs if an automatic and manual
. reactor trip fail to insert the CEAs.
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RECOVERY' ACTIONS'-
ALTERNATE ACTIONS
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- NOTE -
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'A break on topfof Pressurl:er will~ result in'an uncontrollable i-increase'in pressurizer level
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.until Pressurizertis solid, t
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Maintain pr'essurizer level
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between 10liand'160 inches.
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-- CAUTI ON ' -
'Do notJthrottle-HPSI flow unless
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p 'f-30 F subcooling.can-be
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maintained.
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a.
If the following.
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conditions can be
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maintained:
-(l) Atuleast 30 F
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- subcooling.
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(2) Fressurizerclevel
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. greaterEthan'101
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a (3)lAt least one S/G l'
available for' heat
- removal.
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.(4) RVLMS indicates that
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the Core is covered.
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l THEN, throttle HPSI flow i
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or, operate Charging Pumps as necessary to maintain pressurizer level between'
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101 and 160 inches.
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' EMER' ENCY AND ABNORMAL PLANT EVOLUTIONS -
Paga;14:
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. QUESTION: 21:
(2.00)?
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List the FOUR (4); plant parameters that are monitored to' ensure-
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tha Technical' Specification requirements,for DNB are being met.
(0.5~each)
(1)
s l(2)l
.
(3)-
-(4)
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.o-QUESTION: 22 (1.00)
uj
. Unit 2--hasfexperienced.a tube' rupture in 21 S/G and a loss.of Joffsiteipower.-' An RCS=cooldown is in progress by steaming 22 S/G-to-atmosphere.
During the cooldown the CRO observes that loop 21
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DT-hot:is1500 degrees'F and-loop 21 T-cold is 525: degrees F; The
,
'CROpshould:
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(Continue-the RCS cooldown.because'the. temperature indications
are expected.
cj
,a T b '.., Continue the RCS cooldown expecting to see' loop 21 T-cold j
decrease and1T-hot increase.
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c..
>Stop?the RCS cooldown until' normal natural. circulation is.
established-in loop 21.
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d.-
- -Stop.the RCS cooldown because the wrong.S/G is being steamed'.
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QUE5 10N: 23 (2.50)
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List FIVE (5) non-duplicate process fluid radiation monitors in
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the control room that could show an increase in the event of a 100 gpm tube leak in 11 S/G.
(0.5 cach)
(1)
-
(2)
(3)
1-(4)
[
(5)
w-rUESTION: 24 (1.00)
Unit 2 is on shutdown cooling with 21 LPSI pump running and the reactor vessel heau removed.
The RCS is at 140 degrees F when
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21 LPSI pump trips.
Prior to starting the other LPSI pump, the CRO must:
a.
close the SDC flow control va3va. SI-306-CV.
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b.
determine cause of LPGI pump trip.
c.
reset and restart the tripped LPSI pump.
o.
or, the SDC temperature control valve, SI-657-CV.
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(36%)
I l-QUESTION: 25 (1.00)
Unit 2 has experienced a loss of all feedwater event with T-ave at 550 degrees F and increasing.
A caution in (EOP-3) Total Loss of All Feedwater, states:
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"After S/G becomes ineffective for heat removal, Once Through
. Core Cooling must be initiated prior to CET temperature reaching 560 degrees F to ensure adequate heat removal."
Wh t is the basis for the 560 degrees F CET limit?
E Q.
It corresponds to a saturation pressure low enough to allow adequate !! PSI flow.
b.
It corresponds to a saturation pressure low enough to prevent reactor vessel head voiding.
c.
It ensures a minimum RCS cubcooling of 30 degrees F at the pressurizur PORV lift setpoint.
d.-
It ensures an adequate shutdown margin exists prior to commencing the cooldown.
QUESTION: 26 (1.00)
What is the purpose of realigning HPSI flow for pressurizer injection after a-large-broa): LOCA occurs?
i QUESTION: 27 (1.00)
.Whtt is the adverse effect associated with operating both letdown control valves simultaneously with Unit 1 at power?
G.
Water hammer in the letdown system
[
b.
Thermal transients in the letdown system c.
Unstable VCT level control d.
Unstable prossurizer level control (*****
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EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 17 L.
-(36%)
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QUESTION: 28 (1.00)
.Tho 11 reactor coolant waste monitor tank is being released via Unit 1 with all circulating sater pumps operating.
Which one of
'
th3 following occurrences could result in an EFFLUENT HIGH RADIATION alarm and automatic termination of the release?
a.
, Inadequate flushing of the radiation monitor detector after-the last discharge.
b.
Stopping one Unit 1 circulating water pump during release.
c.
Adjusting the setpoint of effluent radiation monitor, RE-2201, to twice the value listed in the discharge permit.
d.
Throttling effluent flow rate to one-half of the value listed in the discharge permit.
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QUESTION: 01 (1.00)
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Which one of the following describes the proper sequence for
!
. operating the CCW heat exchanger outlet valves (CCW or SW) when Lchifting from 11 CCW heat exchanger in service to 12 CCW heat l
.cxchanger in service?
'
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.Open 12 CCW outlet; open 12 SW outlet; shut 11 SW outlet; shut 11 CCW outlet.
b.-
Open 12 CCW' outlet; shut 11 SW outlet; open 12 SW outlet; shut'll CCW outlet.
c.
Open 12 SW outlet; open 12 CCW outlet; shut 11 CCW outict; shut 11 SW outlet.
d.
Open 12 SW outlet; shut 11 CCW outlet; open 12 CCW outlet; shut 11 SW outlet.
QUESTION: 02 (2.00)
MATCHING For each type of radiation monitor listed in Column A, select the type of radiation detector from Column B that is used at Calvert Cliffs in that type of monitor.
(0.5 each)
Note:
Choose ONLY ONE detector type from Column B for each radiation monitor type in Column A; however, some detector types l
may not be used at all and some detector types may be used in more
then one type.of monitor.
l-COLUMN A COLUMN D a. Air particle process monitors (1) Geiger-Mueller detector b. Gaseous process monitors (2) Proportional detector I
c.
'iquid process monitors (3) Fission chamber d.-Normal (low-range) area monitors (4) Scintillation detector
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-QUESTION: 03'
(1.00)
If a 4kV breaker is automatically tripped due to actuation of the
[
CD;ociated lockout relay, which one of the following actions must b3 taken to prepare the breaker for closing after the cause of the trip is corrected?
i O.
. Turn the brc her control switch on the main control board to-the TRIP position.
b.
Locally move the breaker handle from the trip-free position to the-tripped position.
c.-
Locally depress the trip button on the breaker front panel.
,
d..
Locally reset the lockout relay on the breaker front panel.
QUESTION: 04 (1.00)
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Choose the combination below which properly states the acthod of op rating the_4kV-disconnect switches for the followirg pumps: 13
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cervice water pump; 13 HPSI pump; and 23 saltwater pu.np.
13 SRWP 13 HPSI 23 SWP
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D.
-Electrically Manually Manually b.
Manualf.y Electrically Manually
)
c.
Electrically Manually Electrically-d.
Manually Electrically Electrically
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QUESTION: 05 (2.00)
j FILL IN THE BLANKS AJ pressurizer level is decreasing below the level setpoint, the
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prCasurizer level control system starts the first backup charging
. pump at (a)
inches below the setpoint and the second
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b:ckup charging pump at (b)
inches below the setpoint.
As pressurizer level is returning to the level setpoint, the first j
p b2ckup pump is stopped at (c)
inches-below the setpoint cnd the second backup pump is stopped at (d)
inches
,
l below the setpoint.
(0.5 per blank)
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QUESTION: 06 (1.00)
Which one of the following is the reactor power signal used by th3 Metrascope (Qmet)?
c.
The maximum Qpower b.
The average Opower c..
The average linear range NI power d.
Thermal power (PA912)
,
QUESTION: 07 (1.00)
Which one of the following will cause the 12 LPSI PUMP SIAS BLOCKED AUTO START annunciator to actuate ONLY AFTER a pump start eignal is initiated?
i n.
Pump handswitch in pull-to-lock b.
Pump breaker closing spring broken c.
' Pump control transfer switch in local b
'd.
Pump breaker racked out i
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PLANT SYSTEMS (51%) AND PLANT-WIDE CENERIC P;g3 21
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j QUESTION: 08.
(3.00)
FCr EACH of the below-listed valves, select ONE of the following cffects that will result from a rupture of the containment instrument air header that occurs downstream (inside) of the
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ccntainment instrument air control valve (IA-2085).
L (0.5 each)
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Effects:
= fail open/ flow goes to maximum
>
FC
= fail closed / flow is stopped FAI = fail aus is/ flow cannot change DNF = does not. fail / valve operation not immediately affected EFFECT VALVE (S)
a. Containment instrument air control valve (IA-2085)
b.
Pressurizer normal spray valves (RC-100 E/F)
c. RCS loop charging control valves (CVC-518/519)
d. Auxiliary pressurizer spray valve (CVC-517)
c. RCP constant bleedoff relief isolation valve (CVC-507)
f. Component cooling containment isolation valves (CC-3832/3833)
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QUESTION: 09 (2.00)
Provide the nominal setpoints at which the pressure signal from PT-103-1 (low-range pressurizer pressure transmitter)
ganerates an actuation / enabling signal in the following valve control' circuits.
(0.5 each)
psia a. Open SI-634/644 (isolation valves for safety injection tanks)
psia b. Shut SI-652 (shutdown cooling return valve)
psia c. Enable MPT protection on Unit 1 l
_ psia d. Enable MPT protection on Unit 2 l
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PLANT SYCTEMS (51%)-AND PLANT-WIDE GENERIC Page 22 RES PONSIBILITIES (13%)
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QUESTION: 10 (1.00)
Which-one of the following correctly states the RCS temperature inputs used in the thermal margin / low pressure (TM/LP) calculator-to calculate delta-T power for use in the variable overpower trip unit?
c.=
.Auctioneered high Thot and averaged Tcold b.
Auctioneered high Thot and auctioneered low Tcold c.
Averaged Thot and auctioneered low Teold d.
Averaged Thot and auctioneered high Tcold QUESTION: 11 (1.00)
Technical Specifications (Mode 6) require a minimum level of borated water be maintained above the top of irradiated fuel
. assemblies seated in the reactor vessel during movement of CEAs.
Which-one of the following identifies the Technical Specifications basis for the required minimum level?
-a.
Shutdown margin considerations for inadvertent CEA movement b.
Heat removal considerations for irradiated fuel assemblies c.
Iodine removal considerations for a ruptured fuel assembly d.
Personnel shiciding considerations for irradiated fuel assemblics
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QUESTION: 12 (1.00)
If Reactor Regulating System (RRS) channel X is initially j
c;1ected, which one of the following correctly states the minimum l
C tions that must be taken to obtain an accurate T-average signal
>
Cfter a coincident failure of the in-use RTDs in the loop 1 hot les and loop 1 cold leg.
- O.
Shift from RRS channel X to RRS channel Y.
b.
Select RRS channel Y and shift selector switch HS-111 in the bottom section of ICO6.
c.
Select OFF on the loop 1 selector switch for RRS channel X.
d.
Shift selector switch HS-111 in the bottom section of 1CO6.
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PLANT SYSTEMS (51%) AND PLANT-WIDE CENERIC
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QUESTION: 13 (2.00)
l Accume that the 4kV emergency diesel generator (EDG) disconnect cwitches are lined up normally for at-power operations with all
EDGs operable.. For each of the following situations, fill in the cccociated blanks with the following information.
. (1) Which, if any, 4kV EDGs will automatically start.
(2) Which, if any, 4kV EDGs will be automatically connected to a bus (i.e., an EDG feeder breaker will close).
-,
Situations: (Assume each situation occurs separately.)
c.
4kV bus 14 (only) suffers loss of voltage (no lockout).
i b..
4kV' buses 14 and 24 suffer loss of voltage (no lockout).
c.
4kV bus 11 (only) suffers loss of voltage (no lockout).
d.
A loss of voltage (no Jockout) occurs on 4kV buses 11 and 21 coincident with a design-basis LOCA on Unit 2 (only).
'
(1) EDGs THAT START (2) EDGs AUTOMATICALLY CONNECTED c.
b.
c.
d.
__
' Note:.Your answer should be either specific EDG numbers or ALL or
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NONE..
(0.25 each blank)
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QUESTION: 14 (1.00)
Unit 1 is in Cold Shutdown and 12A RCP is about to be started.
'
Which of the following conditions ensures an interlock is C;tisfied that' enables 12A RCP to start when its control switch is pieced in the START position?
G.
12A RCP oil lift pump must have operated for 60 seconds.
I b.
All RCS cold leg temperatures must be > 275 degrees F.
c.
The " COMPONENT COOLING FLOW LO" alarm is clear.
d.
The " OIL RSVR LEVEL LO" alarm is clear.
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QUESTION: 15 (1.00)
Unit 1 is operating at 40 percent load with a load increase in progress when a "CEA POSITION DEVIATION" alarm is received and a
,
CEA in regulating group 5 is observed to be S inches below the group position.
In order to align the CEA with the group, the
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opsrator must:
c.
Bypass the CEA Motion Inhibit in effect by depressing the Group Inhibit Bypass pushbutton on CEDS.
b.
. Bypass the CEA Motion Inhibit in effect by depressing the Group Inhibit Bypass pushbutton and the Motion Inhibit Bypass pushbutton on CEDS.
-
t c.
Select-the Manual Individual mode, the affected group, and the CEA to be withdrawn on CEDS.
Bypass pushbutton(s) do not i
need to be depressed, d.-
Select the Manual Group mode, the affected-group, and the CEA
,
to be withdrawn on CEDS.
Bypass pushbutton(s) do not need to be depressed.
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i QUESTION: 16 (1.00)
Unit 2 is in.the process of CEA insertion during a reactor l
Chutdown when the "SHL.DOWN GROUP INSERTION PERMISSIVE" alarm is
,
r:ceived.
This alarm first actuates when:
c..
One CEA regulating group is inserted below 10 inches.
b.
~.'
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All CEA regulating groups are inserted helow 10 inches.
c.
One CEA shutdown group is inserted below 129 inches.
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d.
All CEA shutdown groups are inserted below 129 inches.
,
-QUESTION: 17 (1.00)
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l Wh:t is the purpose of the handwheel on liquid waste discharge
!
icolation valve, MWS-2201-CV?
a.
Allows the operator to manually open the valve to commence a liquid radwaste discharge if control air is lost.
'
b.
Allows the operator to manually close the valve in the event of high effluent radioactivity and a failure of automatic
valve closure.
Allows the operator to manually open the valve following an c. '
automatic valve closure to flush the, radiation monitor and discharge header.
i 6.
Allows the. operator to manually close the valve as necessary to. throttle the effluent flow rate below the value entered in the discharge permit.
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QUESTION: 18 (1.00)
Th3 waste gas, compressors are operating normally when the lead compressor fails to cycle off as waste gas surge tank. pressure d: creases.
How will the waste gas surge tank be protected from Cxcessive vacuum?
'
L-c.
,A tank relief valve will open to the atmosphere.
E b.
A rupture disk on the surge tank will rupture.
'
c.
An isolation valve in the compressor suction line will close.
d.
A nitrogen supply valve on the surge tank will open.
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QUESTION: 19 (1.00)
Wh t is the basis for the Technical Specification limit on oxygen
content in the waste gas decay tanks?
o-Minimize tho' possibility of corrosion in the tanks.
.
b.
Minimize the possibility of an explosive gas mixture in the tanks.
c.-
-Minimize the amount of radioactive oxygen released to the atmosphere, d.
Minimigo the amount of non-radioactive gases contained in the tanks.
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QUESTION: 20 (1.00)
l A waste gas decay tank is'being released through the Unit i vent wh n a waste gas discharge radiation monitor (RI-2191) alarm is rOceived.
Assuming all automatic actions occur as expected, what valve must be manually shut to prevent subsequent wante gas decay
t:nk discharge to the waste gas surge tank?
._
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i c.
Waste gas discharge isolation valve - WGS-2191-CV
b.
Waste gas discharge isolation valve - WGS-2192-CV c.
Waste gas discharge pressure control valve - WGS-2191-PCV d.-
Waste gas discharge pressure control valve and filter
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bypass - WGS-630
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f QUESTION: 21 (1.00)
,
Unit 1 is operating at rated load when an inadvertent actuation of
,
c channel B AFAS Start signa) occurs and seals in.
Which AFW pump (s), if any, will automatically and immediately start?
O.
'One turbine-driven AFW pump only b.
.AFW pump 13 only
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c.
One turbine-driven'AFW pump.and AFW pump 13
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None, until at least 18 seconds has elapsed
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A reactor trip has occurred on Unit 2 and AFW pumps 21 and 23 are
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cperating and feeding both steam generators when a loss of L
instrument air pressure occurs.
Assuming no operator actions are t ken, AFW flow rate to the steam generators will initially:
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. increase, because the 21 AFW pump turbine will increase
speed.
I b.
increase, because all AFW flow control valves associated with AFW pump 23 will fail open.
'c.
decrease, because the 21 AFW pump turbine will decrease speed.
e d.
decrease, because all AFW flow control valves associated with AFW pump 23 Will fail closed.
QUESTION: 23 (1.00)
Unit 2 is operating at 60 percent load with a hot leg temperature of 590 degrees F.
What will be the approximate reading on average core exit thermocouple temperature indication?
a.
566 degrees F
b.
578 degrees F c.
602 degrees F-d.
614 degrees F
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QUESTION: 24 (1.00)
.
Unit 1 is operating at 70 percent load when a spurious AFAS occurs
- nd seals in.
If no operator action is taken and the reactor does-nit trip, how will main feedwater flow, feed regulating valve po ition, and S/G 1evels be affected when the plant stabilizes?
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FEED REGULATING MAIN FEEDWATER FLOW VALVE POSITION S/G LEVEL C.
Lower More closed No change
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b.
No change More closed Lower c.
Lower More open Higher d.
No change More open Unable to determine
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QUESTION: 25 (1.00)
If a large fire requires all Unit 2 vital instrument buses to be d 3nergized, what electrical system design feature allows Unit 2 nuclear power to be monitored at 2C43 (Aux Shutdown Panel)?
QUESTION: 26 (1.00)
During a Unit 2 load increase from 50 percent to 100 percent, a
" NUCLEAR INSTRUMENT CHANNEL INOPERATIVE" alarm is received.
Which of the following failures could have caused this alarm?
n..
Power range safety channel A power summer output fails high.
b.
Power range safety channel B upper detector output f ails 1.ow, c.
Power range safety channel C control power fuse blowe.
d.
Power range safety channel D high voltage power supply fails low.
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QUESTION: 27 (1.00)
A cmall feedline break has occurred inside Unit 1 containment and hra resulted in containment temperature increasing from 100.
d:grees F to 160 degrees F.
Disregarding any effects'from RCS or c:ntainment pressura changes, what effect will-this increase in l
c;ntainment temperature have on the pressurizer level indicated by
'
L:0,110X/Y?
'c.
Indicated level will be higher than actual level.because the
'
reference leg fluid density decreases.
b.
Indicated level will be lower than actual level because the reference leg fluid expands and spills back into the pressurizer, c.
Indicated level will be higher than actual level because the elevated containment temperature causes flashing in the reference leg.
d..
Indicated ~ level will be lower than actual level because of the high temperature effects on the differential pressure-detector.
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QUESTION: 28 (1.00)
Unit 1 is in Hot Standby with the following parameter values.
RCS pressure - 1800 psia Loop 11 T-cold - 535 degrees F Loop 11'T-hot - 540 degrees F l
Loop 12 T-cold - 536 degrees F Loop 12 T-hot - 544 degrees F i
l What' temperature and pressure values would be indicated on the cubcooled margin monitors?
G.
81 degrees F, 805 psia b.
77. degrees F, 963 psia c.
81 degrees F, 963 psia d.
77 degrees F, 805 psia (*****
CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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PLANT CYSTEMS (51%) AND PLANT-WIDE CENERIC Pzg3 32 RESPONSIBILITIES (13%)
i I
QUESTION: 29 (1.00)
.
Unit 2 is shetdown following a small LOCA..
It is determined that rc:ctor vessel eenting is required to collapse a void in the VC:sel head.
When: reactor vessel vent valves, RC-103-SV and RC-104-SV are-opened, 'he discharge will be directed _to the:
.
c.
,. Containment b.
Quench tank c.
Reactor coolant drain tank d.
Volume control tank QUESTION: 30 (1.00)
'Whnt parameter is measured to automatically activate a CVCIS if a Ictdown line rupture occurs outside containment, a'
Temperature
.
b.
Pressure
,c.
Flow rato d.
Sump level l-l (*****
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i F-PLANT SYSTEMS-(51%) AND PLANT-WIDE GENERIC P;ga 33 RESPONSIBILITIES (13%)-
L
.
!
QUESTION: 31 (1.00)
' Unit 1 is operating at 30 percent load when FT-1111,. main fC dwater flow transmitter output to the main feedwater regulating i
cy; tem falls high.
The main feedwater regulating system responds CJ designed in automatic and no operator actions are taken.
A; uming.the reactor does not trip, how will 11 S/G level respond?
'
-
.
.
C.
Level will initially decrease, then stabilize at a lower
~1evel, b.
Level will initially decrease, then increase and stabilize at
-the same level.
c.
Level will initially increase, then stabilize at a higher level.
,
d.
-12 Vel will initially increase, then decrease and stabilize at-
,
the same level.
,
i i
,
-QUESTION: 32-(1.00)
Unit 1 is operating at 90 percent power when a liquid waste Gyrporator is placed in service resulting in a 20 degree F increase in CCW system temperature.
Assuming no automatic actions occur in the CVCS, and no operator actions, how will the reactor bo affected?-
G; Reactor power will initially decrease because the CVCS lon e
'
exchangers are releasing boron into the letdown flow.
b.
Reactor power will initially increase because the CVCS lon exchangers are absorbing boron from the letdown flow, c.
Reactor power will-initially decrease because T-ave is being i
increased by hotter CVCS charging flow.
d.
Reactor power will initially increase because T-ave is being decreased by hotter CVCS charging flow.
.-
- -
I (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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- PLANT SYSTEMS (51%) AND PLANT-CIDE CENERIC P29] 34 RESPONSIBILITIES (13%)
L
.
QUESTION: 33 (1.00)
Unit 1 is in the recirculation phase following a LOCA with current
[-
conditions as follows:
RCS pressure - 200 psia Pressurizer level - O percent RWT level - 25 inches
.
containment pressure - 1 psig In order to start the LPSI pumps with the above conditions, the CRO must:
O.
match the control switch to the actual pump condition and then start the pump, b.-
reset the RAS at 1C10 or the RAS logic module, c.
override the RAS for the LPSI pumps.
d.
stop the llPSI pumps until after the LPSI pumps are running.
QUESTION: 34 (1.00)
Unit 1 is operating at 100 percent power when a shutdown group CEA drops into the core (fully inserted).
The reactor does not trip cnd no operator actions are taken.
Ilow will shutdown margin-(SDM)
b3 affected.
c.
SDM will increase.
b.
SDM will decrease.
c.
SDM will remain the same, d.
The change in SDM cannot be determined unless more information is given..
l-(*****
CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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j PLANT SYSTEMS (51%) AND PLANT-WIDE CENERIC P293_35 RESPONSIBILITIES (13%)
i QUESTION: 35 (1.00)
,
L Chat is the reason for LIMITING the number of RCP starts in a
- given period?.
O.
Minimize pitting of starter contacts.
'
b.
, Prevents excessive torsional stresses on notor shaft.
c.
Prevents overheating of motor windings.
[
d.
Minimizes axial stresses on motor bearings.
i i
QUESTION: 36 (1.00)
Prior to initiating withdrawal of fuel assemblies from the reactor
'
vcacel, at.least channel (s) of audible source range
indication and channel (s) of visual source range indication must be operable in the control room.
C.
1; 2.
'
b.
2; 3-
'
c.
3; 2 d.
2; 1
-QUESTION: 37 (1.50)
<
,
C.
List the TWO Engineering Safety Feature Actuation Signals (ESPAS) that can be BLOCKED.
(0.5 each)
t b.
How many of the four sensor channels must reach the BLOCK setpoint to permit blocking of the associated ESFAS signals?
(0.5)
,
(*****
CATEGORY 3 CONTINUED ON NEXT PAGE *****)
o
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PLANT' SYSTEMS'(51%) AND PLANT-WIDE GENERIC Page 36 RESPONSIBILITIES (13%)
.
-QUESTION: 38 (1.00)
Which of the following describes the operation of the charging pumps when the Charging Pump Selector Switch on 1C07 is in the "13 cnd 11" position.
c.
12 - running,113 - first backup, 11 - second backup
~
b.
13 - running, 11 - first backup, 12 - second backup c.
13 and 11 - running, 12 - backup d '.
-12 - running, 11 - first backup, 13 - second backup QUESTION: 39 (1.00)
A steamline break has initiated inside Unit 1 containment with current conditions as follows:
, Containment pressure = 7 psig
- Containment radiation = normal
- S/G levels = -145 inches and -185 inches
- PZR pressure = 1800 psia
'
- RWT level = 30 feet
- S/G pressure = 680 psia and 580 psia lUsing the above information, select the group of actuation signals
'
that should have occurred, a.
SIAS, SGIS, CIS, AFAS BLOCK b.
SIAS, CSAS, SGIS, CIS, AFAS c.
,
(*****
CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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. PLANT CYSTEMS (51%) AND PLANT-WIDE CENERIC Pr.go 3 7 l
RESPONSIBILITIES - (13 %)
.
QUESTION: 40 (1.00)
-
Unit 1 has experienced a LOCA during which a CIS actuation has occurred.
Which one,of the following must occur to allow r cetting CIS?
c.
The reset time delay must time out.
'
b.
All CIS isolation valves must have reached the fully shut position.
c.
All CIS isolation valve control switches must be placed in CLOSE.
-l d.
Both reset pushbuttons must be depressed simultaneously.
QUESTION: 41-(1.00)
' Unit 2 is at normal operating pressure / temperature when 12B RCP Experiences a single and complete failure of its middle seal.
Which one of the following sets of seal parameters indicates this failure?
MIDDLE SEAL UPPER SEAL PRESSURE (PSIA)
PRESSURE (FSIA)
'a.
1150 100 b.
2200 1100 c.
1150 1150 d.
2200-2200 i
!
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PLANT SYSTEMS-(51%) AND PLANT-WIDE GENERIC Prgi 38 f
,
' RESPONSIBILITIES (13%)
.
.
.
' QUESTION: 42 (1.00)
Unit 2 is operating at rated load when an inadvertent CSAS is g;nerated.
What prevents spray down of the containment?
,
as The spray header isolation valves are closed because they require.an SIAS to open..
,
b.
'The spray header isolation valves are closed because they require both CSAS and SIAS to open.
c..
The containment spray pumps are stopped because they require an SIAS to start.
r d..
Tne containment spray pumps are stopped because they require both CSAS and SIAS to start.
QUESTION: 43 (1.50)
,
In addition to the two steam generator low level trips, what are THREE (3) other RPS trips that CANNOT be bypassed, either cutomatically or manually?
(0.5 each)
-
'
-(1)
(2)
.(3)
>
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"~
PLANT SYCTEMS (51%) AND PLANT-WIDE GENERIC PO93 ~ 3 9
,
RESPONSIBILITIES (13%)
i l
a-QUESTION: 44 (1.00)
During verification of a FULLY OPEN manually operated valve, the cperator should:
O, fully close the valve, then reopen the valve to the fully open position.
~
b.
operate the valve handwheel in the open direction, if the handwheel does not move, the valve is fully'open.
c.
operate.the valve handwheel in the open direction until the
. valve is backseated one-half turn.
d.
operate the valve handwheel in the close direction, then reopcn the valve to the fully open position.
r QUESTION: 45 (1.00)
Tho MAXIMUM fluid system temperature and pressure chat'can. exist during component repair WITHOUT requiring two valve isolation are i
degrees F and psig.
.
a.
200, 500 b.-
200, 1000
c.
212, 500 d.
212, 1000
,
I l
l
{
i l
P (*****
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' PLANT ' SYSTEMS ' (51%) AND ' PLANT-WIDE CENERIC P;gi 4 0 RESPONSIBILITIES.(13%)
J
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!
.
QUESTION: 46 (1.00)
,
i
.
.
i F r which of the following reasons may the CRO leave the control i
room routine surveillance area without first being relieved?
12.-
Verify receipt of alarmr,and initiate corrective actions.
i-
,
'
b.
p
, Complete control room logs and hang safety tags.
f.
c.
Conduct shiftly control room-tour and communicate with CRS or p
SS.
!
d.-
Obtain controlled keys and review shift supervisor's log.
,
QUESTION: 47 (1.00)
"
A 25 year-old licensed male reactor operator has the following cxposure history:
i Lifetime whole body dose - 34 rem Current quarterly.whole body dose - 400 mrem Ancuming-his exposure is properly documented, what is the-maximum
.cdditional whole body exposure this operator can receive this E
qu2rter and still comply with 10 CFR 207
.a.
600 mrem-
,
b.
825 mrom
'
c.
2600 mrem d.'
2825 mrem
.
I i
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PLANT SYSTEMS (51%) AND PLANT-WIDE CENERIC P^ga 41
'3 RESPONSIBILITIES (13%)
an,
.
QUESTION: 4b (1.00)
In order.to perterm a proper shift relief, the oncoming CRO must
.
Cc::plete the applicable Shif t Turnover Checklist:
'O.
prior to beginning verbal turnover, b.
.! prior to relieving the on-shift CRO.
.c.
after relieving the watch and within the first two hours of shift.
,
,
Ed.
after relieving the watch and before the end of shift.
,
t
" QUESTION: 49 (1.00).
EOP-1 directs the operator to, " Verify heaters or sprays restoring pr ssurizer pressure to between 2225 and 2275 psia." When used in-ths previous example, the term " VERIFY" means:
c.
to make sure by taking necessary or appropriate actions.
b.-
to observe an expected condition or characteristic;- to determine; to-ascertain.
c.
to watch or monitor; to visually take note of; to pay attention to.
.d.
to attend to displays to determine equipment operating conditions.
.
I l-(*****
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' PLANT SYSTEMS (51%) 2 AND PLANT-WIDE CENERIC P:go 42.
.
RESPONSIBILITIES (13%)
,
t
' QUESTION: 50 (1.00)
A licensed reactor operator working in a' controlled area has been 12 ued a 0 - 200 mrem Self-Reading Dosimeter.
Assuming his qurrterly whole body exposure limits are not exceeded, the
. operator must immediately notify Rad-Con Operations when his
'
ldosi.neter first indicates:
~
O.
>
50 mrem b.
> 100 mrem c.-
> 150 mrem d.
>'200 mrem
,
t
' QUESTION: 51 (1.00)
P Locked valve'MS-109, 21 AFW Pump Main Steam Supply was closed and tcgged for repairs on 21 AFW' pump.
When repairs were completed, MS-109'was opened and locked by a licensed operator.
Docs another-r licensed operator have to verify the condition of MS-109?
,
cf.
Yes, because the second. verifier of restored locked valves must'be a licensed operator, b..
>Yes, because two licensed operators are required to verify the position of restored locked valves, c.
No, because only one licens7d operator'is required to
. participate in the verification process for locked valves, d..
No, because any person qualified to operate this valve may perform the second verification.
-!
!
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PLANT SYSTEMS (51%) AND PLANT-WIDE-GENERIC-Page'43l-w RESPONSIBILITIES (13%)-
l;
.
'
. QUESTION:-52 (l'. 00 )
.
) Unit 2 is operating at 70 percent power during a power ascension L
.to 100 percent.
What indication should be used as the PRIMARY Lindication-of-reactor power?'
a,
, Wide range logarithmic power channels.
I e
b.
Power. range' Safety channels o c.:
.RPS. delta-T power channels.
d.;
Secondary cLlac imetric power (plant computer)
.\\i QUESTION: 53 (1.00)
- Which one of'the following normal evolutions requires that the operator have the appropriate procedure PRESENT.
-a.
Shifting charging. pumps b.
Commencing blended makeup to the VCT c.-
Shifting component cooling heat exchangers d.
Stopping a circulating water pump-s
.t
-
' QUESTION: 54-(2.00)
Ia'accordance with CCI-112J, Safety Tagging, list FOUR conditions under whichtindependent verification.of a restored valve may be waived. assuming-proper authorj aation is received.
'(0.5 each)
(*****
CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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.PLANTLSYSTEMS (51%) AND= PLANT-WIDE GENERIC
.Page 44-
.
RESPONSIBILITIESL-(13%)
.
,
k
,
. QUESTION: 55 (1. 00) -
,
- When an alarm annunciator is removed from service, a
- , ticker _is;placed on the alarm annunciator window.
a.
blue
.!
-I
'b.1 fyellow-c.
' white ad. --
red i
s
QUESTION: 56 (1.00)
- There is only one entry condition for EOP-8 (Functional Recovery l
Procedure) that allows exiting EOP-8 before EOP-8 is completed.
I Which one of the following conditions for entering EOP-8 allows an-exit before EOP-8 is completed?
a..
EOP-6 (SG' Tube Rupture) has been implemented,.but the shift supervisor (SS) wants to check the EOP-8 guidance on RCS Pressure and' Inventory Control.
-l b.
EOP-6 (SGTR) has been. implemented,. but the SS 'deterraines the
' acceptance criteria for 30S Pressure. and Inventory Control are not-being met, c.
EOP-0 (Post-Trip Immediate Actions) has been completed, but
~the SS-can't determine whether the casualty is a LOCA or a SG, tube rupture.
,
[
d.
EOP-0.(Post-Trip Immediate Actions) has been completed, but the SS considers he:has a coincidental LOCA and SG tube rupture..
(***** END OF CATEGORY 3 *****)
(********** END OF EXAMINATION **********)
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Page': 4 51 Wi!"
! EMERGENCY-AND! ABNORMAL 1 PLANT EVOLUTIONSr
'
'
"-
+
y
._ ( 3 6 % ) 2
,-
1*
'
"1 ANSWER:.
.(3,00)
a..
(1) 'Rx delta-T (Thot-Tcold)
(2)
10 to 50 degrees F b.
'(1) - CET temperatures (2)
Consistent with Thot c..
(1)
Steaming rate.
(2)
Affects RCS temperature-(0.5 each part)
' REFERENCE : -
EOP-7 000055A202
..(KA's)
' ANSWER:
(1.00)
b.
REFERENCE:
EOP-2 3.0/3.4
.
'000056A249
.. ( KA.' s )
-
_
ANSWER:-
(1.00).
a..
REFERENCE:
~ LOR-202-7C-89
- 2.9/3.0 000026A107
..(KA's)
I (*****
CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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} (36%)}
P g3 -- 4 6 :
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ANSWER:.
04:
(1.00)-
d
_l REFERENCE:
, SRO-2 01-2 -0 --
4.4/4.7
000056K302
..(KA_'s)
,
.
ANSWER:
-05 (1.50)
,(c);
10.
(0.5 each blank)-
-L (b)
bearing.(guide or thrust)
_;
-
(c)'
,(lower) seal cavity / controlled bleedoff.
'
t-
' REFERENCE:
AOP-7C-p. 5,-OI-1A p.,13,
.R31ated K/As 000015A120 000015A122 000015A123
-_3.1/ 2 ; 9, 2._7/2.7, 4. 0/ 4 '. 2, 3.1/3.2 000015A106
..(KA's)
!
- ANSWER
-06 (1.00)
.
'
c..
.t 11EFERENCE:
'1AOP9A; LOR-202-9A-89 g 4.'2/4. 5 00'0068 K318
..(KA's)
m-(*****
CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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- EMERGENCY; AND' ABNORMAlf PIANT EVOLUTIONS!dtiie w-S 9 Pago 47.-i; r
.s..
..
f ' p, (36%)
'-
,
'
!
. ANSWER:
07-(2.00)
(1). -101AT_
(O.50 EACH)-
.(2)
101BT
'(3)
104R1 (4)
114R-
' REFERENCE:
! LOR-202-7I-89 p. 22-3.3/4.0
- 000067A216
..(KA's)
'
-- ANSWER:
(1.50)
(1) -Penetration Room Exhaust Air Filter Train
.(2)
Containment Iodine-Filters (0.5 each).
- (3)
Containment Coolers REFERENCE:
-AOP-6D 3.7/3.8
,
LOOOO36G005-
..(KA's)
ANSWER:
(2.00)
'* ANSWER-(a)-
200 (0.5 each)
'
(b);.Open CVC-514 (BA Direct Makeup Valve)
(c). Start a BA pump (d) : Start all available charging pumps REFERENCE:.
- REFERENCE EOP-O '
3.4/3.6 000005G010
..(KA's)
(*****
CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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EMER'GENCY'AND AENORMAL PLANT EVOLUTIONS-
-Pagf48t
!
- ##
'
(36%)-
,e
.
I
,
5
.
.
,
.
- 10 "
(1.00$
-ANSWER:.
'
'
'd.
,
.
,
REFERENCE:
RO-202-7G-2.p. 9
.
s 2.6/2.9 y
,
'l
,
,
000051G011-
-..(KA's)'.
'
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ANSWER:
1.00)
.
C. :.
-
REFERENCE:-
.
.
E
' Tech Spec-3.4.8:3 asis 2.9/3~6
.
' 000076K305
...(KA's)
' ANSWER:
(1.00)
d.-
-
'
. REFERENCE:
>
l SRO-301-4-0:
4f. 5/ 4. 7 -
,
000040K304
..(KA's)
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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'
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D Page.49 4:
.(36%)/
.
t L_ ANSWER:
13-(1.00)
a.
.
-REFERENCE:
.g
'01-34,_ Sect:VI,.'VIII 3'.7/4.0'
,
.a-000057A204-
..(KA's)
o
- ANSWER:'
(1.00).
C '.
REFERENCE:
'
'
- LP-RO-6 0-1-2,. LO -.2. 01 -
..LP-RO-60-1-2, p.28-30 SD-60, p. 28
'
<
'3.'7/3.9
.
-000003A201
..(KA's)
-
.
' ANSWER:
- 15
'(1.00)
,
! Green ((Safe-Reset) light'is off
,
J.'
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--Pagei50f L'"
EMERGENCY AND1 ABNORMAL PLANT EVOLUTIONS:
o
-
-q;
- (36%)1
,
.,
REFERENCE:.
i
.LP-RO-122-1-2, p.
-LP-RO-122-1-2, LO'2.6-c341/3.5-000061A204
..(KA's)
.
ANSWER:-
16-(1.00).
b.
,
iREFERENCE:
OI-12A, p.:4
>
~LP-RO-103-1-0,fp. 28, 29 o
LP-RO-103-1-0,iLO13.5 LER 84- 03-4'.~4/4.6 000054K304-
..(KA's)-
,
- r
-
. ANSWER:
-( 1. 0 0 )
'
-a.
l REFERENCE:-
SD-62.
>
'TX - None'available
'
3.5/3.8-y
,\\
'000009A202-.
..(KAis)
'
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.
<
(*****
CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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p*) M EMERGENCE AND ABNORMAL' PLANT' EVOLUTIONS- -
=Page 51:
,;(36%)?
'
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!
i' ANSWER:'
L18 (1.00)'
A -~ d.,
.N i
iREFERENCE:.-
(EOP-0, p.'4
'
.
.LO - None available
'
.4.2/4.3-
-
000029K311
..'(KA's)
t; ANSWER:
(1.00)
-\\
'
d.
REFERENCE:
~LP-LOR-201-5-88, LOL2.3
'
LEOP-5, p.
-3.6/4.2-
'000009A234
..'(KA's)
. ANSWER:
'2 0,
'(1.50)
'
l '.
Open feeder breaker to'12A 480v bus (0,5)
2.
Open' feeder breaker to 13A 480v bus (0.5)
,3.,
Open: tie-breakers to 12A and 13A 480v buses (0.5)
L
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- EMERGENCY ANDiABNORMAL: PLANT EVOLUTIONS +-
-
- " ' -
?
h i, (36%)(..
'
.
'
- REFERENCE:
- x
_,'
EOP-0,-p. 4
.
'
' aLO:- None available
' 4 ~. 2/4 ~.1
. 000007G010
..(KA's)-
.
.
1-ANSWER:L-
'21 (2.00)
(1)-
T-cold
- (2): Pressurizer pressure
,
(3):RCS flow rate
-
(4)
-ASI~
(0.5 each)
'
-REFERENCE:'
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RESPONSIBILITIES,(13%)
I a-n c-C REFERENCE:
SD-63, p. 101 LO - None available.
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(1.00)
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REFERENCE:
LP-RO-07-1-1, p.
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High Pressurizer Pressure High Containment Pressure.
(any order; 0.5 each)
CREFERENCE:
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RO-59-1-4 App D 3.2/3.5 012000K406
..(KA's)
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(1.00)
d.
REFERENCE:
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CCI-300J, p. 10.
LO - None 4.vailable 3.6/3.7
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Pago 73
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REFERENCE:
CCI-112J, p. 15 LO - None available R31ated K/As-194001K109 3.5/3.4, 3.4/3.4 194001K108
..(KA's)
ANSWER:
(1.00)
2.
REFERENCE:
CCI-305B,-p. 2 LO - None available 3.1/3.4 194001K105
..(KA's)
ANSWER:
(1.00)
a.
REFERENCE:-
.LO - Nono available 2.8/3.4 194001K103
..(KA's)
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(1.00)
b.
o-REFERENCE:
I CCI-307D, p. 3 LO - None available
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REFERENCE:
CCI-800C, p.-33 LO - None available 3.3 194001K104
..(KA's)
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ANSWER:
(1.00)
a.
REFERENCE:
CCI-309B, p. 5 LO None available 3.6 194001K101
..(KA's)
ANSWER:
(1.00)
'
.c.
REFERENCE:
GSNO SI 88-6 LO - None available 4.3/4.1 194001A113
..(KA's)
ANSWER:.
(1.00)
d.
(*****
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REFERENCE:
LO - None available GSNO SI 85-1, p. 3 l
4.1/3.9
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ANSWER:
(2.00)
1.
Emergency conditions exist.
2.
Entry into High radiation area is requir9d.
3.
-An operational test is used to verify operability and the component is not a locked valve.
4.
Component is not safety-related.
5.-
Component does not affect plant reliability.
6.
Hazardcus area entry is required.
(any 4 0 0.50 each)
,
- REFERENCE:
CCI-112J, Safety Tagging, p.
LO - None available i
194001K101
..(KA's)
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(1.00)
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REFERENCE:
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CCI-306C, p. 2
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3.7/4.1
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(********** END OF EXAMINATION **********)
__
_____-.__ _ -.-__ _ _ _ - _ _ - _
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ATTACHMENT 2-WR11IEN CXAMINATION AND ANSWER KEY (SRO)
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NUCLEAR RE2ULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION r
'
REGION
FACILITY:
Calvert Clific 1 &2
,,
REACTOR TYPE:
PWR-CE
.
l DATE ADMINSTERED:
90/05/07
!
-CANDIDATE:
,
INSTRUCTIONS TO CANDIDATE:
!
' Points for each question are. indicated in parentheses after the-question.
The passing grade requires at least 80% correct overall. -Examination prpers will be picked up four anskunaa ham (4 W) hours after tho
.cxamination starts.
,
,
i
' CATEGORY
% OF NUMBER VALUE TOTAL CORRECT CATEGORY
,
43.00 43.00 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (43%)
t 57.00-57.00 l
PLANT SYSTEMS (40%) AND PLANT-WIDE GENERIC i
RESPONSIBILITIES (17%)-
'100400
,
OVERALL
%
CORRECT OVERALL All work done on this examination is my own.
I have neither given
,
nor received aid.
Candidate's Signature
'
i 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 cnd 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 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 candidate at a time may leave..You must avoid all contacts with anyone outside the examination 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.
6.
Fill in the date on the cover sheet of the examination (if necessary).
7. You may writo your answers on the examination question page or on a separate sheet of paper.
USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON
.THE BACK SIDE OF THE PAGE.
8.'If you write your answers on the examination question page and you need more space to answer a specific question, use a separate shoot of the paper provided and insert it directly after the specific question.
DO NOT
. WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
9.. Print your name in the upper right-hand corner of the first page of each section of your answer sheets whether you use the examination question pages or separate sheets of paper.
Initial each page.
10. 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.
'11.-If you are using separate sheets, number each answer as to category and number (i.e. Plant Systems # 04, EPE # 10) and skip at least 3 lines between answers to allow space for grading.
12'.= Write "End of Category
" at the end of your answers to a category.
13.-Start each category on a new page.
.
14. Write "Last Page" on the last answer sheet.
15. Use abbreviations only if they are commonly used in facility literat. ire.
Avoid using symbols such as < or > signs to avoid a rimple transposition error resulting in an incorrect answer.
Write it out.
16. The point value for each question is indicated in parentheses after the question.
The amount of blank space on an examination question page is NOT an' indication of the depth of answer required.
..
17. Show cll calculctions, mathods, or caeumptions unsd to obtain an answer.
18.. Partial credit may be given. -Therefore, ANSWER ALL PARTS OF THE QUESTION
,
AND DO NOT LEAVE ANY ANSWER BLANK.
NOTE: partial credit will NOT be given on multiple choice questions.
19.. 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 deducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answers.
20. If the intent of a question is unclear, ask questions of the examiner only.
21. When turning in your examination, assemble the completed examina. tion with examination questions, examination aids and answer sheets.
In addition, turn in all scrap paper.
2:2. To pass the examination, you must achieve an overall grade of 80% or greater.
23. There is a time limit of (4 1/2) hours for completion of the examination.
(or some other time if less than the full examination is taken.)
24. When you are done and have turned in your examination, leave the examin-ation area.as defined by the examiner.
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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v7 EMERGENCY AND, ABNORMAL PLANT EV2LUTIONS PCg3
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(43%)
i t
QUESTION: 01 (3.00)
- EOP-7l(Station Elackout) lists five criteria that are used to c;nfirm the existence of natural circulation (NC).
Each NC c:nfirming. criterion includes a plant parameter and a required c:ndition for that; parameter.
Two of the NC confirming criteria
'
cro the plant parameters Tcold and Thot, and the required c;ndition for each.is " Constant or decreasing."; Fill.in the f0llowing' blanks with the OTHER three NC confirming criteria-licted in EOP-7, including the parameter and the required condition for each.
(0.5 each part)
PARAMETER REQUIRED CONDITION a.
(1)
(2)
b.
(1)
(2)
c.
(1)
(2)
QUESTION: 02 (1.00)
Assume all systems have responded per design to a coincidental loss of the 500kV red and black buses with the plant at full rated power.
Which one of the following events can cause diesel
- generator overloading after the loss of off-site power?
a, Reactor trip
'
b.
SIAS actuation t
c.-
Loss of power from SMECO (Southern Maryland Flectrical Cooperative)
d.
Loss of power from DG 12 L
r
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I EMERGENCY'AND ABNORMAL PLANT EVCLUTIONS P go' S
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QUESTION: 03 (2.00)
FILL IN THE BLANKS
~If'the~ Unit 1 reactor trip breakers have fused shut and will NOT cpen on a trip, there are two immediate lines of defense to-pravent core damage being caused by a overpower accident that
'
Lre:ults intan anticipated transient without scram (ATWS).
(0.5 each blank)
i c '.'
The automatic line of defense against this ATWS is for.the
'
diverse scram system to deenergize the CEDMs by (1)
(how)
i
.wh n (2).
(what)
exceeds its setpoint.
,
b. The other line of defense against this ATWS is for the (3)
(what)
to deenergize the CEDMs by
(4)
(how)
.
(1)
(how)-
,
(2)
(what)
,
(3)
(what) __
,
' (4)..(how)
QUESTION: 04 (1.00)
'
IWhich one of the following explains why the MSIVs are required to bs, shut at the start of EOP-2 (Loss of Offsite Power)?
c.
Because main steam is not needed since the main turbine has tripped._
b..
Because the increased SG pressure in natural circulation increases the possibility of a steam line rupture.
c.
.Because the automatic operation of the turbine bypass valves can cause excessive cooldown.
d.
Because the possibility of condenser overpressure is increased.
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CATEGORY 5 CONTINUED ON NEXT PAGE *****)
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g-EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Pago
(43%)
. _ __
__
QUESTION: 05 (1.50)
FILL IN THE BLANKS In accordance-with AOP-7C (Loss of Component Cooling) if component cDaling water to the RCPs is lost and CANNOT be restored for (0)
minutes, the RCPs are required to be stopped.
Even bDfore this time elapses, however, if the temperatures on certain c;mponents of an RCP, specifically the motor (b)
cr the pump (c)
, exceed their trip limits, th:t pump must be stopped.
(0.5 each blank)
,
(c)
!
(b)
(c)
QUESTION: 06 (1.00)
Which one af the following is the reason the saltwater air compressers-(SWACs), which are not normally running, receive an l
Gutostar.t on a large-break loss of coolant accident (LOCA)7 c.
Because the SWACs are the only air compressors that receive cooling water after a SIAS.
b.
Because instrument air usage is significantly higher after a SIAS than during normal operations,
'
c.
Because service water to the plant and instrument air compressors is isolated on a SIAS.
'd.
Because the SWACe tie in downstream (inside) of IA-2080 (IA
,
containment isolation valve), which closes on CIS.
t S
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EMERCENCY AND ABNORMAL PLANT EVOLUTIONS Page
(43%)
. - -
. -
,
x QUESTION:.07 (1.00)
If the. saltwater valve handswitches are NOT manipulated during a large-bresk' loss of coolant accident, which one of the following describes the saltwater flow conditions through the COMPONENT COOLING heat exchangers during the accident?
a.
Full flow during SI injection phase; throttled flow during recirculation phase b.
No flow during SI injection phase; throttled flow during recirculation phase c
_ Throttled flow durin'g SI injection phase; full flow during recirculation phase d.
Throttled flow during SI injection phase: no flow during recirculation phase QUESTION: 08 (1.00)
If the saltwater valve handswitches are NOT manipulated during a large-break loss of coolant accident, which one of the following describes the saltwater flow conditions through the SERVICE WATER heat exchangers during the accident?
a.
Full flow during SI injection phase;t throttled flow during recirculation phase b.
No flow during SI injection phase; throttled flow during
,
recirculation phase
'c.
Throttled flow during SI injection phase; full flow during
' recirculation phase d.
Throttled flow during SI injection phase; no flow during recirculation phase
-
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,
. EMERGENCY AND ABNORMAL PLANT EVCLUTIONS Pcg3
(43%)
--
-QUESTION: 09 (1.00)
After RAS has occurred on a LOCA, EOP-5 (Loss of Coolant A';aident) directs the operator to throttle HPSI flow if HPSI pump cavitation.is occurring.
If throttling is not successful, the Alternate Action is to align containment spray to the HPSI pump cuction.
Which one of the following is the purpose of this Alternate Action?
,0.
To' increase the heat removal capacity of the HPSI water
-
,
going to the core.
b.
To increase the available NPSH at the suction of the HPSI
-
pump.
c.
To match the core cooldown rate to the containment building
'
depressurization rate.
d.
To match the injection rate to the containment sump drawdown rate.
QUESTION: 10 (1.00)
If the-11 saltwater pump ~1s started after the saltwater valves for tho-' service water heat exchangers have been overridden open per
- AOP-9A (Control Room Evacuation and Safe' Shutdown due to a Severe Control Room Fire), which one of the following explains why the 11 caltwater pump discharge valve must be throttled?
a.
To' prevent the possibility of runout on 11 saltwater pump.
'b.
To: prevent excessive cooldown of the service water system.
c.
To prevent long-term cavitation damage to 11 saltwater pump
~1mpeller, d.
To prevent excessive vibration of service water heat exchanger tubes.
,
,
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i-w
]
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Pr.gD
l (43%)
'
QUECTION:-11 (3.00)
FCr EACH of the below-listed valves, select ONE of the following cffects that' will result-from a rupture of the containment
~in:trument air header that occurs downstream (inside) of the c:ntainment instrument air control valve (IA-2085).
(0.5 each)
,
. Effects:
= fail open/ flow goes to maximum
'FC
= fail closed /f3ow is stopped FAI = fail as is/ flow cannot change DNF = does not fail / valve operation not immediately
,
affected
,
EFFECT VALVE (S)
,a. Containment instrument air control valve (IA-2085)
,
b.
Pressurizer' normal spray valves (RC-100 E/F)
c '. RCS loop charging control valves (CVC-518/519)
,
d. Auxiliary pressurizer spray valve (CVC-517)
e. RCP' constant bleedoff relief isolation valvo (CVC-507)
f.
Component cooling containment isolation valves (CC-3832/3833)
.
Y i
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EMERGENCY'AND ABNORMAL PLANT EVOLUTIONS P g610 L(43%)-
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QUESTION: 12 (1.00)
.!
If a fire requires deenergizing one of the Unit i vital 480vac
.bures (llA, 11B, 14 A OR 14B), the associated vital 480vac MCC may-be cross-tied to restore power from the counterpart 480Vac bus.
' List the FOUR'(4) Unit i vital 480vac MCCs (as designated in OI-L 27D, Station Power 480-volt System) that may be cross-tied to rectore power.
(0.25 each)
(1)
(2)-
i
!
(3)
l (4)
.
QUESTION: 13 (1.50)
,
p If a. fuel handling. incident in the containment building results in a oignificant release of activity to the containment building atmosphere, the containment radiation signal should actuate and th3 containment purge isolation valves should automatically close
'
(if not already closed).
List the THREE (3) other non-duplicate
'oyatems/ components listed in AOP-6D (Fuel Handling Incident) that
.chould be operated (if not already running) to reduce containment activity or prevent releasing this activity to the environment.
(0.5 each)
( l')
(2)
(3)'
r t
l l
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I E
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EMERGENCY AND ABNORMAL PLANT EVOLUTIONS PCga 11
!
l(43%)
l i-QUESTION: 14 (2.00)
!
Cn a reactor trip, if one CEA' fails to fully insert, EOP-0 (Post-Trip Immediate' Actions) requires the operator to borate
'
t L-(0)
ppm.
The THREE (3) steps the operator is directed to i
perform to initiate this boration are:
(0.5 each blank)
i L
'(b)
,
.(c)
and
,
(d)
.
,
-
.
'
QUESTION: 15 (1.00)
Th3 plant has been operating at full rated power for more than two w;sks.
While reviewing his panels, the reactor operator no*.es
'
thOt since his last review, the megawatt output meter has d creased by about 25 MW, while reactor power, Tref, and Tavg have remained constant.
Which one of the following is the most
'
likely cause of this unnoticed output power / reactor power
,
mismatch?
c.
A large load reduction on the grid.
.b.
A feed-excursion causing increased-SG levels, c..
A leaking SG code safety valve, s
!d.
An air leak in the main condenser.
,
l0
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EMERGENCY AND: ABNORMAL PLANT EVOLUTIONS P ga 12 f
(43%)
,
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QUESTION: 16 (1.00)
j a
,
If RCS specific activity exceeds the limits of Technical Specification 3.4.8, the required action is to go to Hot Standby
,
Cnd reduce Tavg to less than 500 degrees F.
Which one of the
'fGilowing is the reason Tavg must be reduced to less than 500 p
degrees F?-
C.
This temperature has a saturation pressure that-is below the i
- lift pressure of the main steam safeties.
b.
This temperature will contract small fuel defects and prevent further release of fission products to the RCS.
c.
Reducing RCS temperature will increase the efficiency of the CVCS letdown ion exchangers.
d._
Reducing RCS temperature will increase the adherency of the RCS corrosion film.and minimize any crud burst in progress.
,
$
$
QUESTION: 17 (1.00)
'For a steam line rupture inside containment, EOP-4 (Excess Steam D; mand) requires maintaining the unaffected steam generator (SG)
within 25' degrees F of core exit temperature while the affected SG 10 blowing down.
Which one of the following is the reason for maintaining this 25 degrees F differential'
.i c.
To maintain an adequate RCS subcooling margin.
'
b.
To establish natural circulation flow if RCPs must be
'
stopped.
c.
To prevent the plant cooldown rate from exceeding
100 degrees F/hr.
d.
To limit RCS heatup after affected SG blowdown is complete.
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- EMERGENCY AND ABNORMAL PLANT EVOLUTIONS P;gi 13-(43%)
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QUESTIOM
(1.00)
II power isl lost to 120vac vital instrument bus 11 (1YO1), ESFAS Cetuation cabinet ZA and ESFAS sensor cabinet ZD will be deenergized.
When power is restored to 120Vac vital instrument
bus 111 (1Y01), the operator must ensure verbatim compliance with the OI-34 (ESFA~LSystem) procedure to return these. cabinets to
.
operation.
Which one of the following is the proper sequence to i
be followed when returning these cabinets to operation?
- 0.
Sensor (ZD) cabinet before actuation (ZA) cabinet; bias power (15vdc) before actuation power (28vdc)
1 b.
' Sensor (ZD) cabinet before actuation (ZA) cabinet; actuation power (28vdc) before bias power (15vde)
.
c.
Actuation (ZA) cabinet before sensor.(ZD) cabinet; bias power
[
(15vde) before actuation power (28vde)
l d.
Actuation-(ZA) cabinet before sensor (ZD) cabinet; actuation i
power (28vde) before bias power (15vde)
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QUESTION: 19 (2.00)
During the natural circulation cooldown after a total loss of all fCedwater, in accordance with EOP-3 what are the TWO (2) separate plant conditions / component states the operator looks for to determine when to commence once-through core cooling?
l (1.0 each)
(1)
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(2),
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l QUESTION: 20 (1.00)
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I During a total loss of all feedwater, after one of the criteria fcr commencing once-through core cooling is met, EOP-3 requires l
this cooling to be initiated before core exit temperature reaches L
560 degrees F.
Which one of the following is the reason for this rcquirement?
'
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c.
To prevent bulk boiling in the hot channel area of the core.
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b..
To prevent, voiding in the head area that might impede natural
.
j circulation.
c.
To prevent reactor overheating due to insufficient HPSI pump flow.
l d.
To prevent flow instability due to low flow in the hot channel area of the core.
,
QUESTION: 21 (1.00)
A'cmall feedline break has occurred inside Unit 1 containment and hoc resulted in containment temperature increasing from 100
p d:grees'F to 160 degrees F.
Disregarding any effects from RCS or
'
containment pressure changes, what effect will this increase in containment temperature have on the pressurizer level indicated by LIC-110X/Y?
G.
Indicated level will be-higher than actual level because the reference leg fluid density decreases, b.
Indicated' level will be lower than actual level because the reference leg fluid expands and spills back into the pressurizer.
c.
Indicated level will be higher than actual level because the J
elevated containment temperature causes flashing in the reference leg.
d.
Indicated level will be lower than actual level because of l
the high temperature effects on the differential pressure if detector.
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EMERGENCY AND ABNORMAL PLANT EVOLUT20NS Page 15 (43%):
QUESTION:'22 (1.00)
While responding to an actuation of annunciator C-43 (MAIN STEAM EFFL RAD MONITOR), the CRO observes that 11 SG rad monitor (RIC-5421) is indicating below his shift-turnover grease mark.
What other indication should the CRO observe on RIC-5421 to confirm the
" keep-alive" source has failed in this rad monitor?
, QUESTION: 23 (1.00)
' Unit 2 is operating at 50 percent load during a load increase with 21 SGFP operating in automatic and 22 SGFP started and in standby.
al SGFP trips resulting in a ?ov S/G level reactor trip and
, turbine. trip.
Why does AOP-3G (calfunctions of MFW System)
require the operator to feed the S/Gs using the AFW system instead of using 22 SGFP?
a.'
To minimize the possibility of overfilling the S/Gs.
'
6.
To minimize the possibility of water hammer in the main feedwater system.
c.
To minimize the possibility of thermal shock to the S/G feed ring J-tubes.
d.
To ensure the most reliable source of feedwater is used to restore S/G level.
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- - - -. - - - - - - - - - -. - - -.. - - - -. ~. - - - - - - - - - - - - - = - - - - - - - - - - - -. -. - - - - - - - -. -. - - - - - -. - - - - - - - - - - - - - - - - - - - -
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EMERGENCY AND ABNORMAL PLANT EVOLUTIONS POg3: 16 q.
(43%)
s l
QUESTION: 24 (1.00)
,
Unit 1 was manually tripped from rated load because of a slow uncontrollable decrease in RCS pressure.
A SIAS automatically
!
initiated a short while ago and current indications are as f llows:
!
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RCS pressure - 1600 psia and decreasing CET - 537 degrees F Pressurizer level (LIC-110X) - 10 inches and decreasing Pressurizer level (LIC-110Y) - > 360 inches containment pressure - 1.5 psig Normal containment sump - high level alarm Quench tank level - 28 inches and stable Quench tank temperature - 100 degrees F and stable What failure could have caused the above events and indications?
c.-
A pressurizer reference. leg has ruptured.
,
b.
A pressurizer spray valve has failed open.
c.
A pressurizer PORV has failed open.
,
d.
A pressurizer heater well has ruptured.
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EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 17
'(43%)
s
' QUESTION: 25 (1.00)
Unit 2 is recovering from a LOCA in accordance with (EOP-5) Loss Of Coolant Accident, with current conditions as follows:
RCP status - OFF
,
RCS pressure - 1200 psia and decreasing Highest T-hot - 525 degrees F and stable Highest CET - 540 degrees F and stable RVLMS - 100 percent Pressurizer level - 108 inches and increasing 11 S/G level - (-)DS inches and increasing 12 S/G level - (-)50 inches and increasing Do plant conditions meet the criteria _for throttling HPSI flow in cccordance with step M.4 of EOP-5 (attached)?
c.
Yes, but only if at least one S/G has a steaming path.
b.
Yes, but only if pressurizer level continues to increase.
c.
No, because pressurizer level criteria is not satisfied.
.
d.
No, because subcooling criteria is not satisfied.
QUESTION: 26 (1.50)
Lict the alternate operator actions required by EOP-O (Post-Trip Immediate Actions) to insert the CEAs if an automatic and manual rcOctor trip fail to insert the CEAs.
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Pcg3116 of 41 l
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RECOVERY ACTIONS ALTERNATE ACTIONS ~
.-
- NOTE -
A break.on top of Pressurizer will result in an uncontrollable increase in pressurizer level-
.
until Pressurizer is solid.
,
4.
Maintain pr'essurizer level between 101 and 160 inches.
!
- CAUTION -
,
Do,not throttle BPSI flow unless
,
30 F subcooling can be
.
maintained _.
s'
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a.
IF the following
'
.
conditions can be maintained:
'
(1) At least 30 F.
subcooling.
(2) Pressuriser level greater than 101-
'
inches.
(3) At least one S/G available for heat removal.
!
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(4) RVLMS indicates that the Core is covered.
P THEN throttle HPSI flow or operate Charging Pumps
L
'as necessary to maintain
.,
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pressurizer level between
.
101 and 160' inches.
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- EMERGENCY AND ABNORMAL PLANT' EVOLUTIONS P;g] 18
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l-E QUESTION: 27-(2.00)
'Lict the FOUR (4) plant parameters that are monitored to ensure-tha Technical Specification requirements for DNB are being met.
l
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L (0.5 each)
!
(1)
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(2)
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(3)
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(4)
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' QUESTION: 28 (1.00)
Unit-2 has experienced a tube rupture in 21 S/G and a loss of offsite power.
An RCS~cooldown is in progress by. steaming 22 S/G
- to atmosphere.. During the cooldown the CRO observes that loop 21 T-hot / is 500 degrees: F and loop 21 T-cold is 525 degrees F.
The CRO should:
G.
Continue the RCS'cooldown because the temperature indications are expected.
'
'
b.-
Continue the RCS cooldown expecting to see loop 21 T-cold decrease and T-hot increase.
c.
Stop the RCS cooldown until normal natural circulation is established in loop 22.
d.'
Stop the RCS cooldown because the wrong S/G is being steamed.
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i EMERGENCY AND ABNORMAL PLANT EVOLUTIONE PCg3 19-(43%)
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QUESTION: 29-(2.50)
Lict FIVE (5) non-duplicate process fluid radiation monitors in g-tha control room that could show an increase in the event of a 100 gpm tube leak in '11 S/G.
(0.5 each)
.
,
V i
(1)
rr
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-(2)
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'(3)
__
.(4)
(5)
,
i-QUESTION:.30 (1.00)
'
Unit 2 is on shutdown cooling with 21 LPSI pump running and.the rotetor vessel head removed.
The RCS is at 140 degress F when 21 LPSI pump trips.
Prior to starting the other LPSI pump, the
'
CRO must:
c.
close.the SDC flow control valve, SI-306-CV.
b.
determine cause of LPSI pump trip.
,
c.-
reset and restart the tripped LPSI pump.
d.
open the SDC temperature control valve, SI-657-CV.
,
QUESTION: 31 (1.00)
Whnt is the purpose of realigning HPSI flow for pressurizer injection after a large-break LOCA occurs?
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-(43%);
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. QUESTION:,3 2 '
(1.00)
.
The 11 reactor coolant' waste monitor tank is being released via
-
Unit'1'with'all circulating water pumps operating.
Which'one of the following occurrences could result in an EFFLUENT HIGH
- RADIATION' alarm and automatic termination of the release?
Inadequate. flushing of the radiation monitor' detector after a..
the last discharge'.
b.
stopping one-Unit 3-circulating water pump during release.
,
c.
Adjusti'.y the setpoint of effluent radiation monitor, RE-2201, to'twice the value listed in the discharge j:ermit.
- -
.
d.
Throttling effluent flow rate to one-half of-the value listed
+
in the: discharge permit, L
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PIANT7 SYSTEMS (40%) AND PIANT-WIDE' GENERIC Paga:21
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. QUESTION: 01 (1. 00 )'
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.0I-16 (Component Cooling System)Section III,-Shifting _ Operating-PuTps,_contains the,following Note:
"Two component cooling water pumps should not,be run for
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extended, periods with only one CC HX in service."
[
xWhich'one'of the:following is the reason for this-Note?'
'
n d.
Minimize possibility of accelerated tube erosion in on-
-
-service CCW heat exchanger.
a
)b/
Minimize possibility'of one pump being at shutoff head if pump discharge pressures are not equal.
!
Lc.
Provide greater reliability since technical specification
13.7.3.1 requires both CCW loops to be operable.
.
.
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jl d.
Minimize possibility of pump with higher discharge pressure-reaching near-runout conditions.
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- -
QUESTION:. _0 2 (1.00)_
,j Which one of.the following describes the-proper sequence for.
!
oporating:the>CCW h' eat-exchanger outlet valves (CCW or SW) when l
Schif ting ? from' 11 ;CCW heat exchanger in. service. to 12 CCW heut
-
cxchanger in' service?-
j na.
Open 12 CCW outlet; open.12 SW outlet; shut 11 SW outlet;
-shut'11 CCW outlet.
b.-
Open 12 CCW outlet; shut 11 SW outlet;'open 12 SW outlet; shut 11 CCW outlet.
j c.
Open 12'GW outlet;.open 12 CCW outlet; shut'11 CCW outlet; shut 11 SW outlet.
'
4:.d; Open 12 SW outlet; shut 11 CCW outlet; open 12 CCW outlet;
-j
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shut.11 SW outlet.
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Page 22'
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' RESPONSIBILITIES (17%)L lL
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-QUESTION: 03'
(1.50)
MATCHING.
Forfeach' circulating ~ water system component listed in Column A,
.
lcolect its primary purpose from Column B.
(0.5 each)
' Note:
1 Select ONLY ONE purpose from Column B for each' component in Column A..
COLUMN A COLUMN B-
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a.-Dewatering pump.
(1) Removes debris from fish collection facility
,
b; Baffle wall (2) Removes' water from isolated CW inlet bay c.uTrash rake.
(3) Separates adjoining CW inlet bays-(4) Removes CW pump packing gland leakoff (5) Removes debris from traveling screens (6)-Prevents intake of bay surface water (7) Removes debris from trash racks 3.
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(e g PLANT: SYSTEMS: (40%) L AND PLANT-WIDE GENERIC
'P;go.23-
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- QUESTION
- 04,
. (2 ; 00)-
!
, MATCHING lli.
F3r;each. tyre'of; radiation monitor listed in Column A, select the
'. type of radiation ~ detector from Column B that is used at Calvert
.
- Cliffs in that type of monitor.
(0.5 each)
a ma
.
'N;te:
Choose ONLY ONE' detector type from Column B for.each (
grcdiation monitor type in Column ~A;-however, some detector types-
'
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' mty not: be.used at all and some-detector types may be used in more tthan one tit 4 cf monitor.
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'l COLUMN -
COLUMN B
.
I a '. Air particle process monitors (1) Geiger-Mueller detector b. Gaseous process monitors (2) Proportional detector
!
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c.
Liquid process monitors (3) Fission chamber
]
.
d. Normal (low-range) area monitors (4) Scintillation detector.
'
o Il EQUESTION :. ' 05-(1. 0 0 )
,
!
IfJaL4kV breaker is automatically tripped due to actuation of the Lassociatedelockout relay,-which one of the following actions must g
--ba: taken to prepare the breaker for closing af ter the' cause of the Etrip.'is. corrected?
"
a.
-Turn the breaker control-switch on the main control board to
,
the: TRIP position.
f 0b. -
Locally move the breaker handle from the trip-free position
- to the tripped p.osition, b. %'
,
o c..
Locally depress the trip button on the breaker front panel.
,
d.
Locally' reset the lockout relay on the breaker front panel.
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PLANT SYSTEMS (40%):AND PLANT-WIDE GENERIC Page.24; RESPONSIBILITIES (17%)
' QUESTION: 06.
.( 1. 00 )
g
" Choose the' combination _ bel'ow which properly states the-method-of-
,oparatinglthe_.4kV disconnect switches for the following pumps:' 13 Lacrvice water pump; 13 HPSI pump; and:23 saltwater pump.
"[ '
13 SRWP:
13 HPSI 23 SWP-a._
' Electrically Manually Manually, b.-
. Manually Electrically Manually 1:.
Electrically.
Manually Electrically d..
Manually Electrically Electrically o-QUESTION: 07'
.(1.00)
-Which-one of the following is the reactor power signal =used by the Metrascope (Qmet)?
a.
The maximum Qpower b.
The average Qpower c.,
- The average linear range NI power
'ch Thermal' power (PA912)
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RESPONSIBILITIES - (17 %) :
p.
IQUESTION'108 (1100)-
Which one of'the following will cause the 12 LPSI-PUMP SIAS
. BLOCKED AUTO START L annunciator to actuate' ONLY AFTER a pump start
'
+oignal is initiated?
,
' a.:
' Pump handswitch in pull-to-lock b.
Pump breaker _ closing spring broken-c..
. Pump control transfer switch in local d.
Pump breaker racked out
,
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-QUESTION: _09 (2.00)
'
Provide:the nominal setpoints_at which the pressure signal from PT-103-l' (low-range pressurizer pressure transmitter)
l generates an. actuation / enabling signal in the following valve
>
! control circuits.
(0.5 each)
,
.psik Ea. Open SI-G34/644 (icolation valves.for safety
<
. injection tanks)
g 2 psia: b.; Shut SI-652-(shutdown cooling' return valve)
-
psia c.LEnable MPT protection on Unit 1 psia d.
Enable MPT protection on Unit 2 m
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PLANTc SYSTEMS (40%) AND(PLANT-WIDE GENERIC-Page 26'
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- QUESTION: 101 (1.00)
'Which'one of the following correctly states the RCS temperature
. i inputs used. in the - thermal margin / low pressure - (TM/LP) calculator to calculate delta-T power for use in the variable overpower trip
-
unit?
'
'G '.
Auctioneered high.Thot and averaged Tcold
,.b.
Auctioneered high Thot and auctioneered low Tcold c.
Averaged Thot and auctioneered low Tcold
!d.
_ Averaged Thot and.auctioneered high Tcold QUESTION: 11 (1.00)
Technical' Specifications (Mode.6) require a mininum level of borated water be maintained above the top of irradiated fuel
- assemblies seated in the. reactor vessel during movement of CEAs.
'Which-one of the_following identifies the Technical Specifications basis for'thefrequired minimum level?
a.:
iShutdown: margin considerations for inadvertent CEA movement
- b.-
Heat removal considerations for, irradiated fuel assemblies LIod'ine removal considerations for a ruptured fuel assembly c.
.d.
Personnel shielding considerations for' irradiated fuel'
'
assemblies
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?b RESPONSIBILITIES
3-i
QUESTION:.12-(1.00)
'
LIf Reactor Regulating System (RRS) channel X.is initially _
colected,-which1 one'of the following correctly states the ninimum.
-
- octions-that must be taken to obtain an accurate T-average signal
- after:a coincident failure of the-in-use RTDs in the loop 1 hot-
. leg.andiloop 1 cold leg.
'
a.
. Shift from RRS channel X to RRS channel Y.
b.'
Select-RRS channel Y and shift selector switch'HS-111 3n the
' bottom section of 1CO6.
c.
Select OFF on the loop _1 selector switch for RRS channel X, d =. -
Shift selector switch HS-111 in the bottom section of 1CO6.
QUESTION:-13:
(1.50)-
In addition to the two steam generator low level trips, what are-iTHREE (3) other RPS trips that_CANNOT be bypassed, either automatically or manually?
(0.5 each)
(1)'
t(2)
Si -(3)
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LQUESTION: 14"
' ( 2. 00)'.
-
- -Assume.that-the 4kV emergency diesel generator (EDG). disconnect switches are. lined-up normally for at-power operations.with all
For each of the following situations, fill in the
's associated blanks with the following information, f(1).Which,fif any, 4kV EDGs will-automatically start..
Which, if any, 4kV EDGs will be automatically connected.
(2). -to a bus (i.e.,_an EDG feeder breaker will close).
.
-
Situations: (Assume each situation occurs separately.)
- a.-
4kV bus 14 (only) suffers loss of voltage (no lockout).
. b.-
4kV buses 1-4 and 24 suffer loss of voltage (no lockout).
c '.
4kV bus 11.(only) suffers loss of voltage (no lockout).
d.
A loss of voltage (no lockout) occurs on 4kV buses 11 and 21 coincident with a design-basis LOCA on Unit'2 (only).
(1) l EDGs THAT START-(2) EDGs. AUTOMATICALLY CONNECTED i.4-sa.
_
b.-
'C.
-
d.
,
Note: -Your answer should be either specific'EDG numbers or ALL or
>
- NONE.
(0.25 each blank)
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cQUESTION: 15-(1.00)
Un'it'l'isLin Cold Shutdown and 12A RCP is about to be started.
i Which-of the following conditions ensures an interlock:is sGtisfied that enables 12A--RCP to start when its control switch is Lplaced-in'the START position?
"
~ a.-
12A RCP o lil ft pump must have operated for-60 seconds.
i i
- b..
All"RCS: cold leg temperatures must be > 275 degrees F.
.
c.-
. The " COMPONENT COOLING FLOW LO" alarm is clear.
d.
Thel" OIL RSVR LEVEL LO" alarm is clear.
QUESTION: 16 (1.00)
Unit 2 is L in the process of CEA insertion during a reactor-shutdowniwhen the " SHUTDOWN GROUP INSERTION PERMISSIVE" alarm is received..This alarm first acLuates when:
ca '
- One CEALregulating group is inserted below 10 inches.
.
ns-b.
- All-CEA regulating groups are inserted below.10 inches.
c '. -
One:CEAl shutdown group-is inserted below 129 inches.
E d.-
JAllLCEA shutdown groups are inserted below'129 inches.
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o QUESTION: 17 ( 1. 00 ).
Wh:t is the purpose of the handwheel on liquid waste discharge
'icolation valve, MWS-2201-CV?
-c.
Allows the operator to manually open the valve to commence a
,
liquid radwaste discharge if control air is lost.
'
b.
Allows'the operator to manually close the valve in the event of high effluent radioactivity and a failure of automatic
,,
valve closure, c.
. Allows the operator to manually open the valve following an automatic valve closure to flush the radiation monitor and I
discharge header.
ad.
Allows the-operator to manually close the valve as necessary to throttle the effluent flow rate below the value entered in the discharge permit.
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. QUESTION: 18 (1.00)
.
Tha waste gas compressors are operating normally-when the lead
compressor fails to cycle off as waste gas surge tank pressure
.dtcreases.
How will the waste gas surge. tank be protected from excessive vacuum?-
a, A. tank relief valve will open to the atmosphere.
b.
A rupture disk on the surge tank will rupture.
c.
An isolation valve in the compressor. suction line will close.
d.,
A nitrogen supply valve on the surge tank will open.
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PLANT! SYSTEMS:-(40%) AND: PLANT-WIDE-GENERIC-
=Page.31 JRESPONSIBILITIES;(17%)
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'. QUESTION: 19'
(1.00)
What is-the sasis.for the' Technical' Specification limit on oxygen
- content ir< tre waste gas' decay tanks?
'a.-
Minimize the possibility _of corrosion in the tanks.
b..
LMinimize the possibility of an explosive gas mixture in the tanks.
c.-
Minimize the amount of radioactive-oxygen released to the
~
atmosphere.
d.
' Minimize the amount >of non-radioactive gases contained in the tanks.
QUESTION: 20 (1.00)
A waste gas decay tank'is-being released through the Unit 1 vent whenia. waste. gas discharge. radiation monitor.(RI-2191)= alarm is received. LAssuming all automatic actions occur as-expected, what
,
' valve must_ be manually shut to prevent subsequent waste gas c ecay ctank; discharge to the waste gas surge tank?
a.-
Waste gas discharge isolation valve - WGS-2191-CV-
-
' b. :
Waste gas discharge isolation valve'- WGS-2192-CV c.
Waste gasidischarge pressure control valve - WGS-2191-PCV d.
Waste gas discharge pressure control valve and filter
- bypass:- WGS-630
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1,iQUESTION: 21
/ (1. 0 0)'
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Un'iti101s operat ing at rated ol'oad when an inadvertent actuation of '
.
em Leichannel'B AFAS1 start signal' occurs and seals in.
Which'AFW
fu ' purp(s)l, 'if: any," will; automatically and immediately ' start?
q
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- One' turbine-driven-AFW pump only
,
b.-
AFW pump 13:only-o P :c.
ione'~ turbine-driven AFW pump and AFW pump 13 ga l
d-None, untilLat least 18 seconds has elapsed
.
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' QUESTION: 22 (1.00)0
[.[ALretctor trip.has: occurred on Unit 2 and AFW pumps 21 and'23'are-op rating and feeding both steam generators whenta loss of l
l: instrument c air pressure occurs. - Assuming. no operator actions are'
!
taken,wAFW flow: rate to the steam generators will initially:
! a '.
increase','because-the 21 AFW pump turbine will increase
_
,
'
speed.
- b.
Iincrease,'because all AFW1 flow control valves associated'with I
AFW pump-23'will failuopen.
,
c.
. decrease, because the 21 AFW pump turbine will decrease a
speed.
,
,-
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t
'd. : ' decrease' because all AFW flow control valves associated w3tn
,1
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L AFW pump 23 will fail closed.
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- QUESTION: - 23
- (1. 00) =
-
. Unit 2 is operating;at 60: percent load withLa hot leg temperature
.
- ofi.590 degrees F.
?What willibe the approximate reading on average J lcoretexit-thermocouple" temperature indication?
.
La.
566 degrees F=
b.
- 578 degrees F-c..
602' degrees F d..
614 degrees F
<
QUESTION: '24 (1.00)-
'1Ifg ai large fire requires all: Unit 2 vital instrument buses to be Ldoenergized, what electrical system design feature allows Unit 2-nuclear power:tos be monitored at 2C43 (Aux Shutdown Panel)?
.
LQUESTION: 25 (1.00):
D'uring aLUnit 2' load increase from-50 percent to 100 percer.t, a
" NUCLEAR INSTRUMENT-CHANNEL INOPERATIVE" alarm is received.
Which of(the following" failures-could have caused this alarm?-
~
a '.
Powerfrange safety channel A power summer output fails'high.
b '. :
Powercrange-safety channel-B upper detector output-fails low.
g c.
PowerJrange' safety channel C control power-fuse blows.
d.
Power range safety-channel D h:gh voltage power supply. falls low.
,
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i QUESTION:'26 (1.00)
Unit 2.is shutdown following a small LOCA.
It is determined that
'
reactor vessel venting is required to collapse a void'in the:
k evossel. head.'
When reactor vessel vent valves, RC-103-SV and RC-
, 1104-SV are' opened,-the discharge will be directed to the:
-
e.
J.4 a.-
Containment ll
.
f
- b.
. Quench-tank
- c. -
Reactor coolant drain tank'
d..
Volume control tank
,
IQUESTION: 27 (1.00)-
$What parameter [is measured to automatically activate a CVCIS if.a
^ letdown line rupture: occurs outside containment.
-
-Temperature
,a.
'
L b. -
Pressure c.
Fl'ow ' rate -
d.
Sump level; g;
E l' k_
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e I4 ! QUESTION:j28 (1. 00) :
'
ATUnit11 is' operating'at'90 percent power when'a, liquid waste icvCporator is placed in service resulting in a 20 degree F
'
increase in CCW system temperature.
Assuming no. automatic actions
!
- occur-in the CVCS, and no operator. actions, how'will;the reactor _
b3-affected?-
'
y'G.;
Reactorlpower will; initially decrease because the CVCS' ion
!
-
.exchangers_are releasing boron into the letdown flow.
" I b.'
ReactorLpower will initially. increase because.the CVCS ion S
'
exchangers are absorbing boron from the letdown flow.-
.t i
- c.)
Reactor power will initially decrease because T-ave is being increased by hotter CVCSxcharging flow.
- i
.,
>> l
-
i d.'
- Reactor' power will-initially increase because T-ave is being.
. decreased.by hotter CVCS ' charging flow.
+
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T L UESTION::29
.(1.00)
!
$
Q L
i,
~ Unit Ifisiin the recirculation phase following.a LOCA with. current.
<
T* Lconditions as follows:
- RCS pressure i 200 psia
+
f.
rPressurizer-level - 0,. percent (:
'RWT 1evel'--25 inches'
,
JContainment pressure 1 psig
"i In order..toLstart;the LPSI pumps with the above conditions, the
.
.,
- CRO must:
-
a.
match the control switch to the actual-pump condition and
- then. start lthe pump.
.b.-
reset'the RAS at 1C10 or the RAS logic module.
hb (c.
' override the RAS for'the.LPSI pumps.
Ld.
'stop the HPSI pumps until after the LPSI pumps are running.
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"RESPONSICILITIES (17%).
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QUESTION:. 30.
(1.00)
[ Unit 1-isfoperating at 100 percent power'when a shutdown group.CEA.
>
' drops into the coreL(fully; inserted).
The reactor does not. trip:
l
.
>cnd;no operator actions are taken.
How will shutdown margin-(SDM)-
i E-b3 affected'
i
s...SDM"will increase.
's
~
'
- t Eb.
SDM:will decrease.
E c.:
SDM will remain'th'e same.
i d. -;
The change in~SDM cannot be determined unless more information=is.given.
.
..
i
- QUESTION: 31 (1.00)-
,
'Whati is the reason for LIMITING the number of RCP starts in a -
,
- given; period?.
a-
. Minimize 5 pitting of starter contacts, b.
- Prevents'excessivettorsional' stresses on motor shaft.
.c
..
I ic.. EPreventsLoverheating'of motor windings.
l (.d..
' Minimizes axial stresses on motor bearings, a
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,.m QUESTION: 32
'( 1. 0 0 ).
,
l Prior to initiating withdrawal of fuel assemblies from the' reactor'
(vcesel, at least-channel (s)1of audible source range.
! indication and-channel (s) of visual source-range
'
l indication-must be: operable in the control room, i -
L..a.
1;'2
. b '. =
2;f3.
c.
3; 2:
~d.
2 ;
1'
QUESTION: 33-(1.00)
L5'steamline break has1 initiated inside Unit 1 containment with
~
- T currenticonditions as:follows:-
Containment pressure-=c7 psig
' Containment radiation = normal
-
- LS/Gl levels = -145 inches and -185 inches
- PZR; pressure = 1800 psia-lRWTLlevel = 30 feet
- S/G; pressure = 680 psia and 580 psia
,Using'the ab'ove11nformation,=selectctie group of actuation signals
,
"thateshould'have occurred.
.a..
': +
-
c.
, S I A S,., S G I S, CSAS, AFAS
- d.
= SI AS L-- AFAS. BLOCK, CSAS, CIS
.
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(QUESTION:-34.
(li00)
.
Unit 1 h'as experienced a LOCA during which a CIS actuation has
'
"
.cccurred.
Which one of.the following must occur to-allow-
!
'
'racetting,CIS?
70.
The. reset. time delay must time out.
b.:
-All CIS isolation valves must.have reached theLfully shut.
position.
.c?
'All'CISt isolation valve. control switchesLaust be placed in CLOSE.'
-
,
.ed.:
Both reset;pushbuttons~must be depressed simultaneously.-
a fQUESTION:135 (1. 00 )~
Unit-2 is at normal. operating pressure / temperature when 128 RCP ecxperiences a' single and complete failure of its middle seal.
- Whichdone~of.the'following sets of seal parameters indicates this
-
failure?'
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MIDDLE SEAL UPPER SEAL
'
PRESSURE (PSIA)1
. PRESSURE (PSIA).
,
L.a.
- 1150 100
'}
l
-
b.
2200 1100
1
'sc, 1150.
1150 t
I
$d.
'2200 2200 g
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' QUESTION: 36 (_ 1.00)
,
' Unit 12 is operating at rated load when-an inadvertent CSAS<is
'
generated.
What_ prevents spray down of the containment?
a..
The spray header isolation valves are closed because they require.an SIAS to open.
-
b '. -.The: spray header isolation valves are closed because they
<
require-both~CSAS and SIAS to open.
L c. --
The containment spray pumps are stopped because they require an SIAS-to start.
(d.
The containment spray pumps are= stopped because they-require
! QUESTION: 37 (1.00)
-There'is only one ' entry condition for EOP-8 (Functional' Recovery Procedure)' that allows; exiting-EOP-8.before EOP-8 is completed.
a Which:one of'the following conditions for entering EOP-8 allows an-
,
exit before.EOP-8-is completed?
, (a.:
.EOP-6:.(SG Tube Rupture) has been implemented, but the' shift-supervisorc(SS)1wants to check the EOP-8 guidance on RCS-Pressure and Inventory Control.
- Eb.
EOP-6 (SGTR) han been implemented, but the SS determines the-acceptance critoria for RCS P' essure and Inventory Control
,
Tareinot being' met.
. c.3 EEOP-0 (Post-Trip Immediate Actions) has been completed, but-the SS~can't determine whether the casualty is a LOCA or a'SG-tube ru'pture.
L
- EOP-Of(Post Trip Immediate Actions) has been completed, but cd..
Vj the'SS. considers he has a coincidental LOCA and SG tube
rupture.
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-QUESTION: 38 (2.00)
10P-2;(Plant'Startup-from Hot Standby to Minimum Load) requires that Attachment 1C of OP-6 (Pre-Startup Checkoffs) be completed
(b3 fore Mode.2-is-entered.. The condition or. status at which Mode 2 l
,
must be: declared depends on the method of approach to criticality j
~
- b31ng used i (CEAs or 'RCS Boron).
For each method of, approaching-
" criticality, state the condition or status ~at which Mode 2 must be
'
dsclared.
-(1. 0 - each)-
. (1) >
.CEAs
',-(2):
- RCS boron
!
!
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QOESTION: 39 (1.00)
Which;one.of the"following combinations states the. dose' rate limits (in' REM per. hour) above which the associated area must-be postedias an Exclusion High Radiation Area.or a1 Locked-High Radiation' Area?
i Exclusion'High-Locked High Radiation 1 Area Radiation-Area a..
10 L
.i.
b..
1
C
- c.
10'
100
'
"d.
100.
10-i
,
b
- .
,
b
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QUESTION:' 40 (1.'0 0 )
Which one of the following correctly states the essential feature
'
of the practice of self-verification as followediat Calvert Cliffs
' Nuclear Power Plant?
G.
Following standard mathematical verification procedures to-ensure plant-calculations are error-free, b.
Checking.to ensure an intended action / component is appropriate or correct before the action is taken.
c.
Initialling the procedure checkoff list at the completion of each step, before'the next step is. started.
<d..
Using a self-generated checkoff ~1ist at the completion of a task to ensure all actions were correctly executed.
QUESTION: 41 (1.00)
Whichione of.the=following actions can be approved / authorized by-the Control Room Supervisor without prior authorization from the Shift Supervisor or higher authority?
L-
<a.
-Temporarily removing an alarm arnunciator from service, o
,
ib.
Changing a plant computer alarm limit from the setpoint-file.
L c.
Bypassing an alarm annunciator limit NOT listed in the
'
L setpoint file.
'
3 d.'
Temporarily bypassing a plant recorder point.
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gl QUESTION:142:
_(1=00)
,
Mo2t; procedure deviations must have the approval of the Shift-Supervisor (SS),;orLif immediate action.is required and.the SS is L
.not$available, the Control Room Supervisor (CRS)' mayfapprove the dsviation. unilaterally.
Deviations from which one of the following procedures always requires the approval of BOTH the CRS
~,
- end SS?.
a.
- EOP-1-(Reactor Trip)
b.;
AOP-2A (Excessive Reactor Coolant Leakage)
-( c.
_OP-3 (Normal Plant Operation)
d..
OI-6 (Reactor Protection)
QUESTION: 43.
( l'. 00 )
'
- During-verification of a FULLY.OPEN manually operated valve, the operator should:
,
fful'ly close the volve, then' reopen the valve to the fully:
a.
open position.
1 b._
operate the valve. handwheel'in the open direction, if the handwheel does not move,-the valve is fully open.
E c.c operate 1the-valve' handwheel in the open directionLuntil the valve is'backseated one-half turn, d.
Loperate the valve handwheel in the close direction,-then reopen the valve to the fully open position.
,
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. QUESTION:-44:
(1.00)-
'
.Tho MAXIMUM fluid system. temperature and pressure 1that can exist during.componenta epair WITHOUT requiring two. valve isolation are r
degrees F.and.
psig.-
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c; l'i O O, 5 0 0,
E.
L200, 1000
-!
b c.
212,-500
}
-5 di 212, 1000
,
x
>
,
i QUESTION:'45
.(1.00)
t lA 25' year-old licensed male reactor oporator has the following scxposure history:~
,
Lifetime whole' body dose - 34 rem Current quarterly;whole body dose - 400 mrem
- Assuming his-exposure is. properly documented, what is the maximum-Scdditional;whole-body exposure this operator can receive this t
'" : quarter -and9 ;111s comply withl10 CFR 20? -
a.
.600 mrem
+
b.-
825 mrem m
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'2600' mrem
,
'
d..
"2825c mrem
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Pago 44-
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c,) 4 QUESTION: 46
' ( 1 ~. 0 0 )
,
m..
EE gWhLt'is-the Calvert Cliffs administrative exposure limit-(Alert
" Point) for ai 25Lyear-old licensed male reactor operator?
'
, y
- C..
-l500 mrem / quarter i
..b.
900 mrem / quarter:
'
!
h c.-
'1250 mrem / quarter
'd.
12000 mrem / quarter i
r LQUESTION: 47
.(1.00)
- EOP-1~directsLthe operator to, " Verify heaters or sprays restoring L
prassurizer pressure to between.2225'and 2275' psia." When used in
- tho; previous example,Lthe term " VERIFY" means:
- a.
to make sure by~taking necessary or appropriate actions..
q
'b '
=
- to observe.anfexpected condition or characteristic;.to
.
,..
,.,
determine; to ascertain..
[*
"c.
to watch or monitor;.to visually take note of;-to pay l
- attention!to.
!
.
.
d.
'tol attend to displays to determine equipment. operating-
,,
- conditions, o
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w QUESTION: 48'
(1.00)
' Locked valve MS-109, 21 AFW' Pump-Main Steam Supply.was closed and
-
taggedifor repairs cn1 21 AFW pump.
When repairs were-completed,,
MS-109.was: opened and, locked by a licensed operator.
Does another
,
licensed' operator have to verify the condition of.MS-109?
,c.
Yes, because the second: verifier of restored locked valves must.be a-licensed operator.
,
.b.
Yes,Ebecause two-licensed operators are required to verify
.
the position of restored-locked valves.
i c..
No, because only one licensed operator is required to
- participatelin the verification process for locked valves, od.
No, because any' person qualified to operate this' valve may.
perform the second verification.
,
g-QUESTION: 49 (1.00)
,
u, 1 Unit 2 = is ~. operating at 70 - percent' power during a power ascension eto'100 percent. -What indication should be used as the PRIMARY
>
Rindication of reactor power?
a.
Wide range' logarithmic pow'er channels
.
Lb.
Power range Safety. channels
'c.-
TOS delta-T power channels d.-
Secondary calorimetric power (plant computer)
0
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.. lQUESTIONi 50 (1.00)'
'
'Which:one offthe following normal evolutions requires that the jopgrator.have'the appropriate procedure PRESENT.
.
'
' 6. :
Shifting charging pumps
-
p b.
Commencing blended makeup to the.vCT d
t y-
,
a 'c, Shifting compone'nt cooling heat exchangers j
E d '.
Stopping a circulating water pump
?
1. QUESTION : 1511 (2.00)-
3 i
'y tin'accordance with CCI-112J, Safety Tagging, list FOUR conditions-i under:which' independent verification of a restored valve.may be a
g'
waived, assuming < proper authorization is received.
(0.5 each)
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ENERGENCY AND ABNORMAL' PIANT EVOLUTIONSi :m 4b
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Pag 3947)
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{I,g.,.:(43%)'-
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- ANSWER:'
'01:
-(3. 00),.
m. - -(1)
Rx delta-T:(Thot-Tcold)
(2)
10-to 50 degrees F'.
s b..
(1)'
CET-temperatures.
(2)
Consistent,with-Thot-Lc.
. (1)i Steaming; rate--
.
(2)
Affacts RCS-temperature (0.5 each part)
.
- REFERENCE:
~000055A202
..(KA's)
ANSWER:
(1.00)
b.;
REFERENCE:
.3.0/3.4;
-
.
000056A249
..(KA.'s)
-
ANSWER::
- 03 (2.00)
'(1)( Opening:the CEDM motor generator normal load (output)
ContSctors-(2) ' ieressuri 9r presstire.
'
'(3)
.(Control Roos.) Aparator
.(4).Deenergizing the CEDM' motor generator sets (or 480v supply buses;for CEDM MG sets'or 12A and 13A buses)
,
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JORY 5 CONTINUED ON NEXT PAGE *****)
o
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!
o LOR-63-1-88, p. 7, EOP-0 i
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05-(1.50)
^
i (c)
(0.5 each blank)
(b)-
bearing (guide or thrust)
,
-(c)
(lower) seal cavity / controlled bleadoff REFERENCE:
AOP-7C p. 5, OI-1A p. 13, 14
!
R01ated.K/As 000015A120 000015A122 000015A123 3.1/2.9, 2.7/2.7, 4.0/4.2, 3.1/3.2
,
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(1. 00)
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SD-38,-p. 21,22
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..(KA's)
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(1.00)
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-4.2/4.5
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TO I
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REFERENCE:
,
SD-6 p. 26, fig. 6-3
.SD-41 p. 42 and fig. 41-10
'AOP-7D p. 6 2.9/3.4 000065K303
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(1.00)'
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101AT (0.25 EACH)
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.(3)
104R
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(4)
114R
REFERENCE:
LOR-202-7I-89 p. 22 3.3/4.0
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.13 (1.50).
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,
P
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'
I AOP-6D 3.7/3.8-i 000036G006
..(KA's)
-i ANSWERt.
(2,00)
L (c)-
200_
(0.5 each)
(b)
Open=CVC-514 (BA Direct Makeup Valve)
'
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'
L (d)- Start-all available charging pumps (*****
CATEGORY 5 CONTINUED ON NEXT PAGE *****)
.
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RO-202-7G-2 p. 9
.
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(1.00)
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OI-34, Sect VI, VIII 3.7/4.0 000057A204
..(KA's)
.
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(2.00)
?
(1). CET temperatures begin increasing (or SGs become ineffective
,'
for heat removal)
B.th SGs are isolated (due to low level)
(1.0 each)
(2)
o
,
REFERENCE:
EOP-3;~SRO-201-3-0 p. 13
!
4.2/4.5 000074K305
..(KA's)
. ANSWER:.
(1.00)
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SRO-201-3-0 p. 14 4.0/4.4 000074K301
..(KA's)
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REFERENCE:
LP-RO-62-1-2, p. 9 LP-RO-62-1-2, EOPs, attachment 9 LO - None available 3.7/3.8 000040K106
..(KA's)
ANSWER:
(1.00)
Grcen (Safe-Reset) light is off
. REFERENCE:
i LP-RO-122-1-2,.p. 11 I
LP-RO-122-1-2, LO 2.6 3.1/3.5
,
000061A204
..(KA's)
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'CI-12A, p. 4 LP-RO-103-1-0, p. 28, 29 LP-RO-103-1-0, LO 3.5 j
LER 84-03 l
4.4/4.6 i
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(1.00)
i d.
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REFERENCE:
LP-LOR-201-5-88, LO 2.3
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.
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,
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Open feeder breaker to 12A 480v bus (0.5)
l C
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l 3.
Open tie breakers to 12A and 13A 480v buses (0.5)
l j
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.
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-
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i
.i (1)
T-cold i
(2)
Pressurizer pressure (3).RCS flow rate (4)
ASI (0.5 each)
REFERENCE T:chnical Specifications, LCO 3.2.5 LP-RO-212-3.2-1, LO 2.04-l 3.1/3.5 l
j
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(1.00)
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EOP-6, p. 3
.
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(2."0)
,
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(2)
S/G blowdesn (RE-4014)
(3)- 11 SG Main steamlino (RE-5421)
,
'(4)
Main vent gaseous (RE-5415)
'
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Main vent wide range noble gas monitor (RIC-5415)
_(6)
SG blowdown recovery (RE-4095)
(Any five at 0.5 each)
!
REFERENCE:
LO - None available
,
.AOP-2A, p. 4 D
SD 15, p. 19-26, 46-54, 63 3.9/4.0
!
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..(KA's)
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REFERENCE:
,LO-- None available AOP-3B, p. 15 3.4/3.6'
000025G007
..(KA's)
,
ANSWER:
(1.00)
PrGvent boron precipitation (in the core) or Flush,(concentrated) boron out of the core (oither for full credit)
REFERENCE:
LO'- None-available EOP-5, p. 28 4.2/4.5 000009K321
..(KA's)
ANSWER:'
(1.00)
-a.-
REFERENCE:
OI-17C, p. 16 LP-RO-133-2-3, p. 16 LO - NoneLavailable 3.7/4.21-000060A205
..(KA's)
(*****
END OF CATEGORY 5 *****)
.
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ICR-202-7C-89
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..(KA's)
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(1.50)
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-(4)
(0.5 each)
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(6)
.c.-
(7)
,
REFERENCE:
SD-35 p.
9, 10, 15, 23
2.5/2.8.-
075000K401
..(KA's)
(*****
CATEGORY 6 CONTINUED ON 'JEXT PAGE * * * * * )
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RO-307-1-0 P.
52'
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..(KA's)
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3.1/3.5 (
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SD 62~p. 29
3.6/3.5
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LP RO-59-1-4 p. 17
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(1.00)
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'
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LP RO-58-2-2 p. 12
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High Pressurizer. Pressure
,
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!
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I
.
R0-59-1-4 App D
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..(KA's)
+
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(2.00)
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(1)
(2)
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(0.25 each blank)
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11, X
'll
,
d.
ALL.
11, 12
.i REFERENCE:
SD-63 p. 111, 112 4.1/4.0 l
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,
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(1.00)
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...(KA's)
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(1.00)
3
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REFERENCE:
i LP-RO-60-1-2, p. 40
.
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..(KA's)
.
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- 17-(1.00)
.
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REFERENCE:
LP-RO-133-2-3; p. 17
'LP-RO-133-2-3, LO 6.4 l
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,
2.5/2.8-j
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LP-RO-133-2-3, LO 2.1
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..(KA's)
.
ANSWER:
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l
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l
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,
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LP-RO-34-1-2, p. 8 i
LP-RO-34-1-2, LO 2.02a, 2.02b
'
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..(KA's)
.
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122 (1.00)
,
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LP-RO-64-1-1,'3.01a
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"
'D-57, figure 57-10 La'-5 7 - 1-1, LO 3.01
,
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..(KA's)
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- p
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REFERENCE:
i t.,
LP-RO-57-1-3, Question #4.07 LP-RO-57-1-3, 14 4.07 SD-57, figure 57-12 i
ARP, 1C05, D-41 l
3.7/3.9
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d.
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'
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REFERENCE:
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4.'
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- Facility Comment:
Section 3,
Answer should be a) 12, c) 11.
EDG~ starts on UV to bus to which it is connected.
.SD-63, p.
113; LD-35.
Examiner Response:.
Concur.
The reference for this answer,.
System Description 63-(SD-63), has-apparently been revised.
The revision
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3 version of SD-63, which vas.provided by the facility for use in preparing the written exam, indicates the ansvers were correct as written.
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4.
Facility Comment:
'Section 3,
- 15 (RO).
Answer should be (b).
A deviation of greater than 4
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SD-60, p.
37.
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Examiner' Response:
Concur.
However,.there appears to be a ti-contradiction.between SD-60-and 01-42.
.
Section VII of-OI-42 (attached) titled, CEA Leveling With Less Than-7.5 Inch
.
Deviation,-does not state that a CMI
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It is recommended that 01-42 be revised to-include a NOTE referring to the requirement for bypassing 1a CMI.
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