ML20206T625
| ML20206T625 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/30/1986 |
| From: | Burdick T, Dave Hills, Lanksbury R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20206T610 | List: |
| References | |
| 50-254-OL-86-02, 50-254-OL-86-2, NUDOCS 8610070111 | |
| Download: ML20206T625 (83) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-254/0L-86-02 Dockets No. 50-254, 50-265 License Nos. DPR-29, DPR-30 Licensee: Coninonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Quad Cities Nuclear Power Station Examination Administered At: Quad Cities Nuclear Power Station Examination Conducted: September 15-17, 1986
$. S. k h 9!30/f6 Examiners:
D. E. Hills Rbhh R f lanksbur 9l30/86 9 R3!%
Approved By:
u di f
Operator Licensing Section Da'tb I
Examination Summary ExaminationadministeredonSeptember15-1L_1986BeportNo. 50-254/0L-86-02)
Written and oral requaliTicaTion examinations we're administerWtif f"our Senior Reactor Operators (SR0) and four Reactor Operators (RO).
Results: Two SR0's and one R0 passed these examinations. All others failed one portion of the examination. The Requalification Program Evaluation Report is contained in Attachment 3.
8610070111 G60?30 PDR ADOCK0500g4
REPORT DETAILS 1.
Examiners D. Hills -- Chief Examiner R. Lanksbury 2.
. Examination ~ Review Meeting.
Specific facility comments concerning written examination questions, followed by the NRC response, are enumerated in Attachments 1 and 2.
3.
Exit Meeting At the conclusion of the examinations, an exit meeting was conducted.
The following personnel attended this exit meeting:
Facility Representatives T._ Tamlyn, Production Superintendent R. Robey, Services Superintendent J. Neal, Training Supervisor W. Graham, Principal Instructor C. Norton, Quality Assurance Engineer R. Sualeson, Instructor M. Kooi, Regulatory Assurance NRC Representatives T. Burdick, Chief, Operator Licensing Section D.-Hills, Operator Licensing Examiner R. Lanksbury, Operator Licensing Examiner J. Keeton, Operator Licensing Examiner A. Morrongiello, Quad Cities Resident Inspector
-The following items were discussed:
a.
Requalification program evaluation guidelines, criteria, and responses.
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.b.
Current status of the new Rcd Worth Minimizer System being installed at Quad Cities.
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7-ATTACHMENT 1 QUAD CITIES STATION COMMENTS R0 EXAM 09/15/86 Facility Comment:
1.01 Concerned the tail pipe temperature of an open SRV and interpretation of the Mollier diagram.
Parts "a" and "b" are good questions with answers that you could use. Parts "c" and "d" are somewhat less defined. The wording in Part "c" is confusing, did you mean we are opening the relief valve to depressurize the reactor or are we already depressurized in which case the SRV won't even open.
Part 'd" answer is difficult to find on the Mollier diagram and the basis for the answer is not understood. This really does not pertain to an.NS0 job.
Examiner Response:
4 1.01 Part "c" pertains to opening the relief valve to depressurize the reactor. Candidates were given the chance and even encouraged to ask for clarifications during the exam; however, no such requests were noted for this question. The answer'to Part "d" could have been detennined from the Steam Tables as well as the Mollier diagram.
Facility Comment:
1.02 Concerns the placement of a high powered bundle near the edge of the core. Part "a" should be "the same" because the orifice did not move with the fuel bundle. The orifice introduces a large pressure drop at the core entry point to insure that the effects of two phase flow are considered significant.
Part "b" has an incorrect statement in parenthesis.
Examiner Response:
1.02 Agree with the convr.ent on Part "a".
For Part "b", the statement is correct. The bundle has a smaller orifice as a peripheral bundle than it would as a centermost bundle. Tuo-phase flow increases and power decreases since it is a higher power bul.dle than normal.
Facility Comment:
1.04 Concerns calculating a negative period following a scram, which is never done, and determining a proper range to be on. To calculate a period problem should not be a problem, but ranging IRM's is done by procedures. QOP 700-2 states that they be kept between 20/125 and 50/125 of scale, Range 1, therefore, is an incorrect response.
r-Examiner Response:
1.04 Question asks for the minimum range without violating any cperational limit and not what is the minimum range per procedure. Although the correct answer is Range 1, will accept Range 2 if an adequate explanation is given.
Facility Comment:
1.05 Concerns control rod positioning. Statement "b" says "it is not uncommon" but it only applies at E0L. At BOL it would not be conmon at all.
Examiner Response:
this did not affect any results.
1.05 Agree Facility Comment:
2.01 Concerns Reactor Recirculation Pump seal failure indication in the control room. There is no GPM leakage indication in the control room as indicated by your answer key. Leakage data in the lesson plan is
" nice to know" material, and the students are not required to know it.
Examiner Response:
2.01 Agree with most of corrment concerning flow except for Part "b".
Can easily detect 60 gpm to DWEDS in the control room. Answer key will be modified.
Facility Comment:
2.03 Concerned fuel orientation and is a good question for SR0's. NSO's don't verify fuel bundle orientation.
Examiner Response:
2.03 Agree - question deleted.
Facility Comment:
2.04 Concerns HPCI restarts after a LOCA. The only place the answer to "b1" can be found is in the electrical prints.
It has never been put into a lesson plan or procedure. The answer to "b2" is a direct quote from a procedure (QOA 2300-1) that the R0's aren't required to memorize.
It also assumes other prerequisites are met, such as the oil pumps are running.
Examiner Response:
2.04 Concerning the comment on "b1", licensed personnel should know this and training material should be modified accordingly. The purpose of "b2" is to determine if the operator understands what is required for system operation.
Facility Comment:
2.05 Concerns the casualities incurred due to a loss of instrument air.
The operators would have more things to notice than what the answer key indicates.
For Part "a" he would probably notice that the SJAE suction valves closed before he notices that he lost steam supply to them. The Part "b" answer is also incomplete, it should include TBCCW TCV failing open and dropping the temperature of all services equipment. There are lots of things affected by instrument air.
Examiner Response:
2.05 Agree - these other actions were considered in the grading.
_Fac_ility Comment:
2.06 Concerns EHC logic. The question and answer are basically good; however, the C.V. scram is not based on hydraulic pressure but on energizing the fast acting solenoids due to a load reject.
Examiner Response:
2.06 This is one scram but the one referred to in the answer key is the EHC low oil pressure (4900 psig). This portion of the question was meant to see if the operator knew this or if they would expect a half scram because of limit switches such as on the stop valves.
Also, although not on the answer key, all C.V. trips are bypassed at <45% power.
Facility Comment:
3.01 Concerns SRM trip reset requirements. The answer should state that all SRM trip circuits automatically reset. The memory lights are i
the only things that must be manually reset.
1 Exeminer Respouse:
3.01 Per the reference supplied for the examination and to support the comment, the answer key is correct.
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Facility Coment:
3.03 Concerns APRM trips. The Part "a' should' state that the trip occurs at 12 LPRM inputs, not <12 so an APRM INOP 1/2 scram and rod block would already be present prior to this LPRM failure.
In part "b",
no rod block would occur because the RBM inputs must be 4,4 LPRM inputs. As described there would still be 4 LPRM inputs.
Examiner Response:
3.03 Agree - question has been rephrased to resolve this for future use.
Facility Comment:
3.05 Concerns scoop tube lockup and is a good question, but the answer to "b" should include resetting it locally as well.
Examiner Response:
3.05 Considered in grading but answer key not changed since this is not done every time but only under certain circumstances.
Facility Comment:
3.06 Concerning SBLC injections and is true/ false. None of the answers are correct.
Reference LIC-1100, page 2, Section A2C. The question asks the person to choose the correct one.
Examiner Response:
3.06 Agree - answer key is changed. Will also accept original answer in answer key.
Facility Comment:
4.01 Concerns the basis for 5 (N-18). What operational benefit is derived from knowing this? This does not apply to the NS0 job.
Examiner Response:
4.01 Disagree - rad workers should know this.
In addition, the question did not ask for the " basis" but rather for when it is used.
Facility Comment:
4.03 Concerns emergency dose for life saving and is not operational in nature.
In that situation, the man will not know the dose anyway so he must make a choice to do it or not.
n Examiner Response:
rad workers should know this.
4.03 Disagree Facility Comment:
4.04 Concerns jumpers and blocks. The R0's have nothing to do with them.
It does not apply to the R0's.
Examiner Response:
question deleted.
4.04 Agree Facility Comment:
4.07 Concerns evidence of SBLC injection. The answer key does not include all available indications.
Examiner Response:
4.07 The question specifies INITIAL indications. Any reasonable answer within this will be accepted.
Facility Comment:
4.08 Concerns detecting a breach in primary containment. The answer key only has the symptoms listed in Q0A 1600-2, and there are many more that could be listed. All reasonable answers should be considered.
Examiner Response:
4.08 The Examiner Standards require operator to know symptoms of abnormal procedures.
Facility Comment:
4.09 Concerns the running of the aux. pump on RCIC crossfed. The procedure was paraphrased into a one paragraph statement. From that the student was asked to make true/ false judgment on listed statements.
It is extremely hard to follow and the real procedure is not required to be memorized.
Examiner Response:
4.09 Question did not require procedure memorization but rather understanding of how to operate the system or how it would respond once in the given configuration.
r ATTACHMENT 2 QUAD CITIES STATION COMMENTS S_R0 EXAM 09/15/86 Facility Comment:
5.07 The answer to Part "c" should include Tstch Spec mismatch limit
(:515% mismatch when4 80% power).
Examiner Response:
5.07 Will give credit for this answer if operator explains basis of this Tech Spec limit.
Facility Connent:
7.04 Concerns QGP 1-1 pressure milestones. The procedure states "when the low pressure isolation signal clears" not 50 psig.
Examiner Response:
will give credit for the actual setpoints if given correct-7.04
' Agree ly for both HPCI and RCIC or will accept "when low pressure isolation signal clears".
Facility Comment:
8.04 Concerns inadvertant Group I isolation 100% power. There is no really correct answer because no real Group I signal existed (Technicianerror). MSIV closure scram is based on low pressure in the steam lines.
Examiner Response:
8.04 Per Technical Specification dasis 2.1.H "the isolation valve closure scram in tne Run mode anticipates the pressure and the flux transients which occur during normal or inadvertant valve closure. With the scrams set at 10% vlave closure in the Run mode, there is no increase in neutron flux". Since the itolation valve closure scram did not function as designed, a pressure and flux transient from the 100%
initial power condition did occur.
From the data received, one does not know the magnitude of this transitnt and thus, if any safety limits were violated.
r f_acility Comment:
8.05 Concerns when SBLC is not required. The conditions listed are not conmon jargon at this station, i.e., what is a "subcritical check" or a " control rod functional check". Students did not know what they were and examiner would not tell them.
Examiner Response:
8.05 These terms are defined in the Quad Cities refueling training module (LIC-REFL).
Facility Comment:
8.11 Concerns reducing scram and rod blocks. Answer "a" should include extended single loop operation @r24 hours) in license (letter K) in Tech Spec. Answer "b" should include reducing the APRM setpoint by the amount specified in TS 2.1.
Examiner Response:
8.11 Agree - will accept either answer for credit.
f ES-601-4 REQUALIFICATION PROGRAM EVALUATION REPORT Facility:
Quad Cities 1 and 2 i
Examiner:
D. Hills Date(s) of Evaluation:
09/15-17/86 Areas Evaluated:
X Written X
oral Simulator Examination Results:
RO SRO Total Evaluation Pass / Fail Pass / Fail Pass / Fail (S
M, or U)
Written Examination 1/3 2/2 3/5 U
Operating Examination Oral 4/0 4/0 8/0 S
Simulator Evaluation of facility written examination grading overall Program Evaluation Potentially Satisfactory Marginal Unsatisfactory X (List major defi-ciency areas with brief descriptive comments)
A generic weakness was identified in Section 8 " Administrative Procedures, Conditions, and Limitations" of the SR0 written exam.
In addition, the R0 written exam exhibited a generic weakness in Section 4.0, " Procedures -
Nomal, Abnomal, Emergency and Radiological Control". Remaining deficient areas appeared to be widespread but more on an individual basis.
Submitted:
Forwarded:
Approved:
,O [
M 1
ilA Examiner Section Chief Branch Chief L
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S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY
_9QGD_G111ER_1k2_________
REACTOR TYPE:
_lMB gg_________________
DATE ADMINISTERED _g&fg9/15________________
EXAMINER:
_HILLE,_Dz_______________
CANDIDATE:
_M$$~[d_
INgIBUCIlgNg_Ig_g8Np]p6IE1 Racd the attached instruction page carefully.
This examination replaces the current cycle facility administered requalification examination.
R2 training requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by
(
your training staff.
Points for each question are indicated in j
perentheses after the question.
The passing grade requires at least 70%
[
in each category and a final grade of at least 80%.
Examination papers will be picked up four (4) hours after the examination starts.
% OF CATEGORY
% OF CANDIDATE'S CATEGORY
__Y8LUE_ _IQI@6
___SCgBE___
_y@LUE__ ________
____C@lEGQBY_________
__ 5.
THEORY OF NUCLEAR POWER PLANT
_19z19__ _26z12 OPERATION, FLUIDS, AND THERMODYNAMICS
_19299__ _2}12h
________ 6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION
_12tD9__ _2Zz24
________ 7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CCNTROL
_1Dz99__ _25124
________ B.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS
_s2249__
Totals Final Grade l
All work done on this examination is my own.
I have neither given nor received aid.
Candid $te s Signature
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~'~~~~~~~~~~~~~
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NRC RULES AND GUIDELINES FDR LICENSE EXAMINATIONS During the administration of this examination the following rules apply 1.
Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2.
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.
3.
Use black ink or dark pencil gnly to facilitate legible reproductions.
4.
Print your name in the blank provided on the cover sheet of the ex ami nati on.
5.
Fill in the date on the cover sheet of the examination (if necessary).
6.
Use only the paper provided for answers.
7.
Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
B.
Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write gnly gn gne side of the paper, and write "Last Page" on the last answer sheet.
9.
Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least thtee lines between each answer.
Separate answer sheets from pad and place finished answer sheets face 11.
down on your desk or table.
- 12. Use abbreviations only if they are commonly used in f acility literatute.
j
- 13. The point value for each question is indicated in parentheses af ter the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the examinet only.
- 17. You must sign the statement on the cover sheet that indicates that the in work is your own and you have not received or been given assistance completing the examination.
This must be done af ter the examination has l
been completed.
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- 10. When you complete your examination, you shell s Assemble your examination as f ollows:
o.
(1)
Exam questions on top.
Exam aids - figures, tables, etc.
(2)
Answer pages including figures which are part of the answer.
(3)
Turn in your copy of the examination and all pages used to answer b.
the examination questions.
scrap paper and the balance of the paper that you did Turn in all c.
not use for answering the questions, If after Leave the examination area, as defined by the examiner.
leaving, you are found in this area while the examination is still d.
in progress, your license may be denied or revoked.
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PAGE 2
THEDRY Og_NUC6ggB_ggggB_g69NT_gggggTIgN _gbulpS,9Np 3
3 5
ISEgyppyN601CS QUESTION 5.01 (1.50)
Explain the dif f erence between driven flow and driving flow within(1.0)
O.
the reactor vessel.
Which of these provides the greater contribution to the total core(0.5) b.
flow?
DUESTIDN 5.02 (1.00) assemblies are designed to incorporate water rods 1
(1.0)
Explain why fuel although these rods contain no f uel pellets.
4 QUESTIDN 5.03 (1.60)
Define the terms " moisture carryover" and " moisture carryunder,"
the adverse consequences describe the possible causes and explain all (1.6) of each in the reactor vessel.
N ili ll QUESTIDN 5.04 (2.00) indicate which reactivity each of the following transients, coefficient (Moderator Temperature, Void, or Doppler) tends to change For 4
power first and in what direction.
(0.5)
Fast closure of one Main Steam Isolation Valve (0.5) m.
b.
Isolation a feedwater heater string (0.5)
A control rod drop (0.5) c.
d.
Relief Valve lifting S
CATEGORY 05 CONTINUED ON NEXT PAGE
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THEDRY OF NUCLEAR _P9WER_ PLANT _gPgRATIgN _FLUIDg3_gNp 3
5 IHERggpyNgdICS GUEST!DN 5.05
(.50) k-effective is increased from 0.880 to
- reactor, In a suberitical the f ollowing is the amount of reactivity added to O.965.
Which of (0.5) the core?
o.
0.085 delta k/k b.
O.100 delta k/k O.125 delta k/k c.
d.
O.220 delta k/k QUESTION 5.06 (2.00)
Select the correct word in parenthesis f or each of the following otatements:
the (shorter, longer)
(0.5)
The closer the reactor gets to critical, neutron density to a.
the wait must be to allow the subcritical reach equilibrium.
(more, less) outward rod movement will be During reactor heatup required at higher temperatures for a given coolant temperature b.
(0.5) increase.
(Beginning-of-Lif e, Middle-of-Life, End-of-Life) is the time in core lif e which requires the least amount of positive reactivity c.
(0.5) addition to achieve prompt critical.
The margin to the minimum critical power ratio limit will (increase, descrease, remain the same) with an increase in recirculation d.
(0.5)
Assume rod positions remain constant.
flow.
!)
QUESTION 5.07 (1.50) i f ollowing a recirculation pump trip the operating i
(0.5)
Explain why l
a.
increase.
recirculation loop jet pump flow will
- }
Explain why f ollowing this recirculation pump trip indicated (0.5) i b.
flow.
core flow will read higher than the actual j
Explain why when restarting the idle loop the operating f
(0.5) recirculation pump speed must be reduced to 45% or less.
c.
CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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T __T'HEORY_gE_Nyg6 EAR _PQWER_ PLANT _QPgRATJgN _ELUJpg,_8ND 3
Dt IHEBU9PyN951gg QUESTION 5.08 (1.00)
Explain why the water level in the reactor vessel can be higher outside the dryer skirt (downcomer region) than inside the skirt.
(1.0)
QUESTIDN 5.09 (1.00)
Calculate a reactor cooldown rate (deg F/ hour) for a vessel pressure Show all work for decrease from 800 psig to 350 psig in one hour.
(1.0) full credit.
QUESTION 5.10
(.50)
Concerning control rod worths during a reactor startup from 100*/. PEAK which statement XENON versus a startup under XENON-FREE conditions, (0.5) is correct?
a.
Both central and peripheral control rod worths will be lower regardless of core Xenon conditions.
b.
Central control rod worth will be higher during the PEAK XENON startup than during the XENON-FREE startup.
c.
Both central and peripheral control rod worths will be the same L
l regardless of core Xenon conditions.
j d.
Peripheral control rod worth will be higher during the PEAK XENON 1
i startup than during the XENON-FREE startup.
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QUESTION 5.11 (1.50) a.
Explain how e " reverse power effect" can possib3y occur in response to a one-or-two notch withdrawal of a control rod.
(1.0)
'j j
" reverse power effect" be more likely to occur (0.5) in the j
b.
Will withdrawal of a deep or shallow rod?
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THEORY OF NUCLEAR POWER PLANT OPERATION _FLUIpS,$Np 3
3 5.
IL48599LN95LCS QUESTION 5.12 (1.00)
Explain why the shutdown margin specification f or a shutdown margin test conducted at beginning of core lif e may need to be increased by a (1.0) difference of "R".
1' I
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~ 5___ELONI_gySI[dg_p{gl@N _GQNIBQ(g_@NQ_lNSIBQUENI@IlgN 3
QUESTION 6.01 (2.00)
(MSIVs) are set to close Explain why the Main Steam Isolation Valves (1.0) c.
between three and five seconds.
What systems provide the air supply to both the inboard and outboard (1.0) b.
MSIVe?
9 QUESTION 6.02 (2.50)
Indicate whether the reactor vessel l evel instrumentation f or each of the f ollowing level ranges is calibrated f or hot or cold reactor c.
conditions.
(0.5)
(1)
Wide Range OE/MAC (0.5)
(2)
Wide Range Yarway (0.5)
(3)
Narrow Range GE/MAC the trip functions associated wih reactor water level Explain why all come f rom the Narrow Range Yarways and why the input to the Feedwater b.
(1.0)
Level Control System comes from the Narrow Range GE/ MACS.
QUESTION 6.03 (1.50) cause an accumulator Describe the signals or conditions which wil) four light display portion trouble light to illuminate on the individual (1.5)
(Include setpoints as applicable. )
of the f ull core display.
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5__Ph@61_gygIEgg_DEglGN3_CgdIBD62_@ND_idgIBUDENIATIDU OUESTION 6.04 (2.00) initiate Indicate whether the Automatic Pressure Relief System will(Unless otherwise indicated under each set of the following conditions.
i below, assume that the system is in automatic standby readiness, a low pressure ECCS pump is running with greater than 100 psig discharge pressure and the 110 second timer is allowed to time out with no Also assume low-low reactor water level signals cperator action.
cre present f or less than 8.5 minutes. )
A high drywell pressure is sensed but subsequently decreases to well below the setpoint.
Following the pressure decrease a c.
(0.5) low-low reactor water level is sensed.
b.
A low-low reactor water level is senser but within two minutes increases to well above the setpoint.
Following the level (0.5) increase a high drywell pressure is sensed.
A low-low reactor water level is sensed simultaneously with a high drywell pressure.
Prior to the 110 second timer timing out, c.
(0.5) reactor water level increases to above the setpoint.
d.
A low-low reactor water level is sensed simultaneously with a Prior to the 110 second timer timing out, high drywell pressure.125 V DC Turbine Building Distribution power is lost to the (0.5)
Panel 1A-1.
QUESTION 6.05
(.50)
If the output of the recirculation speed control function generator would the recirculation pump suddenly dropped to zero milliamp output, (0.5) speed increase, decrease, or remain constant?
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6 __P68dI_SX@lEUS_ RESIGN 3_CgdIB063_8UQ_16SIBudENI611gN i
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i OUESTIDN 6.06 (1.50)
Intermediate Range Which one of the following combinations of (IRM) channels will result in a full scram assuming an c.
(0.5)
Monitor IRM High-High trip on those channels only?
A 3
(1)
Channels 11 and 12 (2)
Channels 14 and 15 (3)
Channels 13 and 14 (4)
Channels 16, 17, and 18 b.
List all the conditions under which the IRM downscale trip is (1.0) automatically bypassed?
4 y
5 QUESTION 6.07 (1.00) the f our automatic trips provided f or the diesel-driven (1.0)
List two of (Setpoints not required.)
fire pumps.
QUESTION 6.08 (1.50) the three signals which could cause a turbine runback List two of (Include upon loss of stator cooling for the main generator.
a.
(1.0)
Setpoints)
I b.
What automatic actions, if any, will r v.sul t if this runback (0.5) does not occur when required?
QUESTION 6.09 (1.00)
Explain why a dif f erential pressure is required to be maintained (1.0) between the Torus and Drywell.
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5 __Ph3NI_gy@][Dg_pgglgy3_C9NIBQ63_9dp_JN!IByDEMI$1]QN l
QUESTIDN 6.10 (1.50) system operates to maintain the discharge piping The ECCS fill of all ECCS systems as well as the RCIC system filled with water.
o.
Explain two reasons why the discharge piping of the ECCS is kept (1.0) filled with water.
)
system takes a suction from the core spray pump b.
The ECCS fill
.What is the alternate source of water to this suction line.
(0.5) system?
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PAGE 10 Z___EBgCgguBgS_:_H985062_eEN9Bdebi_g5EBEENGY_eND BBD1QLQElG66_GQNIBQL DUESTIDN 7.01 (2.00) the six methods for checking proper fuel orientation Describe f our of (2.-)
0 during refueling.
QUESTIDN 7.02 (1.50) result in an Indicate whether each of the following situations will increased or decreased recirculation pump number two seal pressures (0.5)
Failure of the number one seal (0.5) o.
Failure of the number two seal (0.5)
Failure of both the number one seal and the number two seal b.
c.
QUESTION 7.03 (1.00)
(no continued run f or cooling Describe two methods to immediately purposes) stop an emergency diesel generator locally in the event (1.0) of a fire or other emergency situation.
QUESTION 7.04 (2.00) indicate at what minimum pressure QGP 1-1, For each of the f ollowing, to normally be performed "Nor mel Unit Startup" prescribes that action occur during a reactor startup.
or (0,5) a.
Start Steam Jet Air Ejector (0.5) b.
Start a Reactor Feed Pump (0.5) c.
Warming of the HPCI and RCIC steam lines (0.5) main steamline drain valve MD 220-4 d.
Closure of i
i i
i QUESTION 7.05
(.50)
What reactor period limitation during a startup is prescribed by (0.5)
QGP 1-1 Nor mal Unit Startup"7 CATEGORY 07 CONTINUED ON NEXT PAGE
- )
9
(*****
_ _ _ ~ _
w PAGE 11 PROCEDURES - NORMAL,@BNgBMA(3_gdgRQgNgY,8Np 3
7.
B09196991986_99NI696 OUESTION 7.06 (1.00)
What are the two dose limiting recommendations f or voluntary personnel an emergency condition involving life saving (1.0) cxposures under cctions?
QUESTION 7.07 (2.00)
" Secondary the five entry conditions f or QGA 300-1 What are f our of (2.')
O Containment Temperature Control"?
QUESTION 7.08 (1.50)
" Normal Unit Shutdown" cautions that vacuum breakers should no be opened to slow the main turbine unless it is necessary to quickly GGP 2-1 a.
reduce turbine RPM.
(1.0) method?
it does become necessary to quickly slow the main turbine as in what vacuum limitations would be b.
Ifthe case of excessive vibration, (0.5) imposed on use of the vacuum breakers?
4 QUESTION 7.09 (2.00)
(2.0) reasons a Radiation Work Permit may be terminated?
What are four l
h l
I l
QUESTION 7.10 (1.00)
List two conditions that must be met prior to placing the economic
~
generation control system in operation with automatic flow (1.0) c ontr ol.
E I
I I
PAGE 12 Zs__EBgCEDyBES_;_NQBd@(3_6BNQBd863_EMEBGENQY_8ND bed 196991Ge6_G9NIBQL QUESTIDN 7.11 (2.00)
Describe f our methods of monitoring to assure actual Standby Liquid (2.0)
Control System injection following it initiation.
1 QUESTION 7.12 (1.00)
QDA 201-10 " Reactor Pressure Control Using Manual Relief Valve Actuation" prohibits actuation of any single relief valve within 10 seconds after that valve has been closed.
Explain why this (1.0) restriction is imposed.
o I
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END OF CATEGDRY 07 *****)
(*****
PAGE 13 0 __ePdjNJgl331]yg_PBgggguBgg3_ggNg1119Ng3_9Np_(Jg1IBIJgNg QUESTION 8.01 (1.00)
Specifications do not require the Rod Worth Explain why Technical (1.0)
Minimizer to be operable at greater than 20% power.
QUESTION 8.02 (2.00)
Specifications under what conditions would a control Per Technical rod drive which cannot be moved with control rod drive pressure a.
(1.0) still NOT be considered inoperable?
rods with scram times greater than those permitted by b.
Control Under what Technical Specifications are considered inoperable.
4 conditions would they NOT be required to be disarmed electrically?
j (1.0)
QUESTION 8.03 (1.00)
Fill-in-the-blanks In addition to three equipment attendants the Fire Brigade consists who serves as Fire Chief and the (1.0) of the (1) ______________ho serves as Assistant Fire Chief.
w (2)__________________
l l
t i
l INUED ON NEXT PAGE *****)
l
}***** CATEGORY 08 CONT
~. - - -
PAGE 10 Ez __6pMINigIBBIlyE _EBQCE QUBE@ 2_CONQlIlONg 3_gND,(I M I T AT igNg QUESTIDN B.04 (1.50) 100% power a group I isolation and a reactor scram While operating at Data collected from the plant computer and plant operators occur.
indicates the following occured:
The group I isolation was caused by a Technician error.
a.
The reactor scram was caused by high reactor pressure.
b.
Both feed pumps tripped.
decreased and HPCI and RCIC auto started and c.
d.
Reactor water level injected to the reactor vessel.
An operator secured HPCI, took manual control of RCIC and e.
maintained reactor vessel level below 48 inches.
A f eed pump was restarted and level control transfered to the f.
feed pump, RCIC was secured, Continuing to f ollow Quad Cities procedures, the plant is g.
placed in a normal shutdown condition.
(1.5)
Select and EXPLAIN the correct statement:
auto-initiated operation cannot resume because HPCI a.
Power and injected to the reactor vessel.
cannot resume becausef a saf ety limit may b.
Power operation have been violated.
operation cannot resume because the f eed pumps should c.
Power not have tripped.
the MSIVs have been l'
d.
Power operation cannot resume until inspected due to the Group I isolation signal.
QUESTION B.05
(.50) the f ollowing conditions occuring during ref ueling i
Under which one of would the Standby Liquid Control System NOT be required to be OPERABLE(0.5:
per Technical Specifications.
a.
Subcritical Check b.
Shutdown Margin Demonstration c.
Control Rod Functional Check d.
Lowering of a fuel bundle into the core
~ - - - -,, _ _ _ _ _ _,
PAGE 15 9:__ePd1NIEIB8IlyE_PBQCEggBES _Cg6911196@2_889_b15118I196@
2 QUEST 1DN B.06 (1.00)
Fill-in-the-blanks:
be Specification surveillance requirement shall Each Technical with a maximum performed with the specified surveillance interval (1)__________X of the allowable extension not to exceed maximum combined interval time and a total surveillance interval f or any 3 consecutive surveillance intervals not to exceed (1.0)
(2) _
____ times the specified surveillance interval.
QUESTION 8.07 (1.00) the Which of the six categories of emergencies require activation of (1.0)
Operational Support Center?
QUESTION 8.08 (1.00) 10 CFR 50.54(X) under which it is Describe the conditions per technical permisable to deviate from license conditions or (1.0) specifications.
QUESTION 8.09 (1.00) may be Describe the conditions under which shif t crew composition contained in less than the minimum requirements (1.0) allowed to be Technical Specification Figure 6.1-3.
o GUESTION 8.10 (1.00) cool ant chloride Technical Speci f ications establish a reactor concentration limit of 1.0 ppm with steaming rates greater than 100,000 lb/hr and of 0.1 ppm with steaming rates less than is a more restrictive limit at 100,000 lb/hr.
Explain why there (1.0) the lower steaming rate.
i l
CATEGORY 08 CONTINUED ON NEXT PAGE
- )
l
(*****
h___00MINISI6911ME_E8QCEDUBES_CQNDillgNSg_@ND_(IMlI811QNS PAGE 16 i
QUESTIDN B.11 (2.00) c.
The APRM Flux Scram Trip Setting while in the Run Mode is prescribed by Technical Specifications to be Si (.58 W, +62) where S is the setting in percent of rated power and We is the percent of drive flow required to produce a rated core flow of 98 million Ib/hr.
Under what condition must this setpoint be reduced?
(Assume remain in the Run Mode.)
(1.0) b.
How is this reduction of the trip setting actually accomplished?
(1.0)
CUESTION 8.12 (2.00) a.
QAP 300-2 " Conduct of Shift Operations" specifies a licensed operator or senior operator shall be present "at the controls" at all times during operation of the facility.
What is the meaning of "at the controls"?
(1.0) b.
DAP 300-2 " Conduct of Shif t Operations" also describes emergency situations and conditions under which a Unit Operator may leave his " stable and under control" reactor to help on the unit experiencing the problem.
What is the meaning of " stable and under control"?
(1.0) l l
i
(***** END OF CATEGORY OB *****)
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PAGE 17 9 __ISE98Y_9E_NyC(geB_E9MEB_E(@NI_gEEB8IJgN _ELyIpS _8Np 3
3 IBE8DggyN951CS ANSWERS -- DUAD CITIES 1&2
-86/09/15-HILLS, D.
ANSWER 5.01 (1.50)
Driving flow is provided to the jet pumps f rom the recirculation c.
pumps (0.5) while driven flow comes from the vessel downcomer region (dryer and seperator drair.s plus f eed flow). (0.5) b.
Driven Flow (0.5)
REFERENCE Quad Cities LIC-0202-1, p.
2,3.
ANSWER 5.02 (1.00)
Water rods allow water passage to help flatten neutron flux across a bundle, thus reducing rod to rod power peaking. (1.0)
REFERENCE Quad Ci ti es LIC-0201-2, p. 4,10.
ANSWER 5.03 (1.60)
Moisture carryover is the inef ficient removal of moisture (0.3) resulting from a high water Invel in the vessel. (0.2) Moisture carryover may damage the turbine or steam piping (0.1) and results in decreased plant efficiency (0.1).
It may also increase the radioactive level of the balance of plant. (0.1)
Moisture carryunder is steam f rom the seperators entrained in the downcomer flow (0.3), caused by a low water level in the vessel. (0.2)
It may cause decreased subcooling (0.1), resulting in a lower critical power (0.1) and /or jet pump or recire pump cavitation. (0.1)
(Will accept other adverse consequences with acceptable justification. )
REFERENCE Quad Cities LIC-0600, p.
2.
E PAGE SE THEgRY_DF_ NUCLEAR _ POWER _ PLANT _DPERATION _FLUIDg3_AND 2
5 IHEBdODYN@ digs
-96/09/15-HILLS, D.
ANSWERS -- QUAD CITIES 1&2 ANSWER 5.04 (2.00)
Increases Power (0.2) c.
Void Coefficient (0.3)
Increases Power (0.2) b.
Moderator Temperature Coefficient (0.3)
Doppler Coefficient (0.3) - Decreases Power (0.2) c.
d.
Void Coefficient (0.3) - Decreases Power (0.2)
REFERENCE Quad Cities Theory, p. 46-57.
ANSWER 5.05
(.50) b (0.5)
REFERENCE Quad Cities Theory, p. 28.
ANSWER 5.06 (2.00) a.
longer (0.5) b.
more (0.5) c.
End-of Life (0.5) d.
decrease (0.5)
REFERENCE Quad Cities Technical Specification 3.5/4.5 Quad Cities Thermodynamics, p.
17.
Quad Cities Theory, p. 28.
ANSWER 5.07 (1.50)
Increase due to lower core pressure drop.
(0.5) a.
b.
Jet pump flows are still summed even though the flow is reversed in ten of them.
(0.5) brace due to e::cessive To prevent damage to the jet pump riser c.
vibration when reversing the flow.
(0.5) l
(
l REFERENCE l.
Quad Cities LIC-0202-1, p.
24,25.
l Quad Citi es LIC-0202-2, p.
12.
l l
'e.
PAGE 19 5 __IH[ggy_gE_ggCLE@B_EQWE8_E(@NI_g[EB@llgN3_E(plDS _9ND 3
IMERdODYN@dlCS ANSWERS -- DUAD CITIES 1&2
-86/09/15-HILLS, D.
ANSWER 5.08 (1.00)
Steam flowing through the dryers is f orced to change direction several times, resulting in a pressure drop across the dryers.
This difference in pressure between these regions causes the difference in water level.
(1.0)
REFERENCE Quad Cities LIC-0263, p. 28.
ANSWER 5.09 (1.00)
Convert pressures in psig to psia (0.25) 364.7 psia 350 psig + 14.7 psi
=
800 psig + 14.7 psi = B14.7 psia Obtain corresponding temperatures from the Steam Tables (0.5) 364.7 psia = 435.5 deg F B14.7 psia = 520.3 def F Determine the temperature change for the hour (0.25)
(520.3 deg F - 435.5 def F)/ 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> = B4.8 deg F/ hour REFERENCE Steam Tables Quad Cities Thermodynamics, p.
10.
ANSWER 5.10
(.50) d (0.5) l REFERENCE l
Quad Cities Theory, p.
60,68.
4 l
l l
l l
t l
I
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i PAGE 20 5 __IMEQBY_QE_NMC6E96_EQNEB_E(gNI_gEEBellgdi_E6 Migs 2_9NQ IBE8cggyNen1Cg ANSWERS -- DUAD CITIES 1&2
-86/09/15-HILLS, D.
ANSWER 5.11 (1.50)
Steam bubbles generated by withdrawal of the rod are carried a.
upward through the remainder of the bundle causing increased void f raction and thus decreased power in the top of the bundle. (0.5)
Overall bundle power may actually decrease increase in depending on the relative magnitude of the power the bottom of the bundle and power decrease in the top of the bundle.
(0.5) b.
Shallow rods (0.5)
REFERENCE Quad Cities Theory, p.
62.
ANSWER 5.12 (1.00)
In case the reactor becomes more active sometime during core-lif e than it was at beginning-of-life (0.5) due to the burnout of gadolinia (0.25) and the buildup of Pu-239.
(0.25) l REFERENCE Quad Cities Theory, p. 74.
l l
l i
t
PAGE 21 0 __P(@NI_@l@lEdg_ peg 1GN2_CQN16961_QNp_idg16UNENIBIlgN
-86/09/15-HILLS, D.
ANSWERS -- QUAD CITIES 1h2 ANSWER 6.01 (2.00)
Five seconds is fast enough to prevent gross release of fission (0.5)
Three seconds is slow enough to c.
products to the environs.
o minimize the severity of the pressure transient resulting f rom an j
isolation.
(0.5) b.
Inboard - Drywell Pneumatic System (0.5)
Outboard - Instrument Air System (0.5)
REFERENCE Quad Cities LIC-0250-1, p. 22.
t ANSWER 6.02 (2.50) a.
(1)
Cold (0.5)
(2)
Cold (0.5)
(3)
Hot (0.5) b.
Yarways require no power supply for l oc al operation.
(0.5)
I GE/NACs are more accurate.
(0.5)
REFERENCE Quad Cities LIC-0263, p.
12-14.
ANSWER 6.03 (1.50)
Low nitrogen pressure (0.5) at less than 980 psig (0.25)
High Water Level (0.5) at greater than 37 m1 leakage past accumulator seal (0.25) l REFERENCE Quad Cities LIC-0281, p.
4.
ANSWER 6.04 (2.00) a.
Actuation (0.5) b.
No Actuation (0.5) c.
No Actuation (0.5) d.
Actuation (0.5) 4
PAGE 22 6t__EL6N1_SYSIEUS_ DESIGN _CONIB06,_9ND_1N@lBydENI@llgN 2
-86/09/15-HILLS, D.
ANSWERS -- QUAD CITIES 1&2 REFERENCE Quad Cities LIC-0287-1, Figure 1.
ANSWER 6.05
(.50) remain constant (0.5)
(Signal failure detector causes brake to lock the scoop tube in place below 1.0 mm)
REFERENCE Quad Cities LIC-0202-2, p.
12.
ANSWER 6.06 (1.50) c.
(2)
(0.5) b.
Reactor mode switch in "RUN" (0.5) or Range 1 (0.5)
REFERENCE Quad Cities LIC-0700-2, p.
14,20.
ANSWER 6.07 (1.00)
Overspeed Low oil pressure High Water Temperature Crank Time Limit (2 required - 0.5 pts. each)
REFERENCE Quad Cities LIC-4100-1, p.
B.
ANSWER 6.08 (1.50) 13 psig a.
Low cooling water pressure at stator inlet High water temperature at stator outlet - 95 deg C Stator cooling water low flow - 455 gpm or 98" water dp (2 required - 0.4 pts. each for signals 24 0.1 pt. each for setpoints) b.
Turbine Trip (0.5)
REFERENCE Ouad Cities LIC-53OO, p.
14.
Quad Cities DOA 5300-1
.f PAGE 23 0 __ Phen 1_@y@lEgg_QEgigN _CQN16g61_@NQ_lN@lBggENI@llgN 3
-86/09/15-HILLS, D.
ANSWERS -- DUAD CITIES 1&2 ANSWER 6.09 (1.00) in the downcomer is reduced to a sufficient volume to The level (1.0) prevent damage due to water hammer.
REFERENCE Quad Cities LIC-1600-3, p.
2.
ANSWER 6.10 (1.50) c.
Prevents water hammer from causing piping damage on system startups.
(0.5) into the reactor vessel (0.5)
Allows f or more rapid injection of water b.
Condensate Transfer System (0.5)
REFERENCE Quad Ci ties LIC-1400, p.
8,9.
i l
l l
l
PAGE 24 Zz__EBQCEQWBES_ _NQBd8L _8ENQBd863_EdE6@ENGY_8NQ 2
B00196991Geb_GQUIB96
-86/09/15-HILLS, D.
ANSWERS -- QUAD CITIES 1&2 ANSWER 7.01 (2.00) the f our bundle array.
The spring clips should be at the center ofspacer blocks should be located on The fuel channel cf the f our bundle array. orientation lugs on the handle of each f uel bundle should The fuel point toward the center of the four bundle array.The serial number on the four bundle array.
as identified by extended f uel rod end plugs, The gadolinia rod location, thould be correct.
There is cell to cell symmetry.
(4 required - 0.5 pts. each)
REFERENCE Quad Cities LIC-0201-2, p. 24.
ANSWER 7.02 (1.50) a.
increased (0.5) b.
decreased (0.5) c.
decreased (0.5)
REFERENCE Ouad Cities LIC-0202-1, p.
5.
Quad Cities DOA-202-6.
ANSWER 7.03 (1.00)
Pulling the f uel injector rack handle (0.5)
Closing the emergency fuel shutoff valve (0.5) justification.)
(Will accept other methods with acceptable REFERENCE Ouad Cities LIC-6600, p.
20.
Quad Cities DOA 6600-4
PAGE 25 Z:_,PB99E99BE@_;_NgBd@b3_@@yg60663_EdgB@ENgy_AND 60 Dig (gG1C96_CgNIBg6
-86/09/15-HILLS, D.
ANSWERS -- QUAD CITIES 1&2 ANSWER 7.04 (2.00) c.
200 psig (0.5)
- b4 * * < 4 - a l e le * " (8 + d b.
300 psig (0.5)
'^ *^ W6a tow p a *5a'*
~^
c.
d.
100 psig (0.5)
REFERENCE Cuad Cities QGP 1-1 ANSWER 7.05
(.50)
(0.5)
Do not allow reactor period less than 30 seconds to be sustained.
REFERENCE Quad Cities OGP 1-1, p. 5.
ANSWER 7.06 (1.00) not exceed 75 rem. (0,5)
Dose equilvalent to the whole body shall not exceed dose equilvalent to the extremities shall Additional 200 rems. (0.5)
REFERENCE Quad Cities ORP 1000-1, p.
30.
ANSWER 7.07 (2.00)
Dif f erential pressure not able to be restored and/or maintained below O in. of water.
An area temperature above its normal operating value.
above Reactor building ventilation system exhaust radiation level 3 mR/hr.
above its maximum normal oper ating val ue.
An area radiation level level above the building floor drain sump A and B water high water level alarm setpoint for greater than 15 minutes.
Reactor each)
(4 required - 0.5 pts.
REFERENCE Ouad Cities OGA 300-1, p.
1.
PAGE 24 Zz__EBgCggyBES_ _NQBM@62_@ENQBd@63_gdEBGENCy_@ND BOD 196QGIC@6_CQNIBQL
-86/09/15-HILLS, D.
ANSWERS -- QUAD CITIES 1&2 ANSWER 7.08 (1.50)
(1.0)
Imposes excessive loads on the turbine last stage buckets.
(no greater than Do not lower vacuum below 25 inches of Hg c.
b.
(0.5) 5 inches of Hg backpressure. )
REFERENCE Quad Cities QGP 2-1, p. 7.
ANSWER 7.09 (2.00)
Conditions Change (0.5)
Job Complete (0.5)
Job Cancelled (0.5)
Expired (0.5)
REFERENCE Quad Cities ORP 1000-1, p.
17.
3 i
ANSWER 7.10 (1.00)
I Reactor power greater than 20%
(0.5) 65 - 100*/. of rated core flow (0.5)
REFERENCE Duad Cities Technical Specification 3.3.F ANSWER 7.11 (2.00) lit.
Amber pil ot light of squib firing continuity circuit not Flow indicating pilot light lit.
Reactor water cleanup system isolation.
l Decreasing level of standby liquid storage tank.
fail annunciator light lit.
Standby liquid squib valve circuit indicate power reduction.
1 Reactor flun level instrumentation (4 r equired - 0.5 pts. each)
REFERENCE Duad Cities DDP 1100-2.
9 4
PAGE 27 l
Z:__EB99ED96gS_:_ugBde61_0269Bd862_EDE69EU9Y_eND 1
699196991G06_QQNI6QL
-86/09/15-HILLS, D.
ANSWERS
- QUAD CITIES 1&2 ANSWER 7.12 (1.00)
Water is drawn up into the relief valve discharge line f rom the as a vecaum is f urmed f rom steam condensation tuppression pool Opening a relief valve shortly fellowing relief valve closure.
of ter a previous operation would thus send a slug of water into resulting in possible structural damage.
(1.0) the suppression pool,
REFERENCE 2.
Ouad Cities DOA 201-10, p.
l l
- ^ ^ ' '
f PAGE 28 Ez__0951NISIB@ LIVE _P69CEgyBgg3_CQNpillgNS _@ND_(IdlI@IlgNE 3
-86/09/15-HILLS, D.
ANSWERS -- QUAD CITIES 1&2 ANSWER B.01 (1.00)
Increased voiding at higher power levels results in flattening of the Thus rod peak-to-average flux profile surrounding each control rod.
enthalpy upon worths are not high enough to exceed 280 cal / gram f uel o rod drop. (1.0) 1 REFERENCE Quad Cities LIC-207, p.4,6.
ANSWER 8.02 (2.00) o.
Control rod drives f ully inserted (0.5) and electrically disarmed.
(0.5) b.
Control rods can be moved with control rod drive pressure (0.5)
Specification 3.3.A.1 (Reactivity Margin) is met for each position of these rods (0.5)
REFERENCE Quad Cities Technical Specification 3.3 A.2 ANSWER 8.03 (1.00)
(1)
Shift Foreman (0.5)
(2)
Radwaste Foreman (0.5)
REFERENCE Duad Cities DEP 340-5, p.
2.
ANSWER 8.04 (1.50)
On a group 1 isolation the scram signal should come f rom MSIV closure b
(0.5)
Failure of the main steamline i sol ati on(0,5) and NOT steam line pressure.
valve closure scram may have allowed a saf ety limit to be viciated.
is Specifications prescribe that exceeding a safety limit unit shutdown and review by NRC bef ore resumption of Technical ccuse for a unit operation.
(0.5)
REFERENCE 1.0-4,1.1/2.1-15,6.4-1.
Technical Speci f i c ati ons, p.
PAGE 29 0:__ePDIUl!IBBIJyg_PBQQggyBgg3_ggNp}QNg3_@Np_LJdJIBIJ9N! -86/09/15-HILLS, D. ANSWERS -- QUAD CITIES 1&2 ANSWER 8.05 (.50) d (0.5) REFERENCE Technical Specifications, p. 3.4/4.4-1. ANSWER 8.06 (1.00) (1) 25 (0.5) (2) 3.25 (0.5) REFERENCE Technical Specifications, p. 1.0-5. ANSWER 8.07 (1.00) Alert (0.33) Site Emergency (0.33) General Emergency (0.33) REFERENCE Emergency Plan Annex QCA 6-1. ANSWER 8.08 (1.00) the is immediately needed to protect In an emergency when this actionand safety and no action consistent with license public health specifications that can provide adequate or conditions and technicalis immediately apparent. ( 1. 0) ' equilvalent protection REFERENCE 10 CFR 50.54(X) ANSWER 8.09 (1.00) For a period of time not to exceed two hours (0.3) in order to(0.3) duty shift crew members accommodate unexpected absence ofis taken to restore the shift crew on provided immediate action (0.4) to within minimum requirements. composition
\\ A PAGE 30 L.__8DUIN1516811ME_PBQCgpg85@2_QQtjp111QNgi_8NQ_(It!!I@IlgNg -86/09/15-HILLS, D. ANSWERS -- QUAD CITIES 1&2 \\ ) l REFERENCE Quad Cities Technical Specification Figure 6.1-3. ANSWER B.10 (1.00) the reactor At the higher steaming rate boiling causes deseration of (0.5) water, thus maintaining oxygen concentration at low levels. At lower steaming rates and thus with more oxygen present, a more restrictive limit is imposed to assure that chloride-oxygen combinations do not exceed that which causes stress corrosion cracking. (0.5) REFERENCE Quad Cities Technical Specifications, p. 3.6/4.6-19. ANSWER B.11 (2.00) li mi ti ng In the event of operation with a maximum f raction of power density (NFLPD) greater than the fraction of rated a. c o co. # s c@ re._, n,s.+..w /..f '-!.^F _ay im +-(( power (FRP). C L Oh ( L 'e w u c. f. ss w w.,e , cog ( w ta A ) --'i.M 4 ope %4 E* A Increasing the APRM gain by the inverse ratio McLPD/FRP.% + v b. G C ec.iu.cs% 9 I/su.-A%%,c.-+.fv+a.'s3(wwa m,w5wm+,f,4 w,,,%4 REFERENCE Quad Ci ti es DAP 300-2, p. 11. b c. a s f. s14c c : nac,3 pg,g ,,4443 Quad Cities Technical Specification 2.1.A b y 3. S~%. l I ANSWER B.12 (2.00) is physically within the operating area in f ront of a. Oper ator the unit panels. (1.0) levels and the pressure and temperature in the primary l b. Radiation containment are stable. (0.5) There is adequate core cooling as indicated by stable reactor (0.5) temperatures and levels. coolant system pra'ssures, REFERENCE Duad Cities DAP 300-2, p. 3,14. l l
STAKT'. 12t> j t. STe Pi IQ ; U. S. NUCLEAR RESULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITYs _GUAD__C,IT_IES_H2_________ REACTOR TYPE: _ M -ggg_________________ DATE ADMINISTERED _@gfq241g________________ EXAMINER: _ M ERWBYz_Bz___________ l CANDIDATE: ____h $L N_ b __________ r i INgIgygIlgNS_IQ_C8NQ1981El Rsad the attached instruction page caref ully. This examination replaces the current cycle facility administered requalification examination. R2 training requirements f or f ailure of this examination are the same as f or f ailure of a requalification examination prepared and administered by l y ur training staff. Points f or each question are indicated in pcrentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers f will be picked up f our (4) hours af ter the examinati'on starts. % OF CATEGORY % OF CANDIDATE'S CATEGORY __YeLUE_ _Igl@L ___SCQBE___ _y@LUE__ _____ _ CQIEGQBy______ 1. PRINCIPLES OF NUCLEAR POWER _1Dz99__ 2ezQ2 PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW i 1 / 1 15 45c2EC'_ _2Ez99 - - - 2. PLANT DESIGN INCLUDING SAFETY _ _ _ = - - AND EMERGENCY SYSTEMS L ________ 3. INSTRUMENTS AND CONTROLS l _15zZ5__ _25za2 $9__.26z32 ________ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL Totals _61z99__ Grade Final L All work done on this examination is my own. I have neither given nor received aid. ---~~--------- C;nsidate s Sign;ture l!. 9 i
f. 5 NRC RULES AND GUIDELINES FDR LICENSE EXAMINATIDNS During the administration of this examination the following rules apply Cheating on the examination means an automatic denial of your application 1. and could result in more severe penalties. Restroom trips are to be limited and only one candidate at a time may You must avoid all contacts with anyone outside the examination 2. 1 eave. [ room to avoid even the appearance or possibility of cheating. Use black ink or dark pencil gnly to f acilitate legible reproductions. 3. k 4. Print your name in the blank provided on the cover sheet of the examination. (if necessary). i in the date on the cover sheet of the examination 5. Fill f 6. Use only the paper provided for answers. Print your name in the upper right-hand corner of the first page of each 'I 7. l. section of the answer sheet. Consecutively number each answer sheet, write "End of Category __" as if write gnly gn gne side M O. appropriate, start each category on a new page, fj of the paper, and write "Last Page" on the last answer sheet. Vi 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least thrgg lines between each answer.
Separate answer sheets from pad and place finished answer sheets face 1 ~l
- 11. down on your desk or table.
")
- 12. Use abbreviations only if they are commonly used in f acility litgtatutg.
41 The point value for each question is indicated in parentheses after the 4., 13. answer required. question and can be used as a guide for the depth of -i assumptions used to obtain an answer
- 14. Show all calculations, methods, or to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. ask questions of If parts of the examination are not clear as to intent,
- 16. the gxamingt only.
You must sign the statement on the cover sheet that indicates that the work in your own and you have not received or been given assistance in S 17. completing the examination. This must be done after the examination has j j been completed. L 9 !,i 3
I
- 10. When you complete your examination, you shalla Assemble your examination as follows:
c. (1) Exam questions on top. (2) Exam mids - figures, tables, etc. Answer pages including figures which are part of the answer. i 9 (3) } Turn in your copy of the examination and all pages used to answer b. the examination questions. j Turn in all scrap paper and the balance of the paper that you did c. not use for answering the questions. If after Leave the examination area, as defined by the examiner. leaving, you are fcund in this area while the examination is still d. your license may be denied or revoked. in progress, il Y f l-N. i. 'i i e I !I i' l i i L {
\\ PAGE 2 l 1 __EBlyCIE6gS_gE_guC658R_E9Mg8_Eb9NI_gEgB9I19N2 IMEBU99XN9 Migs,_gEeI_IgegSEEB_689_E(Ulg_E69W i f GUESTION 1.01 (2.00) During your Shif t, an SRV inadvertantly opens f rom 100% power and 1000 Use a Hollier Diagram or the Steam Tables to answer the following psia. (ASSUME a saturated system and instantaneous heat transfer): assuming atmospheric pre'ssure ~ t WHAT is the SRV tailpipe temperature,and No Reactor Depressurization? j (0.5) a. in the Suppression Pool If the Suppression Pool Pressure were to increase, would the DECREASE, or REMAIN THE SAME7 (0.5) b. tailpipe temperature INCREASE, is depressurized when the SRV is opened, will the If the reactor Tailpipe Temperature INITIALLY INCREASE, DECREASE, or REMAIN THE c. (0.5) SAME7 At WHAT Reactor Pressure will the Tailpipe Temperature be at its(0.5) d. MAXIMUM value (during the depressurization)? l k QUESTION 1.02 (1.00) During the last ref ueling outage a center bundle was inadvertently bundle location. The reactor is then brought positioned in a peripheral (LARGER, SMALLER, or THE SAME) to Fill-in-the-blanks with indicate the correct response f or the ther mal hydraulic conditons in the to 100% power. h! misplaced bundle. The flow rate in the mispl aced bundle will be _____________ than the 4i (0.5) l a. adjacent peripheral bundles. j,} than in the misplaced bundle will be ____ The power level location.(0.5) j b. if the bundle had been properly placed in its central 4 1 1. I 5 i }s l -;l (- 4 l 8
- p. :1 t
CATEGORY 01 CONTINUED ON NEXT PAGE *****) (***** ~ d-----.
3 PAGE 3 4 11.__EBINQ1ELES_QE_NQQLE98_EQWEB_EL9NI_QEgB911gNa INEBUDDYN951GEa_UE9I_IB9NBEEB_9ND_ELUID_EL9W h GUESTION 1.03 (2.50) Ctate whether the following statements concerning fission poisons are TRUE I j or FALSE: i The largest production contribution of xenon is the radioactive j (0.5) a. i decay of Iodine. A 25% power reduction f rom 100% power would have a larger xenon l G36 b. (0.5) Ma' peak than a 25% power reduction from 50% power. } wyis.t
- WUd-A rapid reactor shutdown from 100% power would have the same (0.5) c.
resultant xenon peak as a reactor scram from 100% power. Since the production and removal of samarium is a direct function d. a reactor that has operated at DNLY 50% capacity of thermal flux, I will have the same equilibrium samarium concentration as one that I (0.5) ,i has operated at 100% capacity. Upon restarting the reactor f ollowing a 6-month outage, the samarium lll concentration will decrease to its 100% f ull power concentration. e. (o.5) (- ( ) QUESTION 1.04 (2.00) .i minutes f ollowing a reactor scram f rom 100% power, reactor power l Five (5) WHAT is the minimum IRM Range that ej in 15 on IRM Range 4 and decreasing. minutes later without violating any operational (2) you could go to two (2.0) SHOW calculation and EXPLAIN any assumptions made. f limits? L b. l H. ai 11 I l b i 3N CATEGDRY 01 CONTINUED ON NEXT PAGE *****) [1 (***** 21 ~ - - ---
PAGE O h__PglWCIP6ES_gE_UUCLE96_EgMEB_E69NI_9EEB9119% IHEBU9DYNedics,_UgeI_IBeNgE[B_969_E6Ulg_E690 ouESTION 1.05 (1.50) [ Answer the fallowing TRUE or FALSE Since the power response to an intermediate control rod is generally difficult to predict, it is more desirable to position the rod in a. (0.5) either a shallow or a deep position. lj It is not uncommon in a one (1) or two (2) nots WITHDRAWAL for the b. It void-related power decrease to be dominant (0.5) rod is withdrawn power DECREASE when a control Control rod worth INCREASES as moderator temperature or f uel (0.5) c. temperature INCREASES or void content DE.",1 TEASES. t t QUESTION 1.06 (3.00) Concerning Thermal Limits: (1) WHAT safety condition does limiting FLCPR to less than one (1.0) a. prevent? (1.0) l WHAT is the definition of MAPRAT? b. NFLPD is used in con. junction with FRP to ________1_________ or t (1.0) lt c. _________2________ to protect the core. i QUESTION 1.07 (3.00) Its capacity is 400 A cooling water pump is operating at 1800 rpm.which requires a power of 45 kw. 1 ) gpm at a discharge head of 20 pai (Show DETERMINE the following if pump SPEED IS INCREASED to 3600 rpm j lJ all work) (1.0) Pump capacity. a. g_l*. (1.0) .a sF C c '3 b. Discharge head. (1.0) I Pump power requir' ent. c. t Pl i.! (*a*** END OF CATEGORY 01
- )
J-
PAGE 5 2,___%9t!I_DEELEN__1EWQlt!Q_ggEgly,qN_Q_EtjEBQEKY_gYgIEt!g GUESTION 2.01 (2.25) With regard to the recirculation system, list the expected indications from the system instumentation f or the f ollowing f ailures of the recirculation i pumps (0.75) Failure of the No. 1 seal only. a. (0.75) b. Failure of both (No. 1 & 2) seals? (0.75) Plugging of the No. 2 internal restricting orifice. J c.
- i
. q, d j' QUESTION 2.02 (1.00) as necessary, to answer the following questions i Use the attached Figure 5, d cbout the Rod Worth Minimizer TRUE or FALSE: J and the latched group is Group 10. The reactor is being shutdown, 10, an If a rod in Group 8 is selected and is inserted to position 1 a. (0.5) INSERT error will be displayed. The reactor is being shutdown, and you are below the LPSP when a You are still able to insert a rod if b. third insert error is made. (0.5) ' i it had a withdraw error associated with it. ' I. i QUESTION 2.03 (2.00) What are four (4) methods or ai -h;; king' fuel orientation when (2.0) anal stage during refueling? fuel is positione , i. i i b, F, s CATEBORY O2 CONTINUED DN NEXT PAGE *****) (*****
PAGE a 21.__E69NI_ DESIGN _lMCLUDIUg_S9 Eely _9dD_gNERgENCy_QygI[Mg QUESTION 2.04 (3.00) The HPCI system started on a valid initiation signal but subseqently The isolation c. received an isolation sigr.a1 f or high area temperature. is cleared and you are directed to reset the system isolation. ignal 4,p;~,'What DIFFERENCE. if any, would you expect in automatic system LINE-UP initiation signal is still present? (*;4. depending on whether or not the 4 y-(1.0) b. A LOCA has occurred and HPCI initiated, operated, and tripped on high level. Level is now 37 inches and decreasing. ASSUME THAT DRYWELL PRESSURE DOES NOT EXCEED THE TRIP POINT ,y-l d s 4 * M (1.0) i t 01. Will HPCI auto start? If so, when?
- f g4 What steps are necessary to manually start HPCI?
(1.0) 2. y pdl. a e 'l QUESTIDN 2.05 (3.00) g while Explain how AND why a complete loss of the instrument air system, operating at f ull power, with no operator action, would af f ect the following plant parameters or components. (0.75) n. Main condenser vacuum. (0.75) l; b. TBCCW operation. (0.75) c. Main Steam Isolation Valves. j; ii i (0.75) p) d. Control Rod position. fI.IiiII il QUESTION 2.06 (1.00) Use Attached Figure # 6 to answer the followings i the Main Turbine has just been placed l l' Reactor power is at
- 20%g As power is increased up to 40%, the #3 Control Valve on the grid.
remains Full Shut (and unnoticed by the operators). This is due to mechanical binding in the valve. [ Include in your DESCRIBE how EHC will respond to this malf unction. l l response any protective trips which would/would not be generated f (1.0) within RPS, due to the above malf unction, and the reason why. i b4 .t., fII (e**** CATEGORY O2 CDN11NUED DN NEXT PAGE *****)
- l
PAGE 7 Et__EL9NI_pggl@N_lNGLUDIN@_g@EEIY_9NQ_EMEB@gNQY_SYSIEME GUESTION 2.07 (1.00) OTATE the interlocks associated with the Normal and Reserve Feeder Include in your response the purpose of each interlock. (1.0) to a RPS BUS. s. O E QUESTION 2.08 (2.00) (a - d), indicate whether it describes 1: For each of the f ollowing items If it does not, describe how the proper system response or not. discussed event should occur. occurs in the CCST. With the RCIC system operating, a low level (RCIC-MO-22) closes and the a. The pump suction from the CCST (RCIC-MD-25 & 26) then pump suction from the suppression chamber
- i (0.5) open.
increasing. The RCIC system is operating with reactor level When the high level setpoint is reached, the steam supply b. (RCIC-MO-16 k 17) close. (0.5) inboard and outboard isolation valves The RCIC system is operating in the TEST mode, discharging A valid low reactor level initiation signal is J c. to the CCST. the The test circuitry is automatically bypassed, received. test bypass to CCST closes, and the flow controller controls (0.5) h RCIC flow automatically. With the RCIC system operating, a high area temperature isolation this The following valves close as a result of 1l d. is generated. ft signal Steam supply inboard and outboard isolation valves (RCIC-MO-16 and 17), the minimum flow valve (RCIC-MO-60),_the RC C. I e; event: (RCIC-MD-4S). and the injection valve (RCIC-MO-49) pump discharge valveThe above listed valves are not the only valves that are DO NOT NOTE: EVALUATE DNLY THE VALVES LISTED. affected by the isolation. (0.5) j _,i ATTEMPT TO COMPLETE THE LIST. l., l 4 l ..j 1 y, tn\\ ..:,) sf t
- 2;j END OF CATEGORY O2 *****)
(***** "~ - - - - -~.
PAGE O L.__INSISWENIS_AND_C9NIgg6S ouESTION 3.01 '(1.50) For the f allowing SRM output. trips, distinguish which will AUTO reset and which require MANUAL reset: MM ~ (CLe-s i s k ; ( <t. (.S s. P*t c Ak pl. Av.4 -st.O L 1. Upscale High ke. u d;&(, a3 S o colth. 4 2. Period 14, b -. t 3. Inop. bmg m, t 4 f 7(3.;,ug, -k 1-tIa t: 1 4. Downscale C D - A o Ann. 5. Retract Permit (1.5) 6. Upscale High High I i QUESTION 3.02 (1.75) N The Recirculation Flow Control System has a liniter that prevents damage i< to the recire pump by limiting its maximum speed during certain plant je l? I conditions. Answer the followings plant conditions and the corresponding type of f! (2) List the two adverse consequence that would occur if the limiter f ailed to a. (1.5) function. (0.25) What is the maximum speed allowed by the limiter? b. 1: ; I. fi ll, QUESTION 3.03 (2.00) h The plant is operating at 45% power when you notice that the "A" level rod (centrally located) is operating LPRM f or the selected control Your review indicates that this LPRM is assigned to APRM Fl1 erratically. the following additional conditions state what AUTOMATIC 1 Channel 5. For fie, SCRAM, HALF-SCRAM, ROD BLOCK, NO ACTION, etc.) actions, if any, would occur if you bypass the above LPRM and what is the root cause of the actions p g ep APRM Channel 5 currently has th ther OPERABLE LPRM's inputting to j a. For the LPRM's in the fo '-rod display the following L it. 2 "A"
- level, distribution of already INOPERABLE LPRM's exists:
(1.0) l 1 2 "B" level, 1 "C" level, and 2 "D" level. APRM Channel 5 currently has 13 other DPERABLE LPRM'S inputting to b. For the LPRM's in the four-rod display the f wing it. " l evel, distribution of already INOPERABLE LPRM'S exists (1.0) 2 "B" level, 2 "C" level, and 1 "D" level. 4.jL A %._ ( L :. !V} ! B. CATEGORY 03 CONTINUED ON NEXT PAGE *****) t~! (***** d ~. ---. -
l PAGE 9 L.__1HEIBWENIE_gND_GQUIBQLH } GUESTION 3.04 (3.00) Both Both Unit 1 and 2 are at 100% power and NO ECCS conditions exist. of the 1/2 DG ouput breaker control switches are in the OFF position. Include Describe the response of the 1/2 DG to the following conditions. (13-1 & 23-1), in your answer the status of the Unit 1 and 2 feed breakersstatus and which bus the bus (13-1 & 23-1) j Your answer should be given in the sequence in which it occurs. l 1/2 DG. ASSUME THAT DG'S 1 AND 2 OPERATE AS DESIGNED AND THA ACTIDN. (1.0) m. Unit 1 experiences a complete loss of normal power. j above, Unit 2 experiences a simultaneous loss of b. Subsequent to a, (1.0) normal power and a LOCA. (1.0) Unit i experiences a LOCA. 11 Subsequent to a and b, above, c. QUESTIDN 3.05 (3.00) (1.0) What are 4 conditions that can cause a scoop tube lockout? l a. (1.0) What must be done to reset a scoop tube lockout? f b. (1.0) How can the MG set speed be changed when a lockout is present? (- c. i I, l l QUESTION 3.06 (1.00) Which of the following are TRUE concerning the Standby Liquid Control (1.0) i Systems (CHOOSE ONE) In the event a remote (outside control room) reactor shutdown is required, SBLC injection can be actuated by the local pump START Ii a. lj i* switch. The pumps may be operated simultaneously if necessary to shutdown !i b. lI the reactor in an ATWS. N l If injected, the SBLC system will provide at least a O_'9M EEWt c. l Il 5 6 % and SOO6~ ppm boron concentration in the reactor vesse. Goo Nitrogen-charged accumulators assure adequate suction pressure d. for the pumps. (e**** CATESDRY 03 CONTINUED DN NEXT PAGE
- )
PAGE 10 h__1HEIBLJd![NIg_gt!D_CQt!IB%S i GUESTION 3.07 (1.50) (if any) will occur DIRECTLY from MSIV Ctate what specific RPS action (1.5) position if the f ollowing main steam lines shut in the RUN modes Lines B, C, and D. a. b. Lines B and C. I Lines A and B. c. OUESTION 3.08 (2.00) J systems or places to which the Rod Position Information f' What are five (5) (2.0) Cystem (RPIS) provides position information? 4 i i ?. i. .I t l 6 !. l t 1 1 I ) i l.I (!'l (***** END OF CATEGORY 03 *****) I' '> I
PAGE 11 h.__M9GEDlJBEH _:_t!985% 2_e!PJ985& a _EMEB9Et!GY _eND 68 DIE 991G% _GQNIgh GUESTION 4.01 (1.50) Answer tka followings Since an 18 year old's accumulated occupational dose (lifetime) [ is O (SEN-183 = 0) why can an 18 year old be exposed to radiation a. ?' on the job and what is his/her quarterly limit per 10CFR207 (1.0) (0.5) BRIEFLY explain the difference between a " rad" and a "res". b. i 2ii QUESTIDN 4.02 (2.50) ic entry conditions with their respective setpoints for List the five (5) (2.5) Q4., QGA 200-1, Suppression Pool Temperature Control. Oud.Jp(4btittic, QUESTIDN 4.03 (1.00) In accordance with QRP 1000-1, Personnel Exposure Under Emergency ll Conditions, what are the two (2) dose limiting recommendations involving (1.0) t a life saving action? ll t h QUESTION 4.04 (1.00) when the procedure for ~ placement of plant l List two (2) exceptions t jumpers and block 300-12, does not have to be followed. (1.0) I
- p caws %.s to.ud.
f' f'I QUESTION 4.05 (3.00) i List the six (6) items you are required to You are the oncoming NSD. l perform at a minimum by GAP 300-7, Shift Change for Nuclear Station i' Operators. (3.0) 1 I e I ia i e e f (e**** CATEGDRY 04 CONTINUED ON NEXT PAGE *****)
l PAGE 12 is.__ PROCEDURES - NORMALg_AB gRM % i_EMERGENQY_A @ BBQ196Q91E & _GQ!!IBQL GUESTION 4.06 (1.50) DGP 2-1 " Normal Unit Shutdown" cautions that vacuum breakers should not be opened to slow the main turbine unless it is necessary to quickly c. reduce turbine RPM. What adverse consequence results from using this (1.0) method? If it does become necessary to quickly slow the main turbine as in b. the case of excessive vibration, what vacuum limitations would be (0,5) imposed on use of the vacuum breakers? QUESTION 4.07 (1.50) QOP 1100-2, Injection Of Standby Liquid Contor1, lists five (5) INITIAL List three (3) of these. ways of verifying that the system is injecting. (1.5) i-i QUESTION 4.08 (1.50) I DDA 1600-2, Loss Of Primary And/Dr Secondary Containment, lists four (4) List three (3) cymptoms that a loss of primary containment has occurred. (1.5) I of these. i. hl a. li ' l: ; f i i 1'1 i I i i I l (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) l, j -- ~..
PAGE 13 is.__EBQGEQWBEE_:_t!QBUh_8RHQBuh_EMEBGENGY_8NQ 8801%QQ1G& _GQNIBA i GUESTION 4.09 (1.50) i OOA 1300-5, Restoration Df Power To The RCIC Vacuum Pump And Condensate Pump Utilizing Opposite Unit Power Crossties, describes how power to a l disabled RCIC condensate pump may be restored by placing both unit's condensate pump control switches in PULL TO LOCK, positioning the disabled pump source side transfer switch in the RCIC pump room to STOP and the and positioning the opposite unit's load side load side switch to CROSS, switch in the RCIC pump room to STOP and the source side switch transfer to CROSS. With this electrical lineup in effect, answer the following TRUE or FALSE: The RCIC condensate pump with the restored power can be operated
- a. from its unit's LOCAL-REMOTE control switch.
(0.5)
- b. The RCIC condensate pump will still cycle on Hi/Lo level.
(0.5) start
- c. Placing the appropriate LOCAL-REMOTE switch in REMOTE will the pump and placing it in LOCAL will stop the pump.
(0.5) A li u [j u!q o ,i
- I')
a '1l1 oI t lb! i.:e (***** END OF CATEGORY 04 *****) ] h fir 5D fD @X AMINAT I ON * * * * * ** ** * * * * ** )
-u a_. j O l l. cy i l7 g l I- ~~ '= ~ i. l. L = -l m a 4 .-m a .-m., l .is i l l l g. A O,. .-,2 M l l la w l. si l w,s .-m ,i l l ~ p l u l l ~ l E i F: renes. ce, tass nes.srssousue N i i
e lil lll11111 til i i ,i; a; ~ ! 'k ii!l,llltd AI ~" ,i,= = = = = = l ,,,,i:; m i 5 i '=$a"== l i " ?,jl _gaI M g
- I4 g%dri.
i HTil 1 ,I _g [Kt y 2 g,'D,5 O 15!!I a i R llls f R -la -l,a (a MT M 'ay ~ -i < 1
== f;l-[*kIII"hljiisigeimsi!- nL p ii
EQUATIONSHEET @ le efficienc o (Network y a s/t m )/(Ene w in f = ma s = Vot + 5 att w = ag E = ac2 A=AN A = Q At RE = 5 av2 a = (Vf-V,)/t PE = agh A = an2/tt = 0.693/t5 4 j Vg = V, + at w = e/t W = -6 tgeff = [(tg) (t Il b [(t ) + (I )2 5 b aE = 931 am g, 9-Ex i=a(pat I = Ic *
- e 4 = UAst I = Io 10~*/UL Fwr = Wrah TVL = 1.3h 5M W L = -0.693A P = Po10 j
P = Ppt /T SCR = S/(1 - Keff) SUR = 26.06/T CRx = S/(1 - Keffx) SUR = 26p/2* + ( s-p )T CR;(1 - Keffg) = CR (1 - keff2) 2 M = 1/(1 - Keff) = CRt/CRo T = (1*/p) + [(8 - p)/Ip3 M = (1 - Keffo)/(1 - Keff t) l ' 'T = t/(p - s) SOM = (1 - Keff)/Keff I . T = (a - p)/(4 ) 2* = 10-5 seconds p = (Keff-1)/Keff = AKeff/Keff I = 0.1 seconds-1 + l p = [(a /(T Keff)] + [s ff;/(1 + IT)] e 'I dt = 1 d22 t 2 f P = (reV)/(3 x 1010) Ildt 2=1d22 2 R/hr = (0.5 CE)/d (meters) !f I = =N R/hr = 6 CE/d2 (feet) d Miscellaneous Conversions fi Water Parameters 10dps 1 curie = 3.7 x 10 i. 1 gal. = 8.345 lbs. 1 kg = 2.21 lhe 1 gal. = 3.78 liters 1 hp = 2.54 x 10 Btu /hr 3 1 ft3 = 7.48 galt.' 1 sw = 3.41 x 106 Btu /hr i ;. Density = 62.4 lbs/ft 1 in = 2.54 cm Density = 1 ge/cm3 lf Heat of vaporization = 970 Btu /1be
- C = 5/9 (*F-32)
'F = 9/5'C + 32 Heat of fusion = 144 Btv/1bs 1 BTU = 778 ft-1bf
- j 1 Ata = 14.7 psi = 29.9 in. Hg.
1 ft H 0 = 0.433 Ibf/in2 2 j l
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- 4
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- ,a
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PAGE 14 1 PRINCIPLES OF NUCLEAR POWER PLANT DPERATION2 IMEBgggyN951CS _BE8I_IBONgEg8_8NQ_ELU1g_ELQW 3 ANSWERS -- QUAD CITIES 1&2 -86/09/15-LANKSBURY, R. 9 ANSWER 1.01 (2.00) c. 295 degrees F (+/- 5 degress F) i b. Increase I c. Increase i d. 450 psia (+/- 25 psia) 5 REFERENCE Steam Tables /Mollier Diagram, and Quad Cities Thermodynamics Training Manual. a a if ANSWER 1.02 (1.00) o. Small er (2 phase flow larger due to higher power, orifice fixed) [! \\,' b. Small er (2 phase flow larger due to smaller orifice) 1; REFERENCE Quad Cities Theory Training Manual. 'I ANSWER 1.03 (2.50)
- t Si c.
True b. True I c. False i d. Trua O. True i L REFERENCE L Quad Cities Theory Training Manual. H I { t il s
PAGE 15 1,.__EBINGIE6Eg_gE_tNQ6E98_EgMEB_E(9NI_ggEB911gN2 IHEBUGQYN951G94_HEBI_IBBNSEgB_gMQ_E(ylg_E69W -86/09/15-LANKSBURY, R. ANSWERS -- QUAD CITIES 1&2 e i ANSWER 1.04 -(2.00) Using P = Po eve (t/T) [0.253 15 e**(-120/go) = .j = 3.35 on Range 4 [0.253 = 33.5 on Range 1
- I Therefore Range 1 is the lowest Range [0.53.
Dn a down power transient, with large negative reactivity ll Assumpti ons: insertions, the stable decay period is determined by the longest lived half-life IO.53. For this example, it is i assumed to be -80 seconds CO.53. s, REFERENCE Quad Cities Theory Training Manual and LIC - 0700-2. ANSWER 1.05 (1.50) a. True b. True c. False REFERENCE l Quad Cities Theory Training Manual. I ii j ANSWER 1.06 (3.00) 't Avoid boiling transition. i m. 'i l b. APLHGR/APLHGR limit. 1 I c. 1. increase gain of the APRM's reduce the scram and rod block setpoints 2. (2 0 0.5 each) i 4 l1 I REFERENCE Quad Cities Thermodynamics Training Manual. l; I l' I l-c i 9 E -~~-, ,,n -_.-~.,---,,----,,,,y- ,-----nn n.,
PAGE 16 1___EB1991ELES_gg_Uyg6E98_PQWEB_E(BNI_gEEB@llgN3 IBEggggyuenigg,_Ug@I_IseNSEEg_969_g6Ulp_gbgW ANSWERS -- QUAD CITIES 1&2 -86/09/15-LANKSBURY, R. / ANSWER 1.07 (3.00) Where V is new flow rate and V = 2(v) c. v is flow rate prior to speed l V = 2(400 gpm) change. j i (1.0) V = BOO gpm i b. H= (2E (h) Where H is new dischg. head and h is head prior to speed H= (4) (20 psi) change. A (1.0) H = BO psi 1. !e P= (2f (p) Where P is new power requirement c. and p is power prior to speed P= (B) (45 kw) change. (1.0) P = 360 kw REFERENCE Quad Cities Thermodynamics Training Manual. 4 9 + i I ? .i i 1i 'i .i .i-4 Y t o i t i I
PAGE 17 Ez__EL9NI_DEE19N_INGLUDINE_B8EEIY_9ND_ENEBEENGY_EYEIENE -86/09/15-LANKSBURY, R. ANSWERS -- GUAD CITIES 1&2 ANSWER 2.01 (2.25) D:%~ t No. 2 seal pressure would approach No. 1 seal ressure [s.??53. (Lrr' ;- 5 c. i.i gpm EO.3752-th-" O cri' ice seld se iv .yy, vn. WhW would approach 60 gpm as limited b. Total leakage out of the seal assemb1ressure in both seals would drop by the breakdown bushing CO.375. (No. 1 pressure might not depending upon magnidtude of failure [0.3753 drop significantly unless f ailure were large). No. 2 seal pressure would approach No. 1 seal pressure IO.X753.
- c. (Controlledleakagewouldapproachzero):0.3751.
REFERENCE Quad Cities LIC - O202-1. .i .i ANSWER 2.02 (1.00) c. False b. True REFERENCE Quad Cities LIC - 207. i ANSWER ,2.03 (2.00) g l ( Any 4 below e 0.5 ea. ) e control cell. - Spring clips are at the center of I - Gadolinia rod location (exten fuel rod end plugs) should be correct. can be read from the center of the control - Serial # on the f uel hand i cell. tons are adjacent,to the control rod blades. - The channel spacer ell symmetry. - There is cell-to n lugs on each lifting handle point toward the center of i - Fuel orientat j the contro cell. REFERENCE Quad Cities LIC 0201-02. Il : i
PAGE 10 22.__EkeNI_DE_gigM_1EWD1MG_geEEILgND_EMRGENCLMSIEt!S ANSWERS -- GUAD CITIES 1&2 -86/09/15-LANKSBURY, R. ANSWER 2.04 (3.00) o. The steam isolation valves (2301-4, 5) will auto open only if the initiation signal is still present. b. 1. The system will automatically restart when level decreases to the initiation setpoint C1.03. 2. The high level trip signal may be reset, the injection valve (2301-B) opened, and the block motor speed changer push button depressed [1.03. REFERENCE Duad Cities LIC - 2300-1 & GDA 2300-1. I ANSWER 2.05 (3.00) c. Decrease (0.25) due to loss of steam supply to SJAE (0.5). b. TBCCW pump trip (0.25) due to low suction pressure as the expansion tank level decreases with time (no makeup to tank) (0.5). Outboard MSIV's drift closed (0.25) as accumulators discharge (0.5). c. d. Rods indiscriminate 1y scram (0.25) as scram valves open under spring pressure (0.5). .i REFERENCE j Quad Cities LIC - 5450, 3700-1, 0250-1, and 0300-2. ] . ANSWER 2.06 (1.00) l l The # 1, 2, & 4 CV's will pick up the load f or the #3 CV. They will open .-l further to allow the apropriate steam flow to maintain reactor pressure at the proper level [0.53. There will be no protective trips within RPS } since the CV Scram is based on hydraulic pressure decrease which is not hj occuring in this instance [0.53. REFERENCE If Quad Cities LIC - 5650-2. b -1 l l .,i > ~ - - ~.
PAGE 19 2t__hkeNI_QESl@N_LNQ(QQ1NQ_g8EEIY_8NQ_EME8@gNQY_EYEIEd@ ANSWERS -- QUAD CITIES 1&2 -86/09/15-LANKSBURY, R. ANSWER 2.07 (1.00) i Apts.% 1) Both Reserve breakers can't be closed at the same time (0.25) (0.25) to prevent powering both RPS buses f rom the same power supply. ,,4 .; 3 ;.u-u a 2) The Normal and Reserve breakers f or the same RPS bus can't be closed simultaneously (0.25) to prevent paralleling an RPS MG Set with the Reserve power source. (0.25) i REFERENCE Quad Cities LIC 0500-1. .1 .0 ANSWER 2.08 (2.00) Il o. No, the torus suction valve opens first, then the CCST suction
- i valve shuts (0.5).
b. No, the turbine steam supply block valve (RCIC-MO-61) shuts (0.5). c. Yes (0.5) d. No, the discharge and injection valves (RCIC-MD-48 & 49) do not close on an isolation (0.5). REFERENCE \\.j Quad Cities LIC - 1300. l t i ~
- l. i i
- t h
oi i U
PAGE 20 L.__ t!SIggt!Et!IS_gt!D_CONigDLB ANSWERS -- QUAD CITIES 18 2 -86/09/15-LANKSBURY, R. ANSWER 3.01 (1.50) 1. Manual 2. Manual 3. Auto 4. Auto 5. Auto 6. Manual (6 G O.25 each) REFERENCE Quad Cities LIC - 0700-1. ANSWER 3.02 (1.75) c. - Feedwater flow must be > 20% [0.253 to prevent pump cavitation [0.53. - Recirc discharge valve must be full open CO.253 to limit the axial thrust on the recirc pump [0.53. b. 30% REFERENCE Cuad Cities LIC - 0202-2. M @% A ANSWER 3.03 (2.00) HALF-SCRAM [0.53 caused by APRM Channel 5 having fewer than 1 perable .l' O. LPRM's CO.53. b. ROD BLDCK [0.53 caused by RBM 7 having fewer than 50% (4) of the i avail ble LPRM inputs CO.53. l REFE F M ).. Quad Ci ties LIC - 0700-3 and LIC - 0700-5. i 8 l: l 1 I
PAGE 21 L.__INSIBLJ!gNIS_gND_CgNIB969 ANSWERS -- QUAD CITIES 18t2 -86/09/15-LANKSBURY, R. ANSWER 3.04 (3.00) y ln-d % ke~er*M> (13-1) breaker
- o. A DG 1/2 starts and comes up to speed and voltage, bus closes, DG 1/2 is feeding bus (13-1), to lu-O bed.- mN oge=,
b. Bus (13-1) breaker trips open, bus (23-1) breaker closes, DG 1/2 is a feeding bus (23-1) and bus (13-1) is deenergized. DG 1/2 bus (23-1) breaker trips open, DG 1/2 bus (13-1) and bus (23-1) c. are both deengergized and DG 1/2 runs unloaded. REFERENCE Quad Cities LIC - 6600. ANSWER 3.05 (3.00) (Any 4/5 below G O.25 ea. ) c. - High coupling lube oil temperature. - Function generator signal failure. - Low lube oil pressure (16 second time delay). - Low voltage on the MG set motor supply bus. - Loss of power to the scoop tube positioner. Match the speed demand and actual NG set speed [0.53, then depress b. manual reset push button CO.53. Speed can be changed manually [0.?53 with a locally operated handcrank i c. at the scoop tube positioner motoi- [0.53. i r. REFERENCE i Quad Ci ties LIC - 0202-2. !i ANSWER 3.06 (1.00) C.' t REFERENCE Quad Cities LIC - 1100. ) 1 4 D e 9 i
PAGE 22 2___INSIggdENIS_QUQ CQNIggLE ANSWERS -- DUAD CITIES 1&2 -96/09/15-LANKSBURY, R. ANSWER 3.07 (1.50) o. Full scram b. None c. Half scram REFERENCE Quad Cities LIC - 0500-1. s 5 ANSWER 3.08 (2.00) b Any 5/6 0 0.4 em. Full Core Display Process Computer Four Rod Display Rod Select Logic RWM Drift Circuitry (odd reed switches) REFERENCE Quad Cities LIC - 0281. i 1 k ? I I ll l1l' l} lI i I l !!II 1< l l: .i 8 j '
PAGE 23 it__EBQGEQWBEE_ _NQBd@(g_8HNQBd@(i_EME8@gNQY_8NQ BeQ1QLQQ1996_GQNIBQL -86/09/15-LANKSBURY, R. ANSWERS -- QUAD CITIE3 1&2 ANSWER 4.01 (1.50) c. Because 5(N-18) only applies if an individual is going to exceed 1.25 rem /qtr. Quarterly whole body limit = 1.25 rem. (2 e 0.5 each) The rad is a measure of the energy released in tissue by ionizing effect caused b. radiation whereas the rem is a measure of biological by that energy. REFERENCE 10CFR20.101 4 ANSWER 4.02 (2.50) 1. Suppression pool temperature > 95 F. 2. Drywell temperature > 180 F. 3. Drywell pressure > 2.0 psig 4. Suppression pool water level > +2.0 ". 5. Suppressicn pool water level < -2.0 ". (5 4 0.5 each) REFERENCE QGA 200-1. 'l s I ANEWER 4.03 (1.00) I i
- 1. Dose equivalent to the whole body f 75 rem.
1 Additional dose equivalent to the extremities f 200 rem. 2. i (2 e 0.5 each) 1 I REFERENCE i QRP 1000-1. I 4i i 4 l t i ~, h
- i
- L
PAGE 24 4,r __P., Bgg [QUBg]_;_MQBd@bs_QEMQBdQ6t_EDEB@E,MQY,_@NQ B021969 GIG 86_QQNI6Q6 ANSWERS -- QUAD CITIES 1&2 -86/09/15-LANKSBURY, R. 0 JA' Jt-ANSWER 4.04 (1.00) ~
- 1. When the temporary alteration is part of an DOS request and is urned to normal when controlled as part of the DOS program and is the DOS is cleared.
I
- 2. When the temporary altera n is part of an approved procedure which i
returns the system to nor upon completion.
- 3. When the tempor y alteration is required to meet a Technical Specification iun Requirement which has previously been onsite reviewed an approved.
l (2 e each) REFERENCE QAP 300-12. I ANSWER 4.05 (3.00)
- 1. Obtain current operational status of the unit.-
Obtain any inf ormation on general plant operations that will be, 2. useful to the shift.
- 3. Read and initial the log from the previous 4 shifts...
6
- 4. Be sure you are aware of any abnormal operating conditions prior i
to accepting the position. i l alarm boards and get reason why any alarms are up.i. 5. Scan the panels' ,l Ii
- 6. Know what major equipment has recently been taken DOS and why.,
l! (6 0 0.5 each) i REFERENCE i l QAP 300-7. t 't ll I ff ANSWER 4.06 (1.50) Imposes excessive loads on the turbine last stage buckets. (1.0) a. H~ b. Do not lower vacuum below 25 inches of Hg (no greater than 5 inches of Hg backpressure.) (0.5)
PAGE 25 Oz__ PROCEDURES - NORMAL _AgNQRMAL _EMER@ENQy_ANQ 2 3 89EIDLQ91G86_GQNIBQL ANSWERS -- QUAD CITIES 1&2 -86/09/15-LANKSBURY, R. REFERENCE Duad Cities QGP 2-1, p. 7. E r. ANSWER 4.07 (1.50) ' ~ . Amber pilot light of squib firing continuity. circuit not lit. 1. ~~ ~ 2. Flow indicating pilot light lit. 3. RWCU system isolation. 4. Decreasing level of the SLC storage tank. 5. SLC squib valve circuit f ail annunciator light lit. (3 e 0.5 each) b REFERENCE GDP 1100-2. ANSWER 4.08 (1.50) 1. Increase in drywell oxygen content. ~ 2. Increase in nitrogen makeup flow. Area radiation monitors annunciating. 3. the During a primary containment isolation valve operability check, 4. containment could be found without integrity due to a valve failure. .i (3 0 0.5 each) REFERENCE (. QOA 1600-2. l l' l? ANSWER 4.09 (1.50) i
- c. False b.
False ,. c c. False i! REFERENCE QOA 1300-5. ll l m _m ,,,.,, _ - _,..,. _..,,}}