ML20235T689
| ML20235T689 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/30/1987 |
| From: | Casto C, Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20235T651 | List: |
| References | |
| 50-261-OL-87-01, 50-261-OL-87-1, NUDOCS 8710130177 | |
| Download: ML20235T689 (65) | |
Text
ENCLOSURE 1
-)
EXAMINATION REPORT 261/0L-87-01 Facility Licensee:
Carolina Power and Light Company P. O. Box 1551 Raleigh, NC 27602 Facility Name:
H. B. Robinson Steam Electric Plant Facility Docket No.-:
50-261 Written examinations and operating. tests. were administered at H. B. Robinson near Hartsville, South rolina.
Chief Examiner:
XA [m bk 7-/5~ - O Cha es A.
asto
Date Signed
[
/
30 Y' Approvedby:k,JohnF.Munro,SectionChief h
Date Signed Summary:
Examinations on August 11-14, 1987.
Operating tests were administered' to six candidates; five 'of whom passed.
Six candidates were ~ administered written examinations, all candidates passed.
Based on the' results described above, five of six R0s passed.
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%A *So!IA SNh f V
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. REPORT-DETAILS I
1.
-Facility Employees Contacted:
J. M. Curley, Director Regulatory Compliance R.~ Allen,' Project Specialist l
H. Young, Directnr QA/QC l
I W. Blaisdell,' Senior Training' Specialist D. Neal. Senior Training Specialist l
l
. E. M. Harris, Jr., Director DNS A. McGilvary, Specialist Operator Training J. Harness,-Manager - NTS 2.
Examiners:
~
- C Casto M. Ernstes
'* Chief Examiner-
- 3..
Examination Review Meeting j
At the conclusion of the written examinations, the examiners = provided Steve Allen, with a copy of the written examination -and answer-key for review.
The NRC Resolutions to facility comments. are listed below.
R0 Exam Question 2.02 b Agree. Answer key was in error and changed to "the VCT".
2.14 b Agree. Facility recommendation is the intended interpretation of the answer key.
2.15 Agree. Answer key changed.to include "CVC-358 from RWST" as possible answer. Also LCV-115D changed to LCV-115B.
2.16 Agree. " Blocked for 30 sec." is not a required part of the answer.
2.20 Disagree. Question is IAW reference material which the-l candidates were trained on..
During exam, candidates were l
instructed to include any assumptions with their answer.
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"No' automatic actions" will be accepted only if the tag l
out is mentioned.
3.14 Disagree. 4160 and D/S generator: engine are not specific l
enough to give an indication of location.-
- However, partial credit will be given for these' answers.
2 3.15 Agree. "SI signal" and " manual spray actuation" will also be accepted as answers.
3.16 Disagree. Facility reference provided does not refer to back-up heater interlock.
3.17 Disagree. Explanation of how the trip open feature is accomplished would not be complete without describing the solenoid valve and its operation.
3.18 Agree. "Deenergize source range high voltage; automatic actuation; no set point" will be accepted in substitute for "SR reactor trip".
3.19 Agree. "RHR system relief valve; 600#" will also be accepted for full credit.
3.22 Agree. Will. accept answers which include a resultant plant trip if the assumption of reaching lo S/G level trip set point is stated.
4.13 Agree. 4 psig will receive full credit.
Answer key was.
incorrect.
Points will not be deducted for additional incorrect answers since the question called for two responses.
1 4.15 Agree. " Fire protection building" will be included as an j
acceptable answer.
4.
Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination.
There were no generic weaknesses noted during the oral examination.
4 For the simulator examination two areas of below normal performance were noted. The areas of below normal performance were (1) communications with the SR0 and (2) procedural usage.
Identified problems with the simulator were discussed with simulator personnel.
The cooperation given to the examiners and the effort to ensure an atmosphere in the control room conducive to oral examinations were also noted and appreciated.
The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.
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l WNo U.
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NUCLEAR REGULATORY COMMISSION l
REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
_RggINggN________________
REACTOR TYPE:
_PWR-WEC3________________
DATE ADMINISTERED _@Zl9@fl9________________
EXAMINER:
_ERN@TE@_________________
CANDIDATE:
INSIBUCIJgNS_IQ_C@Npip@IE1 Use separate paper for the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question.
The passina grade requires at least 70% in each category and a final grade of at least 80%.
Examination papers will be picked up six (6) hours after j
the examination starts.
l
% OF CATEGORY
% OF CANDIDATE'S CATEGORY
__Y6LUE_ _IQI@6
___SCgSE___
_y@6UE__ ______________C@IEGORY_________.
_29t99__ _25t99 l.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW l
_29199__
29199
________ 2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS i
_29199__ _29199
________ 3.
INSTRUMENTS AND CONTROLS I
_29199__ _22199
________ 4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL
{
129199__
Totals i
Final Grade All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Si gnature l
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'O NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS
/,
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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 cheatino.
3.
Use black ink or dark pencil only to facilitate legible reproductions.
4.
Print your name in the blank provided on the cover sheet of the examination.
5.
Fill in the date on the cover sheet of the examination (if necessary).
6.
Use only the paper p r ovi ded for answers.
7.
Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
8.
Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one 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 three lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
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- 12. Use abbrevi ations only if they are commonly used in facility l i t er_a t ur e.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required, i
- 14. Show all calculations, methods, or assumptions used to obtain an answer l
to mathematical problems whether indicated in the question or not.
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- 15. Par ti al credit may be given.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
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- 16. If parts of the examination are not clear as to intent, ask questions of I
the examiner only.
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- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.
This must be done after the examination has been completed.
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- 18. When you complete your examination, you shall:
a.
Assemble your examination as f oll ows:
(1)
Exam questions on top.
(2)
Exam aids - figures, tables, etc.
(3)
Answer pages including figures which are part of the answer.
b.
Turn in your copy of the examination and all pages used to answer the examination questions, c.
Turn in all scrap paper and the balance of the paper that you did I
I not use for answering the questions.
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d.
Leave the examination area, as defined by the examiner.
If after l
leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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1.__EBINg1E6ES_QE_NUg6E98_EQWEB_E6@NI_gfgBBIlgN PAGE 2
1 IbEBDggYN6 digs _bE91_IB9NS[EB_9NQ_E6Ulg_E69W s.
1 QUESTION 1.01 (1.00) i Which one of the following is NOT one of the conditions necessary for brittle fracture to occur 7 a.
Plastic deformation at or below the yield point.
b.
Temperature at or below the NDTT.
I c.
Nominal stress level.
)
d.
Flaw such as a crack present.
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QUESTION 1.02 (1.00)
J l
Which one of the follow!og actions or occurrences is likely to cause water hammer?
a.
Maintaining the discharge line from an auto starting pump filled with fluid.
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b.
Water col l ect i ng in a steam line.
c.
Pre-warming of steam lines, d.
Slowly closing the discharge valve of an operating pump.
QUESTION 1.03 (1.00) i l
The reactor is critical at 10,000 cps when a S/G PORV fails open.
l Assuming BOL conditions, no rod motion, and no reactor trip, choose i
the answer below that best describes the values of Tavg and nuclear power for the resulting new steady state.
(PDAH = point of adding heat).
I a.
Final Tavg greater than i ni ti al Tavg, Final power above PDAH.
b.
Final Tavg greater than initial Tavg, Final power at POAH.
c.
Final Tavg less than initial Tavg, Final power at POAH.
d.
Final Tavg less than initial Tavg, Final power above POAH.
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l 1 __EBINCJELEg_gE_ NUCLE 98_EgyEB_E68NI_gEEB911gN PAGE 3
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ISEBdgDyN8dICS1_SE8I_IB8NSEEB_8NQ_ELUlp_E69W i
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i OUESTION 1.04 (1.00)
.l Which one of the-f ollowing f actors will help, rather than hinder, natural ci r cul ati on?
1 a.
lowering S/G 1evel b.
lowering RCS pressure c.
increasing RCS temperature d.
increasing PZR level l
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l QUESTION 1.05 (1.00)
The reactor trips from full power, equilibrium xenon conditions.
Six hours later the reactor is brought critical at 10E-8 amps on the inter-mediate range.
If power level is maintained at 10E-8 amps which one of the f ollowing statements concerning rod motion requirements f or the next two hours is correct?
a.
Rods will have to be withdrawn since xenon will closely follow its normal build-in rate following a trip.
b.
Rods will have to be inserted since xenon will closely follow its normal decay rate following a trip.
l c.
Rods will have to be rapidly inserted since the critical reactor will cause a high rate of burnout.
i d.
Rods will have to be rapidly withdrawn since the critical reactor will cause a higher than normal rate of build-in.
OUESTION 1.06 (1.00) i i
The major constituent of the power coefficient at BOL is the:
l a.
Void coefficient I
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b.
Moderator temperature coefficient c.
Baron coefficient d.
Doppler coefficient
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1.__EBINg1E6Eg_gE_NUg6E@S_EgyEB_f6@NI_ggES@llgN PAGE 4
1 IU55099XN@ dig @z_bE@I_Ig@NgEEB_@Ng_E6UJg_E699 QUESTION 1.07 (1.00)-
Which one of the following statements best describes the relationship between integral and differential rod worth?
a.
Integral rod worth (at any location) is the slope of the differential rod worth curve at that location, b.
Integral rod worth (at any location) is the total area under the differential rod worth curve from the end of the rod to that location.
c.
Integral rod worth (at any location) is the square of the differential rod worth at that location.
d.
There is no relationship between integral and differential rod worth.
QUESTION 1.08 (1.00)
Which one of the f ollowing will cause the Axial Flux Difference to become more positive (less negative)?
a.
Power increase with power defect compensated for by dilution only, b.
Power increase with power defect compensated for by rod withdrawal
- only, c.
Buildup of xenon in top portion of core, d.
Burnup of xenon in bottom portion of core.
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lt__EBJNCJE6gg_gE_NUC6gg8_EgWgB_E69NI_9EES911gN PAGE 5-1 ISEBuggYN901Cg1_bE9I_IB9NSEgB_9Ng_ELUJg_E69W QUESTION 1.09 (1.00)
Which one of the following statements describing the thermal stresses induced in the reactor vessel during a RCS cooldown is correct?
a.
Tensile stress at OUTSIDE diameter and compressive stress at INSIDE diameter.
b.
Tensile stress at INSIDE diameter and compressive stress at OUTSIDE diameter.
c.
Tensile stress at OUTSIDE diameter and no stress at INSIDE diameter.
l d.
Tensile stress at INSIDE diameter and no stress at OUTSIDE diameter.
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QUESTION 1.10 (1.00)
Which statement is true if natural circulation is lost a j
a.
Core delta T approaches zero, S/G 1evel increases, S/G pressure decreases.
i b.
Core delta T is constant at approximately 80% full power value, S/G 1evel is constant, S/G pressure decreases.
c.
Core delta exceeds 100% full power value, S/G 1evel increases, j
S/G pressure decreases.
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d.
Core delta T will exceed.100% full power value, S/G. level decreases, S/G pressure increases.
l QUESTION 1.11 (1.00)
With the plant operating at 85% power and all systems in a normal / auto configuration, the operator borates 100 PCM. Shutdown Margin wills a.
Increase b.
Increase until rods move c.
Decrease i
d.
Decrease until rods move I
e.
Remain unchanged regardless of rod movement l
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CATEGORY 01 CONTINUED ON NEXT PAGE *****)
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it__EBINCIE6Eg_QE_ NUCLE @B_EQWE6_E6@NI_QEEB911gN PAGE 6
t ISEBdQDYN@dlCQt_dE@I_IS@NSEEB_@ND_E6UID_E6QW QUESTION 1.12 (1.00)
I The main steam line break accident forms the basis for the shutdown margin requirement at end-of-life (EOL) conditions because l
a.
Beta-effective is at its maximum value.
b.
Boron concentration is at its maxi mum value.
j c.
Control rod insertion limits are most restrictive.
)
d.
Hot channel factors are at the most conservative values.
e.
MTC is at its most negative value.
l DUESTION 1.13 (1.00)
Which one of the following best describes the behavior of equilibrium xenon reactivity over core life?
a.
It decreases, because of the increased fuel burn-up, b.
It decreases, because of the decrease in plutonium-xenon yield.
c.
It increases, because of the increase in thermal flux.
d.
It increases, because of the decrease in boron concentration.
QUESTION 1.14 (1.00)
Which one of the following statements best describes parameter changes in the pressurizer following a rapid load reduction of 15*/. f ul l power?
a.
Pressurizer pressure and level will increase, with the pressure I
increase stopping before the level increase stops.
b.
Pressurizer pressure and l evel will increase, with the level increase stopping before the pressure increase stops, c.
Pressurizer level and pressure will decrease, with the pressure decrease stopping before the level decrease stops.
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d.
Pressurizer level and pressure will decrease, with the level decrease stopping before the pressure decrease stops.
6
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1 m_________.__
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1 __BB]Ng]E6Eg_gE_ NUCLE 83_ggyEB_E68NI_ GEE 8@JJgN PAGE 7
2 ISEBd99YN801Cgx_SE9J_IB@NSEEB_@Np_ELUlp_ELOW QUESTION 1.15 (1.00)
Choose the correct; order of the - boiling phases listed below as they' would occur in a coolant channel with normal flow and high heat flux?
i 1.
transition boiling 2.
bulk boiling 3.
film boiling 4.
sub-cooled nucleate boiling i
a.
2, 4,
3, 1
b.
2, 4,
1, 3
c.
4, 2,
3, 1
d.
4, 2,
1, 3
QUESTION 1.16 (1.00)
During a reactor startup you have just verified a constant startup rate on the SR Nuclear Instruments without any rod motion or baron dilution.
1 The actual condition of the core with this indication is:
a.
Prompt Critical b.
Critical c.
Supercritical d.
Subcritical i
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- 1. -
PRINCIPLES OF NUCLEAR POWER PLANT-OPERATION PAGE' 8
1 IUEBygpyN9d1Cg1_UE91_IB9N@EEB_9Np_ELUlp_ELgW i
QUESTION 1.17 (1.00)
Which one of the following describes a reason for the height correction factor, K (z ), used in the heat flux hot channel factor calculation?
a.
K(z) compensates for the increased coolant temperatures i
that occur higher in the coolant channels b.
K(z) is an uncertainty factor to allow for conservatism i
I since we cannot accurately measure flow in the core c.
K (z ) takes into account that there is some resistance in j
refilling the core completely f ollowing a small break LOCA 4
l d.
K(z) allows for greater power production in the' upper l
regions of the core near the end of life due to axial flux J
shifting QUESTION 1.18 (1.00)
Which one of the following is the purpose of using soluble boron to control the excess reactivity of the roartnr?
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a.
It does not affect the flux shape
{
l b.
It does not affect the rod worth c.
It is cheaper than adding more rods d.
It increases reactor loading rates QUESTION 1.19 (1.00)
Under which one of the f ollowing conditions is the Moderator i
Temperature Coefficient Most negative?
l a.
BOL, high temperature b.
BOL, low temperature l
c.
EOL, high temperature l
d.
EOL, low temperature
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1 IHEBMQpyN8MIC@2_HE81_IB@NSEEB_9Ng_E691g_E69W a
QUESTION 1.20 (2.00)
A motor driven centrifugal pump is operating at rated flow.
You then start closing down on the discharge valve.
How (INCREASE, DECREASE, or REMAIN THE SAME) will each of the following be affected?
a.
Flow (0.5) b.
Discharge Presure (0.5) c.
Available NPSH (0.5) d.
Motor Amps (0.5)
QUESTION 1.21 (2.50)
The plant is operating at 30*/. power, turbine in AUTO (IMP-IN), when loop
- 1 reactor coolant pump trips.
Assuming a reactor trip does not occur, there is no operator action and rod control is in MANUAL, indicate whether l
the following parameters will be HIGHER, LOWER or the SAME at the end of the transient compared to their initial values.
a.
- 2 S/G steam pressure (0.5) l b.
- 3 RCS loop flow (0.5) c.
Tc in loop #1 (0.5) d.
Th in loop #2 (0.5) l e.
Nuclear Power (0. 5) -
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l G' JEST I ON 1.22 (1.00)
Assuming all other DNB parameters remain constant, how will the f ollowing changes affect DNBR? (INCREASE, DECREASE, NO CHANGE) i.
a.
Reactor thermal power increases (0.5) b.
Average RCS temperature increases (0.5) l c.
RCS pressure increases (0.5) d.
RCS flow increases (0.5) l
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1.
PRINCIPLES'OF NUCLEAR POWER PLANT-OPERATION PAGE 10 1
IUEBMgDYN8MICg1_bE91_168NSEEB_@ND_66UID_F69W QUESTION 1.23 (2.00)
Answer TRUE or FALSE to the following.
l 1.
The use of a ramped Tavg program allows the. plant to operate with a higher thermodynamic efficiency than does a constant Tavg program.
(0,5) l 2.
Increasing condensate depression (subcooling) will cause BOTH a decrease.in plant efficiency AND an increase in condensate (hotwell) pump available NPSH.
(0.5) 3.
During a RCS heatup, as temperature gets higher, it will take a smaller lerdown flow rate to maintain a constant pr essuri z er level.
(0.5) 4.
The difference between pump suction pressure and the saturation pressure of the fluio being pumped is ref erred to as net posi-j l
tive suction head.
(0.5) )
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1 QUESTION 1.24 (1.50)
Match the heat transfer process in Column A to the equation or equations that applies to that process in Column B.
COLUMN A COLUMN B a.
Across the core 1.
Q = m Cp' delta T I
b.
Across S/G tubes (primary to 2.
O=
m delta T secondary) 3.
Q=UA delta T c.
Across S/G (feedwater to steam) 4.
O = m Cp delta h 5.
Q=m delta h I
i,
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1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION PAGE. 11.
1 IdEBOOQyN8dlCS _bE@I_IB@NSEEB_@ND_ELUlp_ELOW 4
t i
OUESTION 1.25 (1.00)
Conduction, convection and radiation are three general methods of heat transfer.
Which of these methods is the principal mechanism involved in transferring heat from:
a.
The fuel pellet to the fuel cladding?
(0.25) b.
The fuel cladding to the moderator?
(0.25) c.
The moderator to the steam generator tubes?
(0.25) d.
The steam generator tubes to the feedwater?
(0.25)
QUESTION 1.26 (1.00) a.
If the reactor is operating in the power range, how long will 4
it take to raise power from 20% to 40% with a +0.5 DPM Start-up rate?
(0.5) b.
How long will it take to raise power from 40% to 60% with the l
same +0.5 DPM Startup rate?
(0.5) l l
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2 __P(@NI_DEgigN_ lng 6UDIN@_S@EEIy_@ND_EDEB@ENgy_gygIEDS PAGE 12 t
e QUESTION 2.01 (1.00) a.
Which one of the following is NOT'a function of the Volume Control Tank:
1.
Provide NPSH to charging pumps 2.
Add hydrazine for oxygen scavenging 3.
Strip fission gases 4.
Used for dilution and boration of RCS (0.50) l b.
On loss of power to LCV-115A (VCT/ HOLDUP TANK DIVERSION) flow is directed to ______________.
(0.50)
QUESTION 2.02 (1.00) i Which of the following will NOT occur fo: Towing a signal to start the steam driven AFW pump.
j a,
service water isolation valves (SW-118 and AFW-24) open, b.
steam supply valves open (MS-V1-BA,B,C) c.
S/G blowdown isolation valves close (FCV-1930 A&B, 1931 ALB, 1932 A&B)
I d.
discharge valves open (AFW-V2-14A,B,C) l l
QUESTION 2.03 (1.00) l l
1 Which one of the following functions can NOT select its input between I
PT-446 or PT-447 using a selector switch on the RTGB?
I a.
P-2 (15% first stage turbine pressure) 6.
P-7 (10% power) i c.
Tref for rod control d.
S/G water level control
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PAGE 13
-a.
QUESTION 2.04 (1.00)
Which one of the following statements concerning the Individual Rod Position Indication system is' correct?
a.
The rod bottom bistable is adjustable and is normally set at 10 steps from the bottom of travel.
b.
The rod bottom bistable only provides indication functions, c.
There is one control bank bypass bistable associated with each control bank except control banks A and B.
d.
The control bank bypass bistable provides a blocking action on the turbine runback signal.
i QUESTION 2.05 (1.00) l Following a simultaneous LOCA and loss of off site power, all four fan cooling units and other essential loads can be supplied by a minumum of how many Service water pumps?
a.
1 b.
2 c.
3 d.
4 QUESTION 2.06 (1.00)
With regard to the containment spray system which one of the following is true7 a.
The containment spray pumps will take a suction off of the containment vessel sump if RWST level is less than 5 0 */..
b.
Containment spray discharge valves (SI-VA-8BO A,B,C,D) open automatically on a Safety Injection signal (S-signal).
(
c.
Spray additive tank discharge valves open automatically on a spray signal (P-signal).
d.
Containment spray suction valves (SI-VA-844 A,B) open automatically on a spray signal (P-signal).
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PAGE 14 1
QUESTION 2.07 (1.00) i The reactor has been operating at full rated power for 100 days. What will the magnitude of the decay heat be after one hour?
a.
O.12% of rated power b.;O.88% of rated power c.
1.62% of rated power d.
3.08% of rated power QUESTION 2.08 (1.50)
Indicate how the following valves fail (OPEN, CLOSED, or NOT AFFECTED) by a sustained loss of Instrument air.
a.
FCV-114B (VCT make-up) b.
HCV-121 (charging flow control valve.)
c.
CVC-310 A&B (charging flow to loops 1&2) d.
FCV-113A (Boric acid to blender) e.
CVC-311 (auxiliary pressurizer spray) f.
LCV-460 ALB (Letdown line stop)
QUESTION 2.09 (1.00)
Indicate whether the following statements are TRUE or FALSE concerning the Reactor Protection System.
j 1
1.
The 108% Power Range nuclear flux trip does not provide protection until the low range trip is manually blocked.
2.
The Intermediate Range high nuclear flux trip can be blocked if 1 of 4 Power Range channeln is above 10%.
_j i
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' PLANT DgglGN_INCLUDJNG_gAFETy_9ND_EMgRGENCy_gy@TgMg-PAGE 15
-QUESTION 2.10 (2.00)
Match the Reactor Coolant System penertation in Column A to the correct location in Column B.
COLUMN A COLUMN B l
q a.
Excess Letdown 1.
Loop A Cold Leg l
2.
Loop.A Hot Leg i
b.
Alternate Charging 3.
Loop B Cold Leg-
)
4.
Loop B Hot Leg c.
RHR Cooldown Suction 5.
Loop C Cold Leg 6.
Loop C Hot Leg 1
d.
Pzr Surge Line a
QUESTION 2.11 (2.00) l Match the items in Column A.with their proper setpoints in Column B.
COLUMN A COLUMN B a.
PZR PORV setpoint 1.
2335 psig b.
Tech. Spec. safety-limit 2.
2385 psig
.{
c.
code safety valves setpoint 3.
24B5 psig d.
reactor high pressure trip 4.
2570 psig 5.
2735 psig 6.
3110 psig
.l i
J i
QUESTION 2.12 (1.50) l Match the most complete MFW system response in Column B with the condition in Column A.
l COLUMN A COLUMN B a.
SI signal (S-signal) 1.
no action b.
Reactor trip with Tavg < 554F 2.
shut MFW reg. valves c.
Hi-H1 S/G 1evel (2/3 @ 75%)
3.
trip both MFW pumps 4.
shut MFW reg. valves and bypasses and trip both MFW pumps.
5.
complete MFW isolation f
(***** CATEGORY O2 CONTINUED ON NEXT PAGE *****)
l n_-.
/,
s-2.
PLANT DESIGN INCLUDJNG_gAFgTY_AND_gggRGgNCY_gYgTgMS PAGE..16 i
1 QUESTION 2.13 (2.00) e List FOUR cohditions which will automatically trip the Emergency Diesel Engines A & D.
QUESTION 2.14 (1.50).
At what. pressure are the following components designed to begin providing water to the RCS during a-SAFETY, INJECTION.
a.
Safety Injection Pumps b.
Safety injection Accumul ator s c.
Residual Heat Removal Pumps i
QUESTION 2.15 (2 00)
List four separate flow paths for delivering boric acid to the charging pumps suction.
QUESTION 2.16 (2.00)
List eight conditions v. hat can trip a main feedwater pump.
.y QUESTION 2.17 (1.50) a.
List the three comp *onents on the Reactor Coolant Pum'ps that are l
cooled by CCW.
i b.
What automatic (eature is associated with CCW supplied to the l
Reactor Coolant Pumps to provide protection in the event of a RCS to CCW leak.
1 QUESTION 2.18 (1.00)
The rod control system is designed to restore programed Tavg for what magnitude of load changes?
(***** CATEGORY O2 CONTINUED ON'NEXT PAGE
- )
t 2'.
PLANT' DESIGN INCLUDING SAFETY _AND_gMgRggNCY_gygIgMg_
PAGE17 o
QUESTION -2.19 (1.00)
What is the advantage in selecting the ALTERNATE DILUTE mode instead of the DILUTE mode?
QUESTION 2.20 (1.00)
What automatic actions occur when the R-15 (condenser air ejector gas monitor) alarm setpoint is reached?
QUESTION 2.21 (2.00) a.
What two protection signals will generate saf ety inj ection actuation for a main steam line rupture outside of the CV upstream of the MSIV's? Setpoints and logic NOT required.
b.
What are the TWO major functions performed by the Safety Injection System to mitigate the effects of a main steam line rupture?
QUESTION 2.22 (1.00)
Explain how the rate of heat removal is controlled with the RHR-system during plant cooldown.
(***** END OF CATEGORY O2
- )
3.
INSTRUMENTS AND CONTROLS PAGE 1B QUESTION T.01
( 1. 00 )
Which one of the f ollowing actions is NOT caused by a containment spray Manual Signal?
a.
steam line isolation b.
containment, ventilation i sol ati on c.
phase B containment i' sol at i on d.
both spray pumps start I,
QUESTION 3.02 (1.00)
/
Which one of the following will NOT; caus'e the automatic closure of the CVCS orifice isolatior valves?
/
a.
high containment pressure 1
b.
pressurizer low pressure c.
loss of air d.
VCT high l evel 1
QUESTION 3.03 (1.00) j Which of the following indications are used in the Steam Generator Water Level Control System.
More than one indication may be correct.
I 1
a.
Auct. high nuclear power b.
Steam flow rate c.
Feed header pressure d.
Wide range Steam Generator level j
e.
Feed tiow rate 1
f.
Turbine impulse pressure
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
3 __INSIBUME@Ig_B@g_CgN1696@
PAGE 19 4
QUESTION 3.04 (1.00)
Which one of the below is a correct statement about the Pressurizer Pressure Control System?
a.
Backup heaters and spray valves are corstrolled from PT-455 and PT-456.
b.
The " Master Controller" controls the PZR heaters, PZR apray valves, and PORV-4458.
l c.
PZR PORV block valves are air operated and f ail closed on loss of air.
l d.
PZR PORVs will not open when pressure is below 1970 psig, except when operated from MCB or ACP.
QUESTION 3.05 (1.00)
Which one of the following i s correct concerning the Source Range channel high voltage cutoff?
a.
During a reactor startup either IR channel increasing above P-6 will turn off the high voltage.
b.
If one IR channel f ails low while at power, the Source Range high voltage will be re-energized.
c.
Two out of four PR channels above 10% power will turn off the high voltage.
d.
During a reactor shutdown either IR channel decreasing below P-6 will turn on the high voltage.
i l
j
(*****
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- )
I l
k
_-_-_.__a
3 __INgIBUdENJg_gND_CgNIBgLg' PAGE 20 1
1 QUESTION 3.06 (1.00) i Which one of the following statements is CORRECT concerning the intermed2 ate range' compensated ionization chambers?
a.
The detectors are surrounded by two inches of lead for shielding fast neutron radiation.
b.
The boron lined chamber is sensitive to neutron and ' gamma radiation, while the unlined chamber is sensitive only to gamma rays.
c.
The compensated ion chamber is designed to remove the gamma signal only at high reactor power l evel s.
d.
Undercompensation will cause loss of some neutron current as well as blocking gamma current.
e.
Gammas which penetrate the detector's lead shielding will cause ionization which results in a voltage pulse.
QUESTION 3.07 (1.00)
Which one of the following rod withdrawal blocking permissives is ONLY effective when Rod Control is in AUTO?
a.
Intermediate Range Overpower (C-1) b.
Power Range Overpower (C-2) c.
Overtemperature Delta T (C-3) d.
Turbine Load Interlock (C-5)
QUESTION 3.08 (1.00)
Which one of the f ollowing malf unctions could cause one of the Over Temperature Delta T trip bistables to trip?
a.
Controlling turbine impulse pressure channel f ailing low.
b.
Power range N43 lower detector failing low.
c.
Reactor coolant flow detector failing low, d.
Controlling pressurizer level channel failing low.
(***** CATEGORY 03 CONTINUED ON NEXT PAGE
- )
.l
- -j
3 __Jy@IBUMENIg_9ND_CONIBOLS PAGE 21 A
QUESTION 3.09 (1.00)
Answer TRUE or FALSE to the following statements concerning Excore Nuclear Instrumentation.
- 1. An OVERCOMPENSATED Intermediate Range detector.could. prevent the Source Range from automatically reenergizing following an at power reactor trip.
2.
When a power range drawer is placed in TEST,'the rod stop and trip functions are disabled.
QUESTION 3.10 (2.00)
Indicate whether the f ollowing statements about the Diesel Generator are TRUE or FALSE.
1.
The synchronizer control is not used if the Diesel Generator is the sole emergency bus power supply.
2.
If a Diesel Generator shutdown sequence has been initiated in local control and a start signal is received, the Diesel Generator will return to a ready for service condition.
3.
When the diesel is started and stopped the diesel's ventilation system is automatically started and stopped.
4.
Prelube pump is not run for automatic diesel start; only for manual starts.
QUESTION 3.11 (2.00)
For the following protection / control circuits, indicate whether the listed permissive function occurs as a result of MANUAL or AUTOMATIC action.
a)
Blocking Source Range Reactor Trip above P-6 b)
Reenergizing the Source Range instrument below the P-6 setpoint.
c)
Blocking Low Pressurizer Pressure Trip below P-7 d)
Blocking High Steam Flow SI when Tavg <'543' degrees F (P-12).
(***** CATEGORY 03 CONTINUED ON NEXT PAGE
- )
-7___----
3 __INSIeUMENIg_9Bp_CggIggLg PAGE L 22 ' '
QUESTION 3.12 (1.00)
List FOUR devices / controllers that receive an input from auctioneered Tavg, OTHER thar, meters or recorders.
I 1
]
i QUESTION 3.13 (1.00)
What level will the Steam Generator Water Level Control System maintain as power changes from 0% to 100%?
QUCBTION 3.14 (1.00)
List the two locations where pushbuttons to start the Dedicated Shutdown Diesel are located.
QUESTION 3.15 (2.00)
List four signals that will automatically isolate containment ventilation.
QUESTION 3.16 (1.00)
State the reason for having backup heaters automatically energize when actual pressurizer level > reference level by 5% or more.
QUESTION 3.17 (1.50)
Explain how the trip open feature of the steam dumps is accomplished once a signal is received from the Temperature Bistables?
QUESTION 3.18 (3.00) 1 List four blocks that are permitted when 2/4 power range channels are above P-10.
Indicate if the block is MANUAL or AUTOMATIC and give the setpoint of the protective f eature being blocked.
1 4
(*****
CATEGORY 03 CONTINUED ON NEXT PAGE
- )
a
3.
INSTRUMENTS AND CONTROLS PAGE 23 QUESTION 3.19 (1.50)
Explain how the RHR system is protected from over pressurization down stream of the RHR pumps. Give automatic actions and setpoints.
QUESTION 3.20 (1.00)
A pressurizer level transmitter has a Differential Pressure Cell which has ruptured. EXPLAIN how the level INDICATION in control room would respond.
QUESTION 3.21 (1.00; a.
EXPLAIN how leakage of reactor coolant between the vessel head and vessel flange is detected. (Include sensing device) b.
How can it be determined if the leak 3ge is past the inner or the outer 0-ring?
QUESTION 3.22 (2.00) l While operating at 100% power the controlling steam flow channel fails l
low.
a.
Describe the S/G level response.
l b.
What will the final relative S/G level be?
l QUESTION 3.23 (1.00)
Prior to resetting a safegaurd signal, what must be done to restart l
safegaurd equipment which was stopped from the RTGB?
I l
(***** END OF CATEGORY 03
- )
4:__PgggggUggg_;_Ng6d@62_@gNgBd@61_ggggggggV_@Ng PAGE 24 689196991996_99NIBg6 QUESTION
'4.01 (1.00)
Which one of the following is NOT an automatic action associated with ADP-OO7 " Turbine trip without reactor trip below P-7"?
a.
Plant loads will shift to start-up transformer if loads were being supplied from the main generator.
b.
Generator lockout will occur approximately one minute after turbine trip IF generator output breakers were closed.
c.
4 reheat stop valves and 4 reheat intercept valves close.
d.
Feedwater isolation and auto start of motot-driven AFW pumps.
l l
QUESTION 4.02 (1.00)
Which one of the following is a 10 CFR 20 exposure limit?
a.
5 rem / year-whol e body.
b.
1 rem / quarter-whole body.
c.
18.75 rem / quarter-hands.
d.
7 rem / quarter-skin of whole body.
QUESTION 4.03 (1.00)
If you are in a 100 mrad / hour gamma field for 45 minutes, what is your dose in MREM after 45 minutes?
a.
45 b.
75 c.
450 d.
750
(*****
CATEGORY 04 CONTINUED ON NEXT PAGE
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4 __PBgCggUggg_;_NgBd@61_dgNg8 dab 1_gdg69ENCy_8Ng PAGE 25 B99196ggIC96_CgNIgg6 QUESTION 4.04 (1.00)
If criticality is not acheived bef ore the upper limit of the ECP is reached during a reactor startup, the operator should a.
shutdown the reactor b.
stop control bank withdrawal and approach criticality via boron dilution.
c.
proceed with the startup utilizing an Inverse Count Rate Plot from the time the ECP upper limit is reached until the time criticality is reached.
d.
proceed with the startup utilizing a pull-and-wait approach to criticality.
QUESTION 4.05 (1.00)
The boron concentration is equalized between the pressurizer and the rest of the reactor coolant system by: (choose one) a.
charging pure water or borated water to the PZR through the aux, spray line as required, b.
charging a blended flow equal to the Reactor Coolant System boron concentration into the Reactor Coolant System to force more of the RCS inventory up the surge line and into the PZR.
c.
taking MANUAL control of the Pressurizer-Level Control System and then increasing and decreasing the pressurizer level as required in order to get an exchange between the RCS'and PZR water inventory.
d.
operation of the pressurizer heaters and spray valves as required.
]
(*****
CATEGORY 04 CONTINUED ON NEXT PAGE
- )
i
'26 4 __P60ggDUBE@_ _NgBd@6g_G@NOBd@6t_EdgggEggy_@ND PAGE t
88D196991906_G9NIBQ(
QUESTION 4.
06 (1.00)
Gi'ven the following procedural steps, select the choice that provides the proper sequence for paralleling a diesel generator to a' live bus.
1.
Turn the synchronizer switch on.
2.
Start the emergency diesel gener ator.
j 3.
Turn off the synchronizer switch.
4.
Operate the governor control switch so the synchroscope moves slowly in the f ast direction.
5.
Close the generator output breaker.
6.
Wait for the synchroscope needle to pass the 11 o' clock posi tion.
7.
Operate the exciter control switch to match incoming voltage to running voltage.
I a.
1,2,4,6,5,7,3.
b.
2,7,1,4,6,5,3.
c.
2,1,4,6,5,3,7.
d.
1,2,7,6,5,4,3.
QUESTION 4.07 (2.00)
Concerning the operation of the DC Supply system, indicate EACH of the following as TRUE or FALSE.
1.
Static Inverter voltage input is 105VDC minimun to 125VDC maximum.
2.
Upon loss of AC, all battery chargers will automatically restart when AC i s restored.
3.
The reactor shall not be made critical without both safety related batteries ("A and "B")
4 For the safety related batteries
("A" and "B")
the MCC Bus Ties should remain open and should be closed only f or maintenance or in an emergency, i
(*****
CATEGORY 04 CONTINUED ON NEXT PAGE
- )
4_ _ _ Pgggg DUggg_;_ NQBygby,,ggNgBDgb1_ggggggNgy_gNQ PAGE 27 58D]QLgGJC@6_CgNIBQL QUESTION 4.08 (1.50)
From.the list of indications / characteristics in column B bel ow, sel ec t those which are characteristics / indications for each of the accidents in column A.' Note that indications / characteristics may P.
used more than once.
I
( ex ampl e:
6.
h,1,j; 7.
i,k)
Column A Column B 17~LArge LOCA
$7~ Low'S/G pressure
~
2.
SGTR b.
Low PZR pressure l
3.
Steam break in containment.
c.
Low PZR level d.
High CV pressure e.
High PZR level QUESTION 4.09
(.50)
Over the temperature range from Cold Shutdown to hot operating conditions, the heat up rate of the RCS shall not exceed
______ degrees F/ hour in any one hour.
QUESTION 4.10 (1.00) a.
Pressurizer heatup rate shall not exceed ______ degrees F/ hour.
b.
Pressurizer spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than ______ degrees F.
QUESTION 4.11 (1.00)
If DEPRESSURIZATION of the RCS is required, list the THREE methr.ds to be used in their preferred order.
l i
l l
l
(***** CATEGORY 04 CONTINUED ON NEXT PAGE
- )
i 4:__PBggEQUBgg_;_NgBd@62_@@Ng80862_EDE8@ENgY_@Ng PAGE 28 689I96991986_99NIBgL QUESTION 4.12 (1.50)
List three parameters that would require monitoring in order to determine-if a Reactor Coolant Pump should be stopped due to a loss of seal injection.
QUESTION 4.13 (1.00) i In accordance with EPP-1 what two conditions constitutes adverse l
containment conditions? (include setpoint values)
QUESTION 4.14 (2.00)
List the immediate actions for a continuous control bank D withdrawal.
I i
QUESTION 4.15 (1.00) l I
i What immediate actions are required if the control room becomes.
inaccessible due to toxic smoke?
l l
l QUESTION 4.16 (2.00) l List the immediate actions for excessive primary plant leakage.
l QUESTION 4.17 (1.50)
List all the critical safety functions in order of priority.
1 (highest priority first.)
QUESTION 4.18 (2.00)
Name five of the six symptoms of a misaligned control rod per the procedure, ADP-OO1.
l
(***** CATE60RY 04 CONTINUED ON NEXT PAGE
- )
1__PBQgEQUBgg_;_NQBd8L _9pNgBd962_EdgBgENgy_9Np PAGE 29 )
4 1
B89196991996_99NIBg6 QUESTION 4.19 (1.00) 3 Explain the process for implementation and approval of a TEMPORARY CHANGE which does NDT violate the intended function of the original I
procedure.
QUESTION 4.20 (3.50) a.
How is a reactor trip verified according to EPP-1, Loss'of all AC power procedure?. E1.03 b.
What operator actions are required if a manual trip of the reactor fails from the RTGB, according to PATH-17 (FIVE actions required) E2.5]
QUESTION 4.21 (1.00)
List the whole body administrative limits per calender que.rter that can be achieved (a) without any additional approval and (b) with the highest level of approval.
QUESTION 4.22 (1.50) a.
List the condition which must be met for the ECCS suction to be shifted to the containment sump following an SI initiation?
b.
What actions are required if RWST level reaches 9% durino Safety Injection?
t i
(***** END OF CATEGORY 04
- )
(************* END OF EXAMINATION
- )
1
.l 11__ESINCIELE@_QE_NQgLE@B_EgWEB_EL@NI_ GEE 6@IION, PAGE 30 IHEBdggyN@dlC@t_HE@I_IB@N@EEB_@ND_ELylD_ELQW 1
ANSWERS -- ROBINSON
-87/08/10-ERNSTES ANSWER 1.01 (1.00)
-(a)
REFERENCE HBR SD-058 p.6 DPC, FNRE, pp. 200 and 221 LO MTSC-TP-8.1 #4 193010K101 2.8/3.2
...(KA'S) l I
ANSWER 1.02 (1.00) 1 (b)~
REFERENCE General Physics HT&FF p.
346 LO HT/FF-TP-48.1 #3 193OO6K110 3.3/3.4
...(KA'S) l I
ANSWER 1.03 (1.00)
(d) i f?EFERENCE I
Westinghouse Reactor Physics,.Section I-5, MTC and Power Defect LO PLR/RO-TP-12.1 #4c 192OO8K114 3.1/3.1
...(KA'S) l ANSWER 1.04 (1.00)
(d) l REFERENCE l
General Physics HT&FF pp.356-358 LO HTFF-TP-50.1 3 193COBK123 3.9/4.1
...(KA'S) l l
l 1
1
7-
- 1J. -
PRI'NCIPLES OF NUCLEAR POWER' PLANT OPERATION PAGE 31 1
THEBdODyN@dlC@2_HE8I_IB8N@EEB_8ND FLUID FLOW ANSWERS -- ROBINSON
'-87/08/10-ERNSTES ANSWER 1.05 (1.00)
(a)
REFERENCE HBR RXTH-HO-1 Session 39 LO#2 192OO6K107 3.4/3.4
...(KA'S)
ANSWER 1.06 (1.00)
(d)
REFERENCE HBR RXTH-HO-1 Session 32 LO2 192OO4K108 3.1/3.1
...(KA'S)
ANSWER 1.07 (1.00)
(b)
REFERENCE Westinghouse Reactor Physics, p.
I-5.40 HBR, Reactor Theory, Session 36, p.
2, LO2 192OO5K105 2.8/3.1
...(KA'S)
ANSWER 1.08 (1.00)
(b)
REFERENCE HBR RXTH-HO-1 Sessi on 49 p. 4, LO 2 192OO5K114 3.2/3.5
...(KA'S)~
ANSWER 1.09
' ( 1. 00 )
(b)
REFERENCE
'l
'HBR, TS, p.
3.1-7 LO MTSC-TP-13.1 #4
'I u
.it__EBINCIELES_gE_NgCLE@B_EgWEB_EL@NI_QEEB@IlgN PAGE 32 t
IHEggggyN@dlCS _HE@l_16@NSEEB_8Ng_E(ylg_ELgW t
ANSWERS -- ROBINSON
-87/08/10-ERNSTES OO2OOOK407 3.1/3.5
...(KA'S)-
ANSWER.
1.10 (1.00)
(c)
REFERENCE General-Physics HT&FF, 357.
LO HT/FF-TP-50.1 #4 193OOOK122 4.2/4.2
...(KA'S)
ANSWER 1.11 (1.00)
(a) j i
REFERENCE j
HBR RXTH, session 50, p.
2, LO #2
{
-192OO2K114 3.8/3.9
...(KA'S)
-j l
ANSWER 1.12 (1.00)
(e)
REFERENCE HBR, TS, p 3.10.10 LO RXTH-TP-26.1
- 1 OO1010K509 3.4/3.8
...(KA'S)
ANSWER 1.13 (1.00)
(c)
I I
REFERENCE HBR RXTH-HO-1 Session 38 p.4 LO #2 192OO6K102 3.0/3.1
...(KA'S)
R 1
l l
c 1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION PAGE ' 33 '
t IHEBOODYN@dlC@t_HE@l_IB@NgEEB_@ND_ELylQ_ELOW
' ANSWERS -- ROBINSON
-87/08/10-ERNSTES ANSWER 1.14 (1.00)
(a)
REFERENCE STM 419 p30 LO PLR/RO-TP-37.1'#2 011000A101 3.5/3.6
...(KA'S)
ANSWER 1.'15 (1.00)
(d)
. REFERENCE General Physics HT&FF pp. 122-125' LO HTFF-TP-20.1 #l' 193OO8K103 2.8/3.1
...(KA'S) i ANSWER 1.16 (1.00)
(c)
REFERENCE-Nuclear Energy Training, Reactor Operations, NUS Corp.
paragraph 12.4 LO RXTH-TP-15.1 #3R OO1000K554 2.8/3.1
...(KA'S)
ANSWER 1.17 (1.00)
(c)
REFERENCE General' Physics HT&FF, p.249 LO HT/FF-TP-32.1 #1d 192OOSK112 2.9/3.1
...(KA'S)
-]
- _2__ u
1..
PRINCIPLES ON NUCLEAR' POWER PLANT OPERATION
'PAGE 34 1
1HggdODyd@d1Cg1_HE9I_IB8N@EE6_9ND_ELUID FLOW ~
ANSWERS -- ROBINSON'
-87/08/10-ERNSTES I
ANSWER 1.18 (1.00)
(a)
REFERENCE HBR RXTH-HO-1 Session 33, p.2.LO2 192OO7K105 3.0/3.2
...(KA*S)-
ANSWER 1.19 (1.00) 1 (C)
REFERENCE HBR RXTH-HO-1, Session 26, p 2, LO1 192OO4K106 3.1/3.1
...(KA'S) l l
ANSWER 1.20 (2.00) a.
DECREASE (0. 5 )- '
b.
INCREASE (0. 5).
c.
INCREASE (0.5) d.
DECREASE (0.5)
REFERENCE I
I General Physics HT&FF p.328 LO HT/FF-TP-43.1 #2 191001K103 2.7/2.9
...(KA'S)
ANSWER 1.21 (2.50) a.
Lower sHigher Stm Flow >> P stm decreases) b.
Higher (Less resistance to flow >>.Other RCPs speed up) c.
Lower (Less total flow across core >> delta T increases. Tc goes'down with rods in manual) d.
Higher (as above, delta.T increases, Th increases) e.
Same (Primary power = secondary load)
'i REFERENCE General Physics HT&FF.Part B, Chapter 1,
pp.129-162 j
LO MCD-TP-49.1 #4 i
l OO2OOOA105 3.4/3.7
... ( K A ' S )'
l 4
l l
1 l
1.-
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE ~35 IHEggggyN8d]CS _HE81_168NSEE8_8Np_ELUlg_ELQW 1
ANSWERS -- ROBINSON
-87/08/10-ERNSTES ANSWER 1.22 (1.00) a.
Decrease
'b.
Decrease c.
Increase d.
Increase REFERENCE General Physics, Rx PWR Limits p.243 General Physics, Boiling Heat Transfer p.122 LO HT/FF-TP-20.1 #3b i
193OOOK105 3.4/3.6
...(KA*S)
ANSWER 1.23 (2.00) 1.
TRUE (0.5) 2.
TRUE (0,5) 3.
FALSE (0.5).
4.
TRUE (0.5)
REFERENCE NUS. Nuclear Energy Training - Plant Performance, p.
5-3.2 General Physics, HT & FF, pp. 155, 319, and 320 LO HT/FF-TP-36.1 #5 OO2OOOK501 3.1/3.4
...(KA'S)
ANSWER 1.24 (1.50) l a.
1, 5
(0.50)
I b.
3 (0.50) c.
5 (0.50) l REFERENCE HBR HTT & FF, pp 101-105.
193OO7K106 3.1/3.3
...(KA'S) l
' PRINCIPLES OF NUCLEAR POWER PLANT ~ OPERATION PAGEL. 36-
- 1.
1 ISE6dODYN@dlCS _dE@l_16@NSEEB_BND_ELUID_ FLOW I
t ANSWERS -- ROBINSON
' -87/08/10-ERNSTES ANSWER 1.25 (1.00) u i
a.
Conduction b..
Convection c.
Convection d.
Convection REFERENCE Nuclear Reactor Engineering, Glasstone/Sesonske, Third Edition, pp343-345.
General Physics HT&FF pp. 99,100 LOHT/FF-TP-17.1
- 1
'193OO7K101 2.5/2.5-
...(KA'S) i ANSWER 1.26 (1.00) a.
36 SECONDS
(+/-
1sec) b.
21 SECONDS (+/-'1sec)
(0.5)each l
REFERENCE HBR RXTH Session 43, pp3.
LO RXTH-TP-43.1
- 1d
{
192OO3K104 2.7/2.8
...(KA'S)
I
.4 1
j I
4 1
i s
i
2 __P69NI_DgglgN_JNC69DJNg_g8BEIX_8ND_EDEgggNCy_gy@lEgg PAGE 37 -
3 ANSWERS'-- ROBINSON
-87/08/10-ERNSTES i
ANSWER 2.01 (1.00) a.
2 (0.5) b.
the hcidup t _' "
.(0. 5)
REFERENCE HBR SD-021 p.12,16; DWG No. 5379-685 sheet 2.
LO CVC-TP-2.1 #1' OO4000K106 3.1/3.1
...(KA'S)
)
{
l ANSWER 2.02 (1.00)
(a)
REFERENCE HBR SD-027 p.29 LO FW-TP-3.1 #4 061000A301 4.2/4.2
...(KA'S)
ANSWER 2.03 (1.00)
(b)
REFERENCE HBR SD-025 PP.10-19 LO RPS-TP-1.1 #3 045050K101 3.4/3.6
...(KA'S)
ANSWER 2.04 (1.00)
(d)
REFERENCE HBR SD-OO9, p.
6 LO RDCNT-TP-3.1 #5 014000K403 3.2/3.4
...(KA'S)
32__PL@yI_DEgl@N_]@CLyD]Ng_g@ggly_8ND_EgggggdCy_gySIEdp-PAGE' 38 kNSWERS -- ROBINSON
-87/08/10-ERNSTES ANSWER 2.05 (1.00)
(b)
REFERENCE SD-004 p.20 LO SW-TP-2.1 #3 076000A302 3.7/3.7
...(KA'S)
ANSWER 2.06 (1.00)
(c) i REFERENCE SD-OO2 pp. 14,32 i
l LO ESF-TP-4.1 #2 026000A301 4.3/4.5
...(KA'S)
ANSWER 2.07 (1.00)
(c) l REFERENCE l
HBR TS 3.3-12 LO RCS-TP-1.1 #1 OO1000K528 3.2/3.5
...(KA'S) l ANSWER 2.08 (1.50) a.
closed E.25 each]
b.
open c.
open d.
open e.
closed f.
closed REFERENCE HBR AOP-017, p.8 LO CVC-TP-4.1 #6 078000K302 3.4/3.6
...(KA'S)
g 3.__PL9NI_DE@J@N_JNC(yDJ@@_@@EEIy_8ND_EDE69ENCy_@y@IEdg PAGE 39 v
ANSWERS --' ROBINSON
-87/08/10-ERNSTES ANSWER 2.09 (1.00) 1.
FALSE [.53 2.
FALSE [.53 REFERENCE HBR SD-011, p.
16
.LO PLR/RO-TP-42.1 #2 012OOOK406 3.2/3.5
...(KA'S)
ANSWER 2.10 (2.00) a.
3 (0.5) b.
2 (0.5) l c.
4 (0. 5).
d.
6 (0.5)
REFERENCE l
VCS, AB-2, Reactor Coolant System, Fig. AB2.3 HBR: -DWG 5379-1971,Shi SD-021 p.7 LO RCS-TP-6.1 #2 OO2OOOK106 OO2OOOK108 OO2OOOK109 3.7/4.0 4.1/4.1 I
4.5/4.6
...(KA'S)
ANSWER 2.11 (2.00) a.
1 E.5 each3 b.
5 c.
3 d.
2 REFERENCE HBR TS p.2.2-1 LO MCD-TP-33.1 #2 OO2020A301 4.4/4.6
...(KA'S)
__ -_.-_ - =____ -
2 __PL@NI_pEgigN_JNCLyp]Ng_g@gEIy_8bp_EdgggENCy_gygIgUS
-PAGE 40' 3
hNSWERS -- ROBINSON
-87/08/10-ERNSTES.
ANSWER 2.12 (1.50) a.
5 E.5 EACH3 b.
2 c.
4 REFERENCE
.SD-OO6 p.16 LO ESF-TP-5.1 #3 059000K419 3.2/3.4
...(KA'S) l l
l
' ANSWER 2.13 (2.00) l Trips are: High Crankcase Pressure, Engine Overspeed,LO Lube Oil l
Pressure, LO Jacket Water Pressure (cool ant), HI Jacket Water Temperature (coolant),- Overcrank(Start. Failure).
(any 4 at 0.5 each)
REFERENCE HBR SD-OO3 p.9,12,18,19 LO DG-TP-4.1 #2,3 064000K402 3.9/4.2
...(KA'S)
ANSWER 2.14 (1.50) a.
1500 (+/-25) psig (0.5 each)
I b.
600 to 700 psig c.
130 (+/-25)psig l
REFERENCE l
HBR SD-OO2 p.29,30.
LO ESF-TP-3.1 #1 OO603OK601 3.7/3.9
...(KA'S)
ANSWER 2.15 (2.00)
-boric acid blender via FCV 113 A&B E.5 each]
-LCV-115DBfrom RWST
-MOV 350
-113A AND 114B into the top of the VCT.
- CVC 3SB isen, al b y fus - S.c Ilsa)fron' Rwsr REFERENCE HBR AOP-OO2 p.6 LO CVC-TP-4.1 #1 1-l W-
1 1
2 __PL@NI_DE@l@N_lNCLUDIN@_@@ Eely _@ND_@d@R@ENCY_@Y@ led @
'PAGE. 41 j t
I i
ANSWERS -- ROBINSON
-87/08/10-ERNSTES OO4010K609 4.4/4.6
...(KA*S)
ANSWER 2.16 (2.00)
I
-electrical overload
(.25ea.)
-undervoltage on its bus
-minimum flow - blocked for 30 secs, after starting
-loss of condensate pump
-low lube oil pressure
-low suction pressure
-SI signal
-Hi steam generator level REFERENCE HBR SD-027 p.14 LO FW-TP-2.1 #1 059000K416 3.1/3.2
...(KA'S) l l
ANSWER 2.17 (1.50) a.
~ upper RCP motor oil cooler
(.33ea.)
-lower RCP motor oil. cooler
-thermal barrier cooling coil b.
outlet line isolation valve FCV-626 E.33 will close on receipt of a hi flow signal.C.23 REFERENCE l
HBR SD-013 p.5 LO CCW-TP-1.1 #2,3 j
OO803OK302 4.1/4.2
...(KA'S) j ANSWER 2.18 (1.00)
+/- 10% step change CO.53
+/-
5% ramp change EO.43 within 15-100% power CO.13 REFERENCE SD-OO7 p.21 LO RDCNT-TP-1.1 #1 OO2OOOGOO4 3.2/3.3
...(KA'S) 1 l
i
2 __PL@NI_DE@lgN_l@CLyDlN@_@@ Eely _@ND_EdEBgENCy_gy@IEgg PAGE 42 1
ANSWERS -- ROBINSON
-87/08/10-ERNSTES l
1 ANSWER 2.19 (1.00) l The. delay time for injecting a portion of primary unborated water is reduced.
1 REFERENCE
{
HBR SD-021 p.25 LO CVC-TP-4.1 45 i
OO4020A401 3.S/3.3
...(KA'S) j l
'I ANSWER 2.20 (1.00)
Air ejector exhaust E.53 shifts to plant vent. E. 53 -o r -
No m u swa tic functr**s w a si al occa J,e to oste m t:e tratare ts 9 9 ed ' ost.
REFERENCE I
HBR SD-019 P.16 l
LO RM-TP-2.1 #3 073OOOK101 3.6/3.9
...(KA'S)
ANSWER 2.21 (2.00) i i
l a.
-PZR low pressure
-High steam line dif f erential CO.5 ea.3
]
l b.
-Inject concentrated boric acid to compensate for the positive reactivity caused by the cooldown. CO.53 l
-Provide makeup to restore PZR level from the
" shrinkage" caused by the cooldown.
[0.53 REFERENCE i
- 5 l
- 1 OOO40EK302 4.4/4.4
...(KA'S)
I L
1 j
l I
i 2___gLeNI_Q@gl@N_ldgLyplNg_g@gEIy_@Np_EDERgENgy_@lgIEdg PAGE 43 ANSWERS -- ROBINSON
-87/08/10-ERNSTES i
l ANSWER 2.22
('1. 00 )
By regulating the reactor coolant flow rate EO.5] through the Residual Heat Removal Heat.Exchangers with HCV-758 (RHR heat exch. outlet.to i
cold legs),[0.53 (from the control. board).
REFERENCE HBR SD-OO3 p.11 LO RHR-TP-1.1 #3
)
J OO5000A402 3.4/3.1
...(KA'S) l l
l 1
l l
1 l
l i
I
(
l 1
a__--__________---
_ = _
'3:__INg1690EMIg_9ND_CgyIBgLg.
PAGE 14 4
.dNSWERS -- ROBINSON
-87/08/10'-ERNSTES ANSWER 3.01
( 1. 00 ) :
(a) l l
REFERENCE.
.SD-OO6 p.16 LO.ESF-TP-4.1 #2-I O26000A401 4.5/4.3
...(KA'S)
ANSWER 3.02
<1.00)
(d)-
REFERENCE SD-021 p.18 LO CVC-TP-3.11#4; CVC-TP-4.1HM6 OO4010A401 3.6/3.1
...(KA'S)
ANSWER 3.03 (1.00) b, e,
f
[O.33 each]
REFERENCE
)
l SHNP SGWLC-HO-1.0, sect. 3.4.2 L
HBR SD-060 p.8 LO SG-TP-1.1 #2 035010A301 4.0/3.9
...(KA'S)
I ANSWER 3.04 (1.00)
(d)
REFERENCE SHNP PZRPC-LP-1.0, p.
14 HBR 50-059 p.12 LO RCS-TP-4.1 #1 010000A302 3.6/3.5
...(KA'S) 1 4
)
l 1
^
l t
3 __JNpI69dE'NIg_ANg_CgN]gggg-RAGE 45 2
.e ANSWERS.-- ROBINSON
,-87/08/10-ERNSTES.
ANSWER 3.05 (1.00)
(c)
REFERENCE SHNPP RPS-HO-1.0 p.12 HBR SD-010 p9,20,21,25 LO NI-TP-3.1 #1 015000K401 3.1/3.3
...(KA'S)
ANSWER 3.06 (1.00)
(b)
REFERENCE HBR SD-010 p.21 LO.NI-TP-4.1 #5 015000K501 2.9/3.2
...(KA'S)
ANSWER.
3.07 (1.00)
(d)
)
REFERENCE NA Lesson Plan, " Rod Control System" l
HBR SD-Oli p.26 LO RPS-TP-3.1 42 OO1000K407 3.7/3.8
...(KA'S)
ANSWER 3.08 (1.00)
(b)
REFERENCE SD-011 p.17 LO RPS-TP-4.1 #3 l
012OOOK611 2.9/2.9
...(KA'S) l l
131__JNjIgpMgNI@_gNp_CQNIQQLp
'PAGE
'46 dNSWERS --LROBINSON 1-87/08/10-ERNSTES l
ANSWER 3.
9 (1.00) j 0
i 1.
FALSE C.53 2.
FALSE
[.53 REFERENCE ll SD-010.011 LO NI-TP-1.1 #3 015000K401 3.9/4.2
...(KA'S) j ANSWER 3.10 (2.00) 1.
FALSE.
[.5 each]
2.
TALSE 3.
FALSE 4.
TRUE REFERENCE HBR SD-OO5 p.9,12,18,19 LC' JG-TP-4.1 #3 OLslOOK402
...(KA'S)
ANSWER 3.11 (2.00) a)
Manual
(*.5 ea) b)
Auto c)
Auto d)
Manual REFERENCE NA NCRODP 93.10, "RPS" HBR SD-OO6 pp. 17; SD-011 pp.16,21,23 LO RPS-TP-3.1 #1 012OOOK610 3.3/3.5
...(KA'S)
I I
l 3__.JNg]BgggNIg_Byg_CgNJggLg PAGE 47 )
j ANSWERS -- ROBINSON
-87/OR/10-FRNRTFS l
l ANSWER 3.12 (1.00) steam dump Car.y 4 at'.25 each 3
[
rod control PZR level feedwater i so?. at i on i
Tavg-Tref alarm REFERENCE HSR SD-OO1,007, 011, 025 LO PLR/RO-37.1 #1 016000K403 2.8/2.9
...(KA'S)
ANSWER 3.13 (1.00)
From 0% to.20% Power the S/G Level is 39% to 52%
[.53 From 20% to 100% Power the S/G Level is 52%.
E.53 REFERENCE HBR SD-027 p.19 LO SGLCS-TP-2.1 #1 035010K401 3.6/3.8
...(KA'S)
ANSWER 3.14 (1.00)
-engine control panel
[.53 j
-remote dedicated shutdown control panel C.53 I
REFERENCE SD-056 p.11 DG-TP-2.1 #1 064000A401 4.0/4.3
...(KA'S)
ANSWER 3.15 (2.00)
- S-signal C.5ea3 of Jy ngr, /
- P-signal on mq,v),,,,,, ;5,, l
- R-11
- R-12 R
l l
1 i
i
l 3 __INSIBUdENIS_AND_CONIB065 PAGE 48 l t
dNSWERS -- ROBINSON
-87/08/10-ERNSTES 1
REFERENCE SD-OO6 p.17 LO CSS-TP-5.1 #3 072OOOK401 3.3/3.6
...(KA'S)
ANSWER 3.16 (1.Gs)
-Assume a cold insurge
(+.25)-
-Which will cause a pressure drop (4.5)
-So heaters energized to anticipate this (+.25)
REFERENCE NA Lesson Plan, "PZR Level Control and Protection" Westinghouse PWR system manual p.10-15 LO RCS-TP-4.1 #2 011000K603 2.9/3.3
...(KA'S)
ANSWER 3.17 (1.50)
A three-way solenoid valve E.5] bypasses the positionerE.53 and applies nitrogen directly to the condenser dump valvest.53 (or instrument air directly to PORVS)
REFERENCE
)
SD-025 p.21 LO PLR/RO-YP-48.1 #3 041020K414 2.5/2.8
...(KA'S)
ANSWER 3.18 (3.00) 1 l
(.40ea)
(.15ea)
(.20)
-IR reactor trip manual 25% (current eqv. )
-PR reactor trip manual 24%
1
-IR rod stop manual 20%
-SR reactor trip automatic 10E5 cps - a r. J n y A g,f f, g,f,tr9 o E d
f I REFERENCE C " ' f i* a> -
SD-011 P.15 PO E n f
'I LO RPS-TP-3.1 #1 012OOOK406 3.2/3.5
...(KA'S) i 1
i
r 3 __IygI69dENIg_96D_CgyI60Lp PAGE-49 2
1 ANSWERS -- ROBINSON
-87/08/10-ERNSTES ANSWER 3.19 (1.50)
RHR-750 (RHR suction i sol ati on ) C.53 is interlocked with RCS pressure E.53 so that it may not be opened if PC-40311s greater than 465 psig E.53 0 [o, r]
~ c r-It HR $ystem eet;ej v a Ive [u. Q y e,.,,
,f Coo # t_ 5o REFERENCE SD-OO3 P.8 LO RHR-TP-1.1 OO5000K407 3.2/3.5
.... ( K A ' S )
ANSWER 3.20 (1.00)
The indication would read high.
REFERENCE SD-059 p.
11 LO RCS-TP-4.1 #3 010000K601 2.7/3.1
...(KA'S)
ANSWER 3,21
(;.00) a.
Elevated temperature in the leakoff line. E.53
)
b.
If. leakage is past inner 0-ring, shutting the inner leakoff connection isolation valve will cause the temperature in the leakoff line to decrease.
If the i
leakage is past the outer 0-ring, the temperature.will j
remain elevated. C.53 REFERENCE SD-058 p.15 LO-RCS-TP-2.1 #1 OO2OOCK405 3.8/4.2
...(KA'S) 1 i
I I
l
3 __Jy@]$90gyIg_gyg_CgNTR9Lg PAGE 50,
f 1
ANSWERS -- ROBINSON
-87/08/10-ERNSTES i
l ANSWER 3.22 (2.00) q a.
Level decreases due to the feed flow decrease on lower steam flow d
input.
Level error increases on level deviation until level error offset feed flow error, Jl& low lev e l '
y
.or-reactor wi II t e,* p on b.
S/G 1evel stabilizes lower than program level.
1 REFERENCE SD-027 p.12 LO FW-TP-2.1 #3 035010K401 3.6/3.8
...(KA'S)
ANSWER 3.23 (1.00)
Remove control power fuses at the breaker and reinstall them. (due to anti-pump' feature in breakers)
[1.003-REFERENCE SD-OO6 p.13 LO ESF-TP-5.1
- 3 013OOOA302 4.1/4.2
...(KA'S) 4 l
4r__66ggEQg6E@_;_Ug6086t_@@Ng60@6t_EDE6GENQy,@NQ; PAGE 51 B891969GICe6_CgNIBg6 ANSWERS -- ROBINSON'
-87/OB/10-ERNSTES ANSWER 4.01 (1.00)
(d) l REFERENCE HBR AOP-OO7 p.3 LD AC-TP-2.1 #3 045010A301
.3.5/3.6
...' (K A ' S )
-ANSWER 4.02 (1.00)
(c) l REFERENCE I
10 CFR 20.101 LO HP-TP-7.1 #2 14001K103 2.8/3.4
...(KA'S)
ANSWER 4.03 (1.00) l (b)
QF=1 for gamma 100 (45/60) ( 1 ) =75 REFERENCE 10 CFR 20.
LO HP-TP-9.1 #1 072OOOK501 2.7/3.0
...(KA'S) j l
ANSWER 4.04 (1.00) i l
1 i
(a)
REFERENCE
- NAPS, 1-OP-1.5, p.10.
HBR GP-OO3 p.25 LO RDCNT-TP-4.1 #2 OO1000A207 3.6/4.2
...(KA'S) l l
w__---_------
, 4.
PROCEDURES - NORMAL _ABNQRMALt_EMERQENCY_AND PAGE 5:2.
t 80919L991CeL_CgNIBQL ANSWERS -- ROBINSON
-87/OB/10-ERNSTES
' ANSWER 4.05' (1.00)
(d)
REFERENCE NAPS 1-OP-B.3, p.5.
HBR SD-059 p.6 LO RCS-TP-4.1 #2 010000A101-2.8/2.9
...(KA'S)
ANSWER 4.06 (1.00)
(B)
REFERENCE i
l NO.P S,
1-OP-6.2, p.
7.
HBR OP-602 pp.10,11 LO DG-TP-2.1 #5 064000A302 3.1/3.1
...(KA'S) l ANSWER 4.07 (2.00) l 1.
FALSE l
2.
FALSE 3.
TRUE l
4.
TRUE l
REFERENCE HBR OP-601 p.4 LO DC-TP-1.1 #6 063000G001 3.1/3.2
...(KA'S) 1
4 __EBgCEpyBE@_;_Ng6D961_9BNg60@(1_EME8GENCy_9NQ PAGE 53 1
8891969GIC86_CgNIBg6 ANSWERS -- ROBINSON
-87/08/10-ERNSTES 1
ANSWER 4.08 (1.50) 1 1.
b,c,d.
- 2.
b,c.
3.
a,b,c,d,(e).
E.5 each]
REFERENCE HBR SD-OO2, p.27 LO MCD-TP-44.1 #2; LO MCD-TP-45.1 #1;_
LO MCD-TP-42.1 #5.
OOO3BEA202 4.5/4.8
...(KA'S)
ANSWER 4.09
(.50) 60 REFERENCE GP-OO2 p.12 LO RCS-TP-2.1 #3 i
OO2OOOGOO5 3.6/4.1
...(KA'S)
ANSWER 4.10 (1.00) a.
100 E.5 each]
b.
320 REFERENCE GP-OO2 p.12 LO RCS-TP-5.1 #1 010000A108 3.2/3.3
...(KA'S) 1
-4.
PROCEDURES - NORMAL,,_ABNgRMAL _ EMERGENCY _ANg PAGE 54 1
R@glg6991C@b_CgNIRg6
. ANSWERS -- ROBINSON
-87/08/10-ERNSTES ANSWER 4.11 (1.00)
First--Normal Spray; (0. 25)
Second--Aux Spray with Letdown (0.25) g i
Third--PZR PORVS.(0.25)
(0.25 for correct order)
REFERENCE HBR Table 1 for Path 1.
1 LO EOP-TP-3.1 #3 OOOO9EK327 3.6/3.8
...(KA'S)
ANSWER 4.12 (1.50)
-CCW flow to thermal barrier (<25gpm)
-CCW inlet temp (>105F)
-pump bearing temp (>180F)
-No.
1 seal leakoff temp (170F)
Cany 3 9~
O.50 each]
REFERENCE HBR AOP 18, p14.
LO CVC-TP-5.1 #4 OOC 15EA210 3.7/3.7
...(KA'S)
ANSWER 4.13 (1.00) 1.
Contai cnt prc;;urc at 20 p; ice-
[.5 each]
-2. Contain,cr,t rad. lavcle et 1,000 R/hr.
j Crn to i nment tren,pe nt y ng l
p REFERENCE NAPS 1-EP-0, p.2.
1 l
HBR EPP-1 p.18 LO EOP-TP-5.1 #4 OOO69EK301 3.8/4.2
...(KA'S) l l
1
. -_ _ -___ ____ _ - _ = -
41__PBgggDgBEg_;_NgBd8L _8pNgBd@L _gdgBgENCy_BNp PAGE 55 t
2 6891g6991C8t_CgNIBQL-4 ANSWERS --- ROBINSON
-87/09/10-ERNSTES ANSWER 4.14 (2.00)
- transf er rod control to manual C4 9 0.5 each]
- attempt to manually insert the control bank and restore equilibrium power and temperature conditions.
- verify proper operation of CVCS, demineralizers, and LCV-1158 and that boration is not in progress.
- IF after transferring to manual control, equilibrium conditions cannot be achieved OR the control bank continues to be-withdrawn, THEN trip the reactor and follow Path-1 REFERENCE AOP-OO1 p.13 LO RDCNT-TP-4.1 #8 OOOO1EA203 4.5/4.8
...(KA'S)
ANSWER 4.15 (1.00) g g,y g g, g; All on shift Operators should report to the 4160 switchgear E.75]
l room and await direction from the Shift Foreman. CO.25]
l REFERENCE AOP-OO4 p.3 OOO68EK312 4.1/4.5
...(KA'S)
ANSWER 4.16 (2.00) l l
-attempt to locate (.25) and isolate (.25) leak l
-increase charging flow (.25) as necessary to maintain pressurizer level within program limits (.25)
-perf orm " Reactor Coolant System Leakage Evaluation" (OST_051) to determine actual leakage (.5)
-IF leakage exceeds RCS makeup capability,(.1) initiate SI
(.2) and follow Path-1 ( 2)
REFERENCE AOP-016 p.5,6 LO MCD-TP-42.1 #5 OOO11EK312 4.4/4.6
...(KA'S)
L
\\
4 __PBgCEgyBEg_;_NgBM861_99NgBM862_EMEBgENCy_@Np PAGE 56 t
BB9196ggICB6_CgNTBQ6 ANSWERS -- ROBINSON
-87/08/10-ERNSTES ANSWER 4.17 (1.50) 1.
Subcriticality (S)
E.125 for function;.125 for ranking]
2.
Core Cooling (C) 3.
Heat Sink (H) 4.
Integrity (P) 5.
Containment (J) 6.
Inventory (I)
REFERENCE 1
HBR.OMM-022 p.12 l
OO6000G015 4.2/4.3
...(KA'S) l 1
ANSWER 4.18 (2.00)
-one or more of the Individual Rod Position Indicators are determined to deviate with the associated Bank.
(above 200 steps: >24 step devi ati on)
(below 200 steps: >12 step devi ati on)
-disagreement between the group step counters from the same bank > 1 step.
-Power Range NI's indicate a radial flux tilt exists.
-abnormal variation between loop Tavg or Delta T measurements.
-abnormal power variation between S/G"s
-core thermocouple and/or in-core moveable detector flux map indicates a flux tilt exists.
Eany.5 0 4 each3 REFERENCE AOP-OO1 p.19 LO RPI-TP-1.1 43 OOOOO1G015 3.9/4.1
...(KA'S)
ANSWER 4.19 (1.00)
Implemented on a temporary basis f ollowing approval by two members (0.2 >
of the Plant (or CLA Management) Staff,(.25) at least one must hold a SRO license.(0.5)
REFERENCE HBR AP-OO4 p.28,29 LO ADMIN-TP-3.1 #3 194001A101 3.3/3.4
...(KA'S)
4:__PBQCEggBEg_;_NgBd8L _8BNgBd8L _EdgBGENgy_8Np:
PAGE 57 l 1
1 68919L991C86_G991696 ANSWERS -- ROBINSON'
-87/08/10-ERNSTES-l ANSWER 4.20 (3.50) a.
reactor trip and bypass breakers open
[.5 each3 neutron flux decreasing b.
-manuall y insert control rods E.5 each]
j
-manually trip the turbine
-initiate emergency boration of the RCS i
-dispatch operator to trip the rod drive MG sets
]
i REFERENCE HBR EPP-1, p3; PATH-1.
l-LO EOP-TP-5.1 #3 OOOO7EA106 OOOO7EA202 4.4/4.5
...(KA'S)
ANSWER 4.21 (1.00) l (a) 1250 mr/qtr
[0.5 each3 (b) 3000 mr/qtr REFERENCE t
NAPS Radiation Protection Manual, p.2.3-7.
- 1 194001K103 2.8/3.4
...(KA'S) l l
ANSWER 4.22 (1.50) a.
RWST level <27%
CO.53 b.
The remaining SI pumps, RHR. pumps, CV Spray Pumps, should be stopped E.53 and the. valve realignment for recirculation should be cor.;pl eted [.53 (within ten minutes).
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REFERENCE HBR EPP-9 pp. 3,4
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LO ESF-TP-3.1 #3 OOO11EK315 4.3/4.4
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- evt pg. ogh peg + keg +PgVg a PE 'KE *P V22
-where V = specific 2
2 "Y
volume
'P = Pressure 0 = &c,(T,,g-T g,1 -
0 = UA (T,,. Tit )
0 = a(hg-h )
t P = P,10(SUR)(t) p. p,t/T SUR = 26.06 T = (B. pit 1
P delta K = (K,gr-1)/K,gg CRg(1.K,ggg) = CR (1-Keff2)
- CR = 5/(1-K,gy) 2 M = (1.K,ggg)
SDM = (1.K,gg) x 1005 U-Keff2I Keff l
A = A,e.(decay constant)x(t)
In (2) 0.693 decay constant
=
=
t1/2 1/2 e
Water Parameters Miscellaneous Conversions f
i 1 gallon = 8.345 lbs 1 Curie = 3.7 x 1010 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 3
1 ft3 = 7.48 gallons I hp = 2.54 x 10 Btv/hr Density =62.4lbg/ft 1 MW = 3.41 x 106 3
Stu/hr Density = 1 p/cm 1 Stu a 778 ft.lbf Heat of Vaporization = 970 Btu /lbe Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbs 1 inch
- 2.54 centimeters 2
1 Atm = 14.7 psia = 29.9 in Hg g =.32.174 f t-1bm/1bf-sec i.
o
. TEST CROSS REFERENCE PAGE 1
$dESTION' VALUE-REFERENCE 01.'01 1.00 MEEOOO1155 01.02 1.00 MEEOOO1150 01.03-1.00 MEEOOO1154 01.04 1.00:
MEEOOO1156 01.05 1.00 MEEOOO1157 i
01.06 1.00 MEEOOO1158 l
01.07 1.00.
MEEOOO1159 l
01.08 1.00 MEEOOO1160 01.09 1.00 MEEOOO1161 01.10 1.00 MEEOOO1163 01.11 1.00 MEEOOO1165 01.12 1.00 MEEOOO1166 01.13 1.00
.MEEOOO1167 01.14 1.00 MEEOOO1168 01.15 1.00 MEEOOO1169 01.16 1.00 MEEOOO1171 01.17 1.00 MEEOOO1172 01.18
.1.00 MEEOOO1173 01.19 1.00 MEEOOO1174 01.20 2.00 MEEOOO1151 01.21 2.50 MEEOOO1153 01.22 1.00 MEEOOO1164 01.23 2.00
'MEEOOO1152 01.24 1.50 MEEOOO1146 01.25 1.00 MEEOOO1170 01.26 1.00 MEEOOO1143 30.00 i
02.01 1.00 MEEOOO1175 02,02 1.00 MEEOOO1211 02.03 1.00
_MEEOOO1214 02.04 1.00 MEEOOO1217 02.05 1.00 MEEOOO1222 02.06 1.00 MEEOOO1224 02.07 1.00 MEEOOO1249 02.08 1.50 MEEOOO1218 02.09' 1.00 MEEOOO1219 02.10 2.00 MEEOOO1181 02.11 2.00 MEEOOO1213 i
02.12 1.50 MEEOOO1225
)
02.13 2.00 MEEOOO1177 1
02.14 1.50 MEEOOO1178 i
l 02.15 2.00 MEEOOO1210
.02.16 2.00 MEEOOO1212 I
O2.17 1.50 MEEOOO1216 02.18 1.00 MEEOOO1250
)
02.19 1.00 MEEOOO1176 02.20 1.00 MEEOOO1215 02.21 2.00 MEEOOO1220 l
(
TEST CROSS REFERENCE PAGE 2
QUESTION VALUE REFERENCE O2.22 1.00 MEEOOO1247 30.00 03.01 1.00 MEEOOO1197 03.02 1.00 MEEOOO1201 03.07 1.00 MEEOOO1185 03.04 1.00 MEEOOO1186 03.05 1.00 MEEOOO1189 03.06 1.00 MEEOOO1193 03.07 1.00 MEEOOO1195 03.08 1.00 MEEOOO1205 03.09 1.00 MEEOOO1207 03.10 2.00 MEEOOO1251 03.11 2.00 MEEOOO1194 03.12 1.00 MEEOOO1190 03.13 1.00 MEEOOO1192 03.14 1.00 MEEOOO1199 03.15 2.00 MEEOOO1203 03.16 1.00 MEEOOO1196 03.17 1.50 MEEOOO1198 03.18 3.00 MEEOOO12OO 03.19 1.50 MEEOOO1202 03.20 1.00 MEEOOO1206 03.21 1.00 MEEOOO1208 03.22 2.00 MEEOOO1209 03.23 1.00 MEEOOO1248 30.00 04.01 1.00 MEEOOO1252 04.02 1.00 MEEOOO1231 04.03 1.00 MEEOOO1232 04.04 1.00 MEEOOO1233 04.05 1.00 MEEOOO1237 04.06 1.00 MEEOOO1238 04.07 2.00 MEEOOO1246 04.08 1.50 MEEOOO1227 04.09
.50 MEEOOO1239 04.10 1.00 MEEOOO1240 i
04.11 1.00 MEEOOO1187 j
04.12 1.50 MEEOOO1228 l
04.13 1.00 MEEOOO1234 j
04.14 2.00 MEEOOO1235 i
04.15 1.00 MEEOOO1236 l
l 04.16 2.00 MEEOOO1241 04.17 1.50 MEEOOO1242 j
04.18 2.00 MEEOOO1243 04.19 1.00 MEEOOO1188
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04.20 3.50 MEEOOO1226 l
04.21 1.00 MEEOOO1229 l
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TEST CROSS. REFERENCE PAGE 3')
L
-QUESTION
.VALUE.
REFERENCE 04.22 1.50 MEEOOO1244 30.00 1 2 0. 0 0 '.
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