ML20151W889
| ML20151W889 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/09/1988 |
| From: | Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20151W845 | List: |
| References | |
| 50-298-OL-88-02, 50-298-OL-88-2, NUDOCS 8808250167 | |
| Download: ML20151W889 (24) | |
Text
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION REGION IV Operator Licensing Exam Report: 50-298/0L 88-02 Operating License: DPR-46 Docket No:
50-298 Licensee:'
Nebraska Public Power District P. O. Box 499 Columbus, Nebraska 68601 Facility Name: Cooper Nuclear Station (CNS)
Examination at:
CNS 3-b Chief Examiner
- 2 J.'L.
Pellet, Chief Date Operator Licensing Section Division of Reactor Safety S
8h Approved by:
dl L. Pellet, Chief Da';e '
Operator Licensing Section Division of Reactor Safety Summary NRC Administered Examinations Conducted During the week of July 18, 1988 (Report 50-298/0L 88-02)
NRC administered examinations to two candidates.
Both candidates passed all portions of the examination and will be issued the appropriate license.
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_DET_ AILS 1.
Persons Examined SR0 R0 License Examinations:
Pass 1
1 Fail 0
0 2.
Examiners.
J. Pellet, Chief Examiner 3.
Examination Report Performance results for individual examinees are not included in this report as it will be placed in the NRC Public Document Room and these results are not subject to public disclosure.
a.
Examination Review Comment / Resolution In general, editorial comments or changes made during the examination, or subsequent grading reviews are not addressed by this resolution section. No coments were submitted for this examination, b.
Site Visit Summary (1) At the end of 'the written examination administration, the facility licensee was provided a copy of the examinations and answer keys for the purpose of comenting on the examination content validity.
It was explained to the facility licensee that regional policy was to have examination finalized within 30 days.
Thus, a timely response was desired to attain this goal.
(2) At the conclusion of the site visit, the examiners and site NRC personnel met with facility representatives to discuss the visit. The following individuals were present:
NRC FACILITY J. Pellet (Chief Examiner)
J. Boyd R. Brungardt J. Dutton G. Reece J. Surette Mr. Pellet opened the meeting by thanking those present for the cooperation received during the site visit.
Those present were also informed that current guidelines do not allow disclosure of preliminary operating examination results. Other items discussed were as follows:
a 21 y
3 s
(a) Several trainees were in the control room during th
'I operating test. This should be avoided in the future.
since it can interfere with the candidate, plus it adds :
additional pressure through the presence of.more observers..
(b) The-E0Ps were confusing when applied to a complex,
-multiple failure event.
Proper usage required that as many
. t --
as four sections of the E0Ps be conducted simultaneously.'
l (c) The E0Ps apcear to provide only mininial guidance-on' prioritiration of mitigation efforts.
For example, whether j
an operator should permit core reflood with cold water when
_.\\'
the reactor has not made subcritical appears to be only indirectly addressed.
(d) Gheratorlicensingprogramchangeswerediscussed, including the generic fundamentals examination, the new requalification audit process, and the examiners handbook, c.
Generic Comments Due to the small.num'ber of examinees, no generic strengths or weaknesses were identified.
d.
Master Examination and Answer Key A copy of the final CNS written examination and answer key is attached.
e.
Facility Examination Review Coments No facility licensee review comments regarding the CNS written examination were submitted.
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U.
S.
NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
COOPER l
REACTOR TYPE:
BWR-GE4 i
DATE ADMINISTERED: 89/07/19 l
EXAMINER:
PELLET.
J.
CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
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 passing grade requires at least 70% in each category and a final grade of at leaut 80%.
Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY
% OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 23.00 100.00 5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS 25.00 Totals Final Grade All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature 1
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
1.
Cheating on the examination means an automatic denial of your application cnd could result in more severe penalties.
2.
Rsstroom trips are to be limited and only one candidate at a time may 1 cave.
You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
3.
Une black ink or dark pencil only to facilitate legible reproductions.
4.
Print your name in the blank provided on the cover sheet of the oxamination.
5.
Fill in the date on the cover sheet of the examination (if necessary).
6.
Uae only the paper provided for answers.
7.
Print your name in the upper right-hand corner of the first page of each ocction of the answer sheet.
8.
Consecutively number each answer sheet, write "End of Category __" as 6
cppropriate, 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. S2parate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Une abbreviations only if they are commonly used in facility literature.
- 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.
- 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 examiner only.
<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 I
completing the examination.
This must be done after the examination has bGen completed.
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- 10. Wh:n you complete _your examination, you shalla c.
Assemble your examination as follows:
(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 not use for answering the questions.
d.
Leave the examination area, as defined by the examiner.
If after leaving, you are found in thic area while the examination is still in progress, your license may be denied or revoked.
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5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 2
. THERMODYNAMICS QUESTION 5.01 (1.00)
Th2 reactor trips from full power, equilibrium XENON conditions.
Twenty--
four (24) hours later the reactor is brought critical and power level is maintained on range 5 of the IRMs for several hours.
Which of the following statements is CORRECT?
(1.0) c.
Rods will have to be withdrawn due to XENON build-in.
b.
Rods will have to be rapidly inserted since the critical reactor will cause a high rate of XENON burnout, c.
Rods will have to be inserted since XENON will closely follows its normal decay rate.
d.
Rods will approximately remain as is as the XENON establishes its equilibrium value for this power level.
OUESTION 5.02 (1.00)
Which one of the following most accurately decribes when Control Rod Worth, during a REACTOR STARTUP, would normally be at its MAXIMUM 7 (1.0) c.
Cold Shutdown b.
Heatup in Progress (* 1% reactor power, 350 deg's F) c.
Heatup Complete (* 1% reactor power, 550 deg's F) d.
50% Reactor Power o.
100% Reactor Power i
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 3
THERMODYNAMICS QUESTION 5.03 (1.00)
A temperature instrument with an out-of-date calibration sticker on it is rocding 400 deg F.
A recently calibrated pressure gauge, sensing the same SATURATED system, indicates 350 psig.
Which of the following is the actual tcnk temperature?
(1.0) c.
428 deg's F b.
432 deg's F c.
436 deg's F d.
440 deg's F QUESTION 5.04 (1.00)
WHICH ONE of the follow ing is the QUALITY of a 540 deg F vapor-liquid mixture whose specific enthalpy is 1175 BTU /lbm?
(1.0) a.
O.559 b.
0.816 c.
0.964 d.
0.971 QUESTION 5.05 (1.00)
Which of the following isotopes found in the reactor coolant would NOT normally be measured to estimate the size of a fuel cladding leak?
(1.0) e.
Co - 60 b.
Xe - 133 c.
I - 131 d.
Kr - 87
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE *****)
.5..
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 4
THERMODYNAMICS QUESTION S.06 (1.00)
A reactor heat balance was performed (by hand) during the shift due to the Process Computer being out of service.
Which of the following statements ic TRUE concerning recctor power?
(1.0) c.
If the core flow rate was LOWER than the actual core flow rate, then the actual power is HIGHER than the currently calculated power.
b.
If the reactor recirculation pump heat input was OMITTED, then the actual power is HIGHER than the currently calculated power.
c.
If the steam flow was LOWER than the actual steam flow, then the actual power is HIGHER than the currently calculated power.
d.
If the RWCU return temperature was LOWER than the actual RWCU return temperature, then the actual power is HIGHER than the currently calculated power.
QUESTION S.07 (1.00)
Which of the following best defines the point of adding heat (POAH)?
(1.0) o.
When the fission RATE is sufficient to cause fuel temperature to increase.
b.
During sub-critical multiplication when Keff is > 0.99.
c.
When ALL heat additions overcome heat losses.
d.
When reactivity due to voidu exceeds the reactivity due to temperature.
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(*****
CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 5
THERMODYNAMICS QUESTION 5.08 (1.00)
Which of the following is correct?
(1.0) c.
As void fraction increases, the moderator density decreases resulting in a positive reactivity effect, b.
.The void coefficient is inversely proportional to the effective size of the core.
c.
The value of the void coefficient is NOT related to the moderator to fuel ratio.
d.
The value of the void coefficient is NOT affected by fuel temperature increases except during the extreme temperatures reached during an accident.
QUESTION 5.09 (1.00)
Which of the following thermal limits protects the fuel from clad rupture dua to PLASTIC STRAIN (deformation)?
(1.0) c.
APLHGR b.
LHGR c.
MCPR d.
MAPRAT QUESTION 5.10 (1.00)
Tha fuel temperature (Doppler) coefficient becomes:
(1.0) a.
Less negative with fuel burnup, and more negative with control rod withdrawal.
b.
More negative with fuel temperature increase and less negative with void fraction increase.
c.
Less negative with control rod withdrawal, and more negative with fuel temperature increase, d.
More negative with void fraction increase and less negative with fuel temperature increase.
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
,5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 6
THERMODYNAMICS QUESTION 5.11 (1.00)
Th3 reactor is critical at 100 cps.
Which of the following BEST describes tho behavior of neutron power following a prompt insertion of negative rocctivity?
(1.0) a.
Neutron power drops immediately to "Beta" (delayed neutron fraction) times the neutron power prior to the prompt insertion of negative reactivity.
b.
Neutron power decreases linearly with time after the initial prompt drop.
c.
After the initial prompt drop, neutron power decreases on a constant negative period; the magnitude of the period determined by the amount of negative reactivity inserted.
d.
Because only delayed neutrons are left immediately after a negative reactivity insertion, neutron power decreases on an 80 second period regardless of the size of the negative reac tivity insertior..
QUESTION 5.12 (1.00)
R]ectivity is defined as which of the following?
(1.0) c.
The ratio of the number of neutrons at some point in this generation to the number of neutrons at the same point in the previous generation.
b.
The fractional change in neutron population per generation.
c.
The f actor by which neutron population changes per generation.
d.
The rate of change of reactor power in neutrons per second.
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE *****)
/
5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 7
/
THERMODYNAMICS b
QUESTION 5.13 (1.00)
Which of the following describes the total amount of reactivity that must j b] cdded to bring a reactor to a critical condition?
(1.0) c.
Reactivity Defect b.
Excess Reactivity c.
Suberitical Factor d.
Shutdown Margin QUESTION 5.14 (1.00)
Which of the following is correct concerning control rod worth during a rocctor startup with 100% peak Xenon versus a startup with Xenon free conditions?
(1.0) c.
Peripheral control rod worth will be LOWER during the 100% peak Xenon startup than during the Xenon free startup.
b.
Central control rod worth will be HIGHER during the 100% peak startup than during the Xenon free startup.
c.
Peripheral control rod worth will be HIGHER during the 100% peak Xenon startup than during the Xenon free startup.
d.
Both central and peripheral control rod worths WILL BE THE SAME regardless of core Xenon concentration.
QUESTION 5.15 (1.00)
What is the reactor period when, during a reactor startup, the IRM readings go from 30% to 65% on the same range in 2 minutes?
(1.0) l c.
120 seconds j
b.
155 seconds c.
173 seconds d.
357 seconds
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE *****)
1
5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
-0 THERMODYNAMICS QUESTION 5.16 (1.00)
Which of the following best defines pump cavitation?
(1.0) s.'
The lack of sufficient system backpressure on the discharge side of the pump.
b.
Pressure oscillations at the discharge of the pump due to excessive inlet pressure, c.
The formation and the subsequent collapse of vapor bubbles which cause erosion of the pump parts.
d.
The existence of gas bubbles trapped in the pump housing causing flow oscillations.
QUESTION 5.17 (1.00)
What amount of reactivity is added if Keff is increased by control rod withdrawal from 0.880 to 0.965 in a subcritical reactor?
(1.0) a.
O.100 delta k/k b.
0.085 delta k/k c.
O.125 delta k/k d.
O.136 delta k/k OUESTION 5.18 (1.00)
Which is the correct description of the ONSET OF TRANSITION BOILING 7 (1.0) a.
The area on a heat transfer curve where the most energy is added to the coolant.
b.
The condition where the fuel cladding becomes continuously blanketed with a vapor film causing the heat transfer coefficient of convection to drastically decrease.
c.
The condition which causes the fuel cladding temperature to increase as the heat transfer coefficient of convection increases, d.
The condition which causes the fuel cladding temperature to fluctuate as the clad is alternately blanketed with steam and then rewetted with subcooled coolant.
(48888 CATEGORY 05 CONTINUED ON NEXT PAGE *****)
, 5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 9
1 THERMODYNAMICS QUESTION 5.19 (1.00)
Which of the following best describes why the coolant flow through a high power bundle will be less than the flow through a low power bundle without core orificing (1.0) c.
The channel quality increases.
b.
The two phase flow friction multiplier decreases.
c.
The fuel rods expand due to thermal effects.
d.
The bypass flow increases.
QUESTION 5.20 (1.00)
Which of the following best describes the change in the length of time PCquired to reach an equilib-ium count rate after insertion of a fixed cmount of positive reactivity as a subcritical reactor approaches criticality?
(1.0) c.
increases primarily because of the increased population of delayed neutrons in the core, b.
increases because of a larger number of neutron life cycles required to reach equilibrium.
c.
decreases primarily because of the increased population of delayed neutrons in the core.
d.
decreases because the source neutrons are becoming less important in relation to total neutron population.
QUESTION 5.21 (1.00)
Which of the following is correct?
(1.0) a.
- MAPRAT d.
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE *****)
-f 5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 10 THERMODYNAMICS QUESTION S.22 (1.00)
Which of the following, conditions would tand to INCREASE the Critical Power-lovel assuming all other variables remain unchanged?
(1.0)
NOTE: ASSUME NORMAL FULL POWER OPERATING CONDITIONS a.
High pressure feedwater heating is lost b.
Turbine control failure causing control valves to close c.
The axial power peak is RAISED d.
Recirc pump speed reduction using the master controller GUESTION S.23 (1.00)
Which of the following statements is NOT true regarding the LHGR (linear hast generation rate) thermal limit?
(1.0) c.
The LHGR design limit = 13.4 kw/ft for both 8x8 and P8x8R fuel.
b.
The limit is based on maintaining peak cladding temperature </= 2200 degrees F.
c.
The LHGR specification assures that the LHGR in any rod is less than the design value even if fuel pellet densification is postulated.
d.
If the limit is exceeded, it could result in fuel clad cracking due to high stress.
QUESTION S.24 (1.00)
Which of the following operations will REDUCE the AVAILABLE Net Positive Suction Head (NPSH) of an operating centrifugal pump?
(1.0) c.
Throttling open the pump's suction valve.
b.
Throttling open the pump's discharge valve.
c.
Decreasing the pump's speed.
d.
Decreasing the temperature of the fluid being pumped.
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 11 THERMODYNAMICS QUESTION 5.25 (1.00)
Which of the following best describes the change in system flow in a closed loop system with two identical constant speed centrifugal pumps in parallel, when changing from two to one pump operation (stopping the second pump)?
(1.0) o.
Decreases by slightly less than half due to decreased flow resistance.
b.
Decreases by slightly more than half due to increased flow resistance.
c.
Decreases by half due to decreased discharge head.
d.
Decreases by 1/4 due to decreased discharge head.
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(*****
END OF CATEGORY 05 *****)
(*************
END OF EXAMINATION ***************)
- 1/
5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND
/
PAGE 12 THERMODYNAMICS AN~WERS -- COOPER
-88/07/19-PELLET, J.
ANSWER 5.01 (1.00) c.
REFERENCE CNS Reactor Theory Ch.
6, Objective 2.5.2, p.
6-8 K/A 292006 K1.07 (3.2/3.2) 292OO6K107
...(KA*S)
ANSWER 5.02 (1.00)
C REFERENCE CNS Reactor Theory Ch.
5, Objective 2.7, p.
5-14 292OO5K109
...(KA'S)
ANSWER 5.03 (1.00)
C REFERENCE STEAM TABLES CNS Heat Transfer and Fluid Flow, Ch.
3, Objective 1.2, p.
3-19 293OO1K101
...(KA*S)
ANSWER 5.04 (1.00) d REFERENCE Stoam Tables CNS Heat Transfer and Fluf.d Flow, Ch.
3, Objective 1.2, p.
3-15 293OO3K112 293OO3K123
...(KA'S) l l
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,5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 13 THERMODYNAMICS
-ANSWERS -- COOPER
-88/07/19-PELLET, J.
ANSWER 5.05 (1.00) o REFERENCE
'CNS Mitigating Core Damage, Fission Product Source Terms 292OO6K101
...(KA*S)
ANSWER 5.06 (1.00) c.
(1.0)
REFERENCE CNS Teat Transfer and Fluid Flow, Ch. 7, Objective 6.4, p.
7-46 293OO7K111
...(KA*S)
ANSWER 5.07 (1,00) c REFERENCE CNS Reactor Theory, Ch.
7, Objective 3.5, p.
7-10 292OO8K111
...(KA'S)
ANSWER 5.08 (1.00) b REFERENCE CNS Reactor Theory, Ch.
4, Objective 3, p.
4-16 292OO4K110
...(KA'S) i ANSWER 5.09 (1.00) b REFERENCE CNS Heat Transfer and Fluid Flow, Ch.
9, Objective 3.3, 3.4, p.
9-15 293OO9K108
...(KA'S)
__ _ __ _ _ _ ~. _ _ _, _._._,. _ _ _
5..
. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 14 THERMODYNAMICS ANSWERS -- C,00PER
-80/07/19-PELLET, J.
ANSWER 5.10 (1.00) d REFERENCE CNS Reactor Theory, Ch.
4, Objective 6.3, p.
4-34 29?OO4K105
...(KA*S)
ANSWER 5.11 (1.00)
C REFERENCE CNS Reactor Theory, Ch.
7, Objective 1.5, 1.7, 8.3, p.
7-5 292OO3K106 292OO3K107
...(KA*S)
ANSWER 5.12 (1.00) b REFERENCE CNS Reactor Theory, Ch. 1 Objective 6.1, p.
1-38 292OO2K111
...(KA'S)
ANSWER 5.13 (1.00) d REFERENCE CNS Reactor Theory, Ch. 1 Objective 5.1, p.
1-35 292OO2K110
...(KA'S)
ANSWER 5.14 (1.00)
C REFERENCE CNS Reactor Theory, Ch.
5, Objective 2.5, p.
5-11 292OO6K114
...(KA'S)
I
5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 15 THERMODYNAMICS
-ANSWERS -- COOPER
-88/07/19-PELLET, J.
ANZWER 5.15 (1.OC) b REFERENCE CNS Reactor Theory, Ch. 3, Objective 3.5, p.
3-15 292OO3K105
...(KA'S)
ANSWER 5.16 (1.00)
C REFERENCE CNS Heat Transfer and Fluid Flow, Ch.
6, Objective 10.8, p.
6-75 293OO6K109
...(KA*S)
ANSWER 5.17 (1.00) o REFERENCE CNS Reactor Theory, Ch.
3, Objective 1.5, p.
3-8 201003K506
...(KA*S)
ANSWER 5.18 (1.00) d REFERENCE CNS Heat Transfer and Fluid Flow, Ch. 8, Objective 2.7.b, p.
8-12 a
293OOOK109
...(KA'S) i ANSWER 5.19 (1.00)
O REFERENCE CNS Heat Transfer and Fluid Flow, Ch. 8, Objective 9.3, p.
8-45 293OO8K131
...(KA'S)
.,e 5... THEORY'pF NUCLEAR NOWER PLANT OPERATION. CLUIDS. AND PAGE 16 THERMODYNAMICS ANSWERS -- COOPER
-80/07/19-PELLET, J..
ANSWER 5.20 (1.00) b REFERENCE CNS Reactor Theory, Ch. 3 Objective 1.3, p.
3-9 292OO3K101
...(KA*S)
ANSWER 5.21 (1.00) c (MAPRAT = APLHGR/MAPLHGR)
, REFERENCE CNS Heat Transfer and Fluid Flow, Ch. 9 Objective 4.5, p.
9-24 293OO9K114
...(KA*S)
ANSWER 5.22 (1.00) 6 O
REFERENCE CNS Heat Transfer and Fluid Flow, Ch. 9 Objective 5.7
- p. 9-25 293OO9K121 293OO9K122 293OO9K123 293OO9K124 293OO9K126
...(KA*S)
ANSWER 5.23 (1.00) b REF*ERENCE CNS Heat Transfer and Fluid Flow, Objective 3.2-4, p.
9-16 293OO9K107
...(KA'S)
ANSWER 5.24 (1.00) b REFERENCE CNS Heat Trannter and Fluid Flow, Ch. 6, Objective 10.9-10, 6-77 291004K114
...(KA'S)
,5.. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 17
' THERMODYNAMICS 88/07/19-PELLET, J.
ANSWERS -- COOPER J
ANSWER 5.25 (1.00)
O REFERENCE CNS Heat Transfer and Fluid Flow, Ch. 6. Obj e c t ivo 10,18, p.
6-100 293006K113
...(KA*S) w-7
+,
,--.,w--
- ~ ~ ~,, - -, - -,
a----~~-.-w-,-e-n, e
Ay,; -
TEST CROSS REFERENCE PAGE 1
-QUESTION
'VALUE REFERENCE 05.01 1.00 JJPOOO2737 05.02 1.00 JJPOOO2738 G5.03 1.00
.1JPOOO2739 05.04 1.00 JJPOOO2740 05.05 1.00
~JJPOOO2741-05.06 1.00 JJPOOO2742
-05.07 1.00 JJPOOO2743 05.08 1.00
-JJPOOO2744 05.09 1.00 JJPOOO2745 05.10 1.00 JJPOOO2746
-05.11 1.00 JJPOOO2747 05.12 1.00 JJPOOO2748 05.13 1.00 JJPOOO2749 05.14 1.00 JJPOOO2750' 05.15 1.00.
JJPOOO2751 05.16 1.00 JJPOOO2752 05.17 1.00 JJPOOO2753 05.18 1.00 JJPOOO2754 05.19 1.00 JJPOOO2755 05.20 1.00 JJPOOO2757 05.21-1.00 JJPOOO2758 05.22 1.00 JJPOOO27*9 05.23 1.00 JJPOOO2760 05.24 1.00 JJPOOO2761 05.25 1.00 JJPOOO2762 25.00 25.00 DOCKET NO 298 L