ML20237F116

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Expresses Appreciation for Time & Effort in Reactor Operator & Senior Reactor Operating Exams During Wk of 980802. Provides Comments on Written Licensing Exam
ML20237F116
Person / Time
Site: University of Lowell
Issue date: 08/11/1998
From: Medich D
MASSACHUSETTS, UNIV. OF, LOWELL, MA (FORMERLY LOWELL
To: Doyle P
NRC
Shared Package
ML20237A702 List:
References
NUDOCS 9809020074
Download: ML20237F116 (43)
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Text

AJG-11-1990 11:11 FROM U.Lowell. Rad. Cab. LTO' 13014153313 P.02 3

1 UNIVERSITY OF MASSACHUSETTS LOWELL ONE UNIVERSITY AVENUE LOWELL, MASSACHUSETTS 01854 l- August i1,1998' p

Mr. Paul Doyle MS O-11 D-19 United States Regulatory Commission Washington, D.C. 20555

Dear Mr. Doyle,

L ~

L Thank you for your time and ofTort in the reactor operator and senior reactor operating exams during the week of August 2,1998. It is always a pleasuie to see you. This letter includes the comments I have made on the written licensing exam.

There are three questions on the written exam that I wish to address:

O-=* ion B 14. may have two answers. In addition to the correct answer (d), answer (c) describes the outside surface temp. of a submerged material to reach 190*, with no indication of units. The lack of units makes this question ambiguous. Depending on whether the 190' is degrees Fahrenheit, or Celsius, this answer is either true or false.

l Please either consider question B.14 to have two solutions, or disregard it.

Oawian C 8, in addition to being outside of the expected reactor sp 4or training

~

focus, has a misprint in answer #2. The question should read " cooling to the steam of

boiling water flowing upward.. ." yet on the exam, the woni steam is replaced with stream. This changes the intent of the question (indicating that a stream ofboiling water flows upwards), rendering it false. Please throw out this question.

O=dian c 12, part B has two answers, I and 3. In addition to requiring a gamma monitor and delayed neutron detector to monitor the primary system, the primary loop is sampled daily to determine the pH of the water, please accept both answers as correct.

I wish to also bring a few minor comments to your attention. On page 7, question B.2, please change the word " radioactivity" to " activity" On question B.12, please formally add the value "0.5" in column B (this was donc during the exam, all examinees were aware of the change). On page 13, question C.2, the question should read "of the core locations listed..." please add a space between locations and listed. In addition, the element B3 is a graphite reflector on your drawing. The answer (5) on the answer sheet is incorrect. The correct answer for C.2 should read: d.4 If you require additional information, please do not hesitate to call me at (978) 934-3353

. e incerely yours, bb d vid C. Medich., PhD

~

9909020074 900812 PDR ADOCK 05000223 >

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University of Massachusetts Lowell 8/3/98 -

EXCLOSURE 3 j j

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~ Section A R Theorv. Thermo. and Facilitv Characteristics Pago'1 iOUESTION (A.1) ~ [1.01

. Core' excess reactivity changes with ...

a. fuel element burnup

b. L control rod height
c. neutronLenergy level l

. d.D - reactor power level '

QUESTION . -(A.2) [1.0)-

- '- j Inserting' a control rod predominantly affects K.,, by changing the ...

.a. fast fissiori factor .

I b. ' thermal utilization factor

c. neutron reproduction factor -

.' d . resonance escape probability .

QUESTION (A.3) [1.0] ' ,

[ 1/M plots are used to predict reactor criticality. Which of the following describes how

criticality is indicated from the graph when the 1/M plot is extrapolated a, ' The plot indicates a certain amount of reactivity added when 1/M equals zero,
b. The plot in' dicates zero reactivity added when 1/M equals infinity.-

. c. The' plot indicates a constant, horizontal line.

- d.- The plot indicates a constant, vertscal line.

QUESTION . (A.4) 12.0, 0.5'each)

Match each term in column A with the correct definition from column B.

~

Column A ~ Column B t

4 a. Prompt Neutron 1. A neutron in equilibrium with its surroundings . c.

b; - Fast Neutron 2. A neutron born directly from fission-
c. Thermal Ne' utron 3. A neutron born due to decay of a fission product I d.  :: Delayed Neutron . 4. A neutron at an energy level greater than its I surroundings

.~,

M '

Section A R Theorv.'Thermo.'and Facility Characteriggina' .Page 2 QUESTION (A.5)? 15011 '

' Figure A.1 (in the handout) is a' trace of r' eactor period over a period of time. 'Between .

points A and B, reactor power level is ...

fa.  ; always increasing 1 increasing then' decreasing'- >

c.  ; always decreasing

'd. . Reactor period and power level changes arelnot related.

- QUESTION (A.6) [1.O]' ,

t.K.,, (the' neutron multiplication factor) is defined as ...

a. . ~a bsorption/(production-+ leakage)
b. (production +. leakage)/ absorption
c.  ! (absorption '+ leakage)/ production

.d. production /(absorption + leakage) i QUESTION -(A.7) - [1.01 You walk into the control room and note that the nuclear instrumentation shows a steady neutron level,~ and no rods are in motion. Which ONE of the following conditions CANNOT be true?

a'L

. The reactor is critical.

bb The reactor is subcritical.

c. -The reactor is supercritcal.

Ld. -The neutron source has 'been removed from the core.

QUESTION' (A.8) [1.01 The reactor is critical aTa milliwatt, with the regulating rod at position X. The regulating

- rod is withdrawn and power has increased to 1 watt. In order to stabilize power at this level, the regulating rod must be p ' a. inserted to a' position LOWER than X

.b. inserted back to position X

'e .f s

ic. s inserted to a position HIGHER than X I s V d. > fully inse.ded.

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4. ,

' Section A R Theorv. Thermo, and Facility Charapleristics Paga 3

^

QUESTION ' -(A.9) [1.0] '

.Which ONE of the following types of radiation has the greatest penetrating power?

, a. p*

b.' $

c.' , y d .~ . .no '.

QUESTION (A.10) [1.0)

~ ~ '-

Reactivity is ...

~

a. :a measure of the core's deviation from criticality.
b. a measure of the core's fuel depletion.
c. negative when Ki,,is greater than 1.0.

'd. equal to $0.66 when the reactor is prompt critical.

. QUESTION ( A.11 ) .-- [1.0]

- With a sixty second period, reactor power would double approximately every

a. 15 seconds
b. 20 seconds
c. 30 seconds -
d. 40 seconds l QUESTION (A.12) (1.0]

Which ONE of the following is an examp;e of beta (D) decay?

a. 33 Br87 - > 33Assa

- 8 88

b. 35 Br ' - > 35Br .e 8 as
c. 33 Br ' - > 33Se t
h. - .

Br - > 3cKr.er 87 -

d. 33 l .: w.

l-p L

Section A R Theorv, Thermo. and Facility Characteristics - Paga 4 QUESTION '(A.13) -(1.0)

Which one of the following atoms will cause a neutron to lose the most energy during a

- scattering reaction?

a. I O'*

u b.- U23s

c. H'

- d. ' C"

- ~~

- QUESTION . (A.14) (1.01 -

. During a startup you increase K.,, from 0.95 to 0.975. What is the change in reactivity?

a. 0.27 AK/K
b. 0.78 AK/K c .' 2.7 AK/K
d. 7.8 AK/K

. QUESTION - (A.15)  :(1.01 The delayed neutron precursor (p) value for U23s fuel is 0.0065 AK/K. However, for

. calculations you should use p.,, which is typically 0.0070 - 0.0075 for research reactors.

Why is S.,, larger than E?

a. Delayed Neutrons are born at higher energies than prompt neutrons resulting in a greater worth for the neutrons
b. Delayed Neutrons are born at_ lower energies than prompt neutrons resulting in a less le'akage during slowdown to thermal energies L

. c. The fuel also contains U23e which has a relatively large D for fast fission.

d. The U23'in the core becomes Puras (by neutron absorption), which has a higher Q for fission. q 1

c.

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)

b _ _ _ _ _ _ __ _ _ _ __ )

Section A R Theory. Thermo. and Facility Characteristics PIgo 5 QUESTION (A.16) [1.0]

The difference between a moderator and a reflector is that a reflector ...

a. increases the fast non-leakage factor and a moderator increases the thermal utilization factor.
b. . increases the neutron production factor and a moderator increases the fast fission factor.
c. increases the neutron production factor and a moderator decreases the thermal utilization factor.
d. decreases the fast non-leakage factor and a moderator increases the thermal utilization factor. -

i.

QUESTION (A.17) [1.O]

Following a one week shutdown, the reactor is started up to 900 Kilowatts with rod ,

control in automatic. If the reactor remained at 900 Kwatts for the next five hours what {

would be the change in xenon concentration be during hours two through five? Xenon concentration would:

a. decrease due to the absorption of neutrons by xenon.

b, decrease due to the beta decay of xenon to cesium. )

i

c. increase due to the decay of iodine to xenon. {

l

d. increase due to the fission yield of xenon from fission.

QUESTION (A.18) [1.0]

Inelastic scattering is the process whereby a neutron collides with a nucleus and ...

a. recoils with a lower kinetic energy, with the nucleus emitting a gamma ray.
b. recoils with the same kinetic energy it had prior to the collision.
c. is absorbed by the nucleus, with the nucleus emitting a gamma ray.

I d. recoils with a higher kinette energy, with the nucleus emitting a gamma ray.

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M Section A R Theory. Thermo, and Facility Characteristics Pagn 6 QUESTION . (A.19) [1.0]

During the neutron cycle from one generation to the next, several processes occur that may increase or decrease the available number of neutrons. SELECT from the following the six factor formula term that describes an INCREASE in the number of neutrons during the

. cycle '

?a; Thermal utilization factor,

b. Resonance escape probability.
c. Thermal non-leakage probability.
d. Fast fission factor.

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(* * * *END OF CATEGORY A* * * *) I I

i

Section B Normal. Emeroency and Radiolonice! Control Procedures Pags 7 -

QUESTION (B.h 11.0):

'If,you had to choose among the following, the least percentage of your yearly allowed

.would be when you '...

o a .- receive one REM of occupational gamma exposure 1

'b. submerse yourself in Ard ' for 400 occupational DAC-hours

. c. . ingest or inhale 0.02 ALI of a nontoxic radioactive substance

d. " L wear breathing' apparatus while performing b above.

~~

QUESTION (B.2) 11.01' -

A material's radioactivity can be determined by ...

a. measuring the dose from it using an accurate radiation detector.
b. multiplying the resul't from (a) above by 4rr to account for geometry
c. ' measuring the total number of radioactive emissions given off over time.

. d. multiplying the result of (c) above by the correct quality factor. -

l

- QUESTION (B.3) 12.0,' O.5 eachl 1 j

Match the type of radiation in column A with its 10CFR2O Quality Factor in column B.

l (Items from column B may be used more than once, or not at all.)

Column A Column B

~

a. Alpha (a) -1

.b. Beta (S) 2

c. Gamma (y) 5 i
d. Neutron (on ') 10 15 I 20

. a i

- .i

Section B Normal. Emeroency and Radiological Control Proced'ures Pagn 8 h ' OUESTION 1(B.4). [1.']- 0 .

, Which ONE of the following is the definition of Committed Dose Equivalent?

i

(, a. The sum of the deep dose and the committed effective dose equivalent.

i

b. ' The dose equivalent.that the whole body receives from sources outside the body.

i-

c. The sum of external deep dose equivalent and the organ dose equivalent.'

h.= The 50 year dose equivalent to an organ or tissue resulting from an intake of radioactive material.

i ' , ," ,

L . QUESTION (B.5)'[1.01' ~

l The dose rate from a point source decreases by a factor of 2 when a 1 cm lead shield is l placed between the source and a detector. By what factor will dose rate decrease if the 1 cm lead shield IS REPLACED by a 3 cm lead shield?

a. .3
b. 4-i
c. 8
d. '9 l

QUESTION (B.6) [1.0]

Technical Specification 4.1 Specification 3, requires a visual inspection of the control rods and the regulating rod to be performed annuallyc if the inspection was last performed on L / July 31,1997, the it must be performed no later than, I

a. July 31,1998
b. August 31,1998
c. September 31,1998 l' d. October 31,1998

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I _ . _ _ . - ._ . ___.-- .__ __ -_._ _: :___-______-___ _ -

Section B ~ Normal. Emeroencv and Radiological Control Procedures Pega 9 QUESTION (B.7) [1.0]-

Limiting Safety System Settings (LSSS) are ...

a. lirnits on very important variables which are found to be necessary to reasonably protect the integrity of certain physical barriers which guard against the uncontrolled release of radioactivity.
b. settings for automatic ' protective devices related to those variables having significant safety functions.
c. combinations of sensors, interconnecting cables or lines, amplifiers and output

, devices which are connected for the purpose of measuring the value of a variable.

.s

d. the lowest functional capability of performance levels of equipment required forsafe operation of the facility.

?

1

' QUESTION (B.8) [2.0,0.5 each]

)

Identify the following requirements as either a SAFETY LIMIT (SL), a LIMITED SAFETY l SYSTEM SETTING (LSSS), or a LIMITING CONDITION FOR OPERATION (LCO).

)

)

a. 'True Power shall not exceed 4 Mw.
b. Minimurn flow (primary) 1250 GPM
c. The isothermal temperature coefficient of reactivity is negative at temperatures >

70*F

d. Maximum Tai,,108'F QUESTION (B.9) [1.0) i Which ONE of the following is an arrangement from least to most important for the three credible types of accidents associated with the U. Mass-Lowell reactor? i
u. Alert, Non-Reactor Safety Related Event, Unusual Event
b. Non-Reactor Safety Related Event, Unusual Event, Alert
c. Unus'u al Event, Alert, Non-Reactor Safety Related Event
d. Non-Reactor Safety Related Event, Alert, Unusual Event ,

e

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- Section B Normal. Emeroency and Radiological Control Procedures Pega 10

);, '

NOUESTION - (B.10) 11.01

.The Emergency plan allows the Emergency Director with the concurrence of the Radiation

N/, '

h, ' Safety Officer (or his designated alternate) to authorize exposure in e.xcess of the limits of

' 1DCFR20. . The limit for corrective actions that mitigate the consequences is ...

d a. J100 REM

' b .' 50 'REM

c. 25 REM
d. 10 REM-

, QUESTION .(B.,11) [2.0,0.5 each]

hV Match each of the 10CFR55 requirements below with its respective time period. .

Reauiremttal Yearts)

.a.- License Renewal 1 s

b. Pass Requalification Written Exam 2 i

, c. Pass Requalification Operating Test 4 e, . - ~d. Medical Examination 6 QUESTION. (B.12) 12.0,0.25 each]

Match each of the T.S. reactivity limits in column A with its respective limit from column B.

Column A '

_ Column B

a. . Single movable experiment (max) %AK/K 0.025 b .- Single Secured experiment (max) %AK/K 0.054
c. -Total of all experiments (max) _ %AK/K 0.1 d .' Control Rod Reactivity insertion (max) _ %AK/K/sec 0.2
e. ~ Regulating Rod Reactivity insertion (max) _ %AK/K/sec 2.5
f. Reference Cois7(enon limir(max) _%AK/K 2.7

.e

-? g.  :- Shutdown Margin (min) 4.7

' h. Core Excess (max) %AK/K l

I i

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Section B Normal. Emeroencv and Radioloalcal Control Procedures PIga 11

. QUESTION (B.13)

Which ONE of the foilowing conditions violates containment integrity?

a. Valve E is stuck in the closed position,
b. The inner personnel hatch on the third level cannot be closed, the outer hatch is danger tagged shut.
c. The containment isolation system is secured for maintenance (will be restored within 15 minutes).

. . d. The Truck Door is danger tagged shut.

QUESTION. (B.14)

Which ONE of the following experiments is not allowed under ANY condition?

a. . Experiment containing cryogenic liquids,
b. 2.5 milligrams of explosive material
c. The outside surface temperature of a subrnerged material will reach 190*
d. An experiment causes a reduction in the reading for the startup channel.

QUESTION (B.15)

EMERGENCY ACTION LEVEUs) is (are) ...

a. a condition which calls for immediate action beyond the scope of normal operating procedures, to avoid an accident or to mitigate the consequences of one.
b. specific instrument readings, or observations; radiological dose rates; or specific contamination levels of airborne, waterborne, or surface deposited radioactive materials that initiate appropriate emergency measures.
c. a class of emergency from a group listed by severity level for which predetermined emergency measures should be taken or considered.
d. a documented instruction that details the implementation actions and methods required to 'ac'hieve the obj6ctives of the emergency plan.

.e l

Y _ _ _ _ _ . _ _ _ - _ . ___ ._______________ - -

Section B Normal. Emeroency and Radiological Control Procedures P ga 12 QUESTION (B.16)

All of the following are actions associated with EO-4, Attack Warning and Civil Disorder except ...

a. Announce over address system that the building is to be evacuated and give cause.
b. Secure the ventilation.
c. Chain and Padlock the outer doors of both air locks.
d. If handling Co" return it to the bottom of the pool.

. ~~

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_ (* * *

  • END OF CATEGORY B* * * *)

Section C Facilltv and Radiation Monitorina Systems - PJga 13

QUESTION -(C.1)'[1.O]'
' Using Figure C-1 provided, Identify the types of radiation detected in each of the two .

marked sections (A and B) of a Compensated lon Chamber.

Section A - ' Section B -

a. .N + y _y-
b. y ~N+y
c. .N NL+ y

'd. N + y' N

c. .. .

QUESTION ~ (C.2)' ' [2.0, 0.33 each] -

Using Figure C-2, match each of the core locationslisted in column A with its correct component from column B.'

' Column A (Grid Position) Column B

a. A1 1. Proportional Counter l
b. A2. 2.- Compensated lon Chamber

. .; - c. A5 3. Startup Source

(

- d. B3 4. Graphite Reflector Element

e. D9 5. Fuel Element

. f. G9 6. Irradiation Basket

7. Servo Control Element (Regulating rod)

)

QUESTION (C.3) - [1.0) -

Using the figure C-3 provided, identify the detector (s) which does NOT supply a scram signal.

a.

b. - .i

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I^ d, ,

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> Section C Facility and Radiation Monitorina Systems Paga 14

. QUESTION (C.4) [1.0)

As shown in figure C-4, Fan EF-14 has an extra component in the bank of filters in its suction. Which ONE of the following is the extra filter component?

a. Carbon filter-
b. HEPA filter
c. Absolute Filter _

. d. Roughing Filter e -

QUESTION (C.5) [1.0] _ -

As shown in figure C-4, fans 3,4, 5 and 6 are all rated at 600 cpm except -

a. # 3, Thermal Column /Beamports & Medical Embed nent Drain line vent

~b.- # 4, Pneumatic Tubes Exhaust '

I

- c. - # 5, Hot Cell d.' # 6, Gamma Cave QUESTION (C.6) 12.0,-0.33 each]

As shown in figure C-4, Match each of the Valves listed in column A with the correct valve type listed in column B.

Column A Column B

a. Valve A - 1. 4" Air Operated
b. Valve B 2. . 12" Blast

)

c.' Valve D 3. 20" Blast

d. Valve E 4. 48" Blast
e. Valve F 5. - 48" Butterfly l

t E f.' .. Valve G ~

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L_:_.________._____.._

4

' Section C' Facility and Radiation Monitorina Svstems Paga 15 QUESTION (C.7) [1.01 ,

The reactor is operating at 1 Megawatt when the SECONDARY pump trips. Assuming no l operator action which one of the following will shutdown the reactor. I i

a. Low secondary flow scram l
I l
b. Low primary flow scram j i
c. high secondary temperature "
d. High primary temperature

- l QUESTION (C.8) [1.0] Question deleted per facility comment. -

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,,m.m....m._<________.-m....rv..._...___y.....,...<_..m rv , 2 _.. . . . . . _.,,m....__ omum .

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. #.._ ._._ ,s .. 3 rnede'e; ef hee;;renefer eve!'eb e for reme.ing decey hee;?

1. Conductica desenvierd eieng :he fucl plete to :he leveer edge of the oper,ed pe.;.
2. convective ceellng ;c the 3;ieem of be:l:ng via:er f;evi ng spvverd threugh the core ceelent peseegee.

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3. netsre: convection of hee ed air flevslng upvserd :hrough the core cec len peeeegee.
4. forced c;rcele::en selng the pr:n,ery cecient pun,p.

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d. 1 end-3

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QUESTION (C.9) '[1 0) . l 1

Given the following calculate T.,, on the shell side of the heat exchanger, j Tube Side Shell Sida j a

Tin ..

1 14.

  • F. ~

82'F i T .. 103*F  ?????

Flow '1600 gpm 1500 gpm . e i

i 1

a. 92.3*F i L
b. 93.7"F l f .
c. 71,7 ap
d. 70.3* F <

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__._________..____._o

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' Section C - Facility and Radiation Monitorina Svstems Pigs 16 QUESTION - (C.10) [2 points,0.5 eachl

' Match the radiation detectors listed in Column "A" with its corresponding detector type -

. from column "B";

a. ? Continuous Air Monitors - 1.'- BF3 detector
b. Stack Effluent Monitor (G' aseous)- 2. ~.. Geiger-Mueller detector-
c. Stack Effluent Monitor (Particulate)- 3. Scintillation detector

~ d.' Bridge Monitor ; 4. lon Chamber

,. QUESTION : (C.11) [1.0] .

  • You are instructed to place the core in the #1 position and align the core for minimum vibration (induced by flow). Select the position and mode of cooling for the core.

Position Flow Alignment

a. Bulk Pool. downcomer mode -
b. Stall Pool ~ ' cross-stall mode

. f

c. Bulk Pool ' ' cross-stall mode
d. Stall Pool downcomer mode QUESTION '(C.12) [1.O]
The liquid radwaste system divides cooling water into four sections for the purpose of  !

l performance checks / monitoring. Match the performance checks in column B, with its '

appropriate section in column A. Note performance checks in column B may be' used more than once or not at all.

I I

, . Column A Column B j

[ a. Pool 1. External y monitor and delayed neutron detector L -)

b. Primary Loop 2. Continuous conductivity measurements. '

- c. Cleanup Loop 3. Daily sample for pH.-

d. Secondary Co'olant 4. Periodic sampling for quality and radionuclides.

L' 5. Daily sampling for Na 24 ,

l V

Section C Focility and Radiation Monitorino Svsterag Paga 17 QUESTION (C.13) (1.0]

You are operating the reactor at 100 kilowatts with the regulating rod in automatic at 50%

withdrawn. You notice an anomaly and scram the reactor. Which ONE of the following is {

i true. (Assume no operator action beyond scram insertion.)

)

i

a. All control elements (control blades and regulating rod) are de-energized and at the I bottom of their travel,
b. All control blades are de-energized and at the bottom of their travel, the regulating rod is in automatic mode at 50% withdrawn.
c. All control blades are de-energized and at the bottom of their travel, the regulating rod is in manual mode at 50% withdrawn.
d. All control blades are de-energized and at the bottom of their travel , the regulat ng rod is in automatic mode and is being driven in to its bottom of travel. {

QUESTION (C.14) [1.0]

The purpose of the thermal column is to ...

a. enhance heat transfer characteristics of the core. {

- . - - b. enhance natural convection flow.

c. provide a thermal temperature rise for experiments.
d. provide a thermal neutron flux for experiments.

QUESTION (C.15) [1.01 You are performing a reactor shutdown and notice that the source range instrument does not come on scale until AEIIB the intermediate range instrumentation went off-scale low.

Select the cause for the lack of overlap,

a. Source range high voltage is de-energized.
b. Source range high voltage is set too high.
c. Intermediate range compensating voltage Is set too low.
d. Intermediate range compensating voltage is set too high. .e h

Section C Facility and Radiation Monitorina Systems Pag 318 QUESTION (C.16) [1.01 You are the console operator when all of a sudden, you notice that there is NO blade position indication, no alarms, the picoammeters are in the tripped state and the scram magnets are deenergized. Which ONE of the following will cause the above conditions? A loss of the ...

a. high voltage DC power supplies
b. unregulated control power supply
c. regulated instrumentation power supply

~

d. emergency generator.

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, 1

(* * * *END OF CATEGORY C')

~

L__-____-__________________________ ._. _

Section' A R Theory. Therrno; and Facility Characteris' tics P;ga 19

~(A.1) a REF: Burn, R., Introduction to Nuclear Reector Operations,

  • 1988, 5 5 6.2.1 & 6.2.2, p. 6-2
(A.2) b REF: Burn, R., Introduction to Nuclear Reactor Operations,
  • 1988, 9 3.3.2,12, p. 3-18 (A.3)Lat .

REF: ' Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, 5 5.5, pp. 5 5-25.

. (A.4)' . a, 2; b, 4; c, l; d,' 3 -

^ REF: Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, 5 t '3.2.2, p. 3-7 & 3.x.x, p.

3.x

-fA.5) a'-

REF: ' Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, I L(A.6) a-REF: Burn, R., Introduction to Nuclear Reactor Operations,
  • 1988, 9 3.3.1, p. 316 (A.7) c -

REF: Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, i' (A.8) b

. REF: Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, & Example 6.2, p. ' 6-2.

(A.9) c:

REF: Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, 5 (A.10) a REF: Burn, R., Introduction to Nuclear Reactor Operations,
  • 1988, 6 3.3.4, p. 3-20.

(A,11) d -

REF: Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, 6 4.10, probfem 4.10.3.

P ='Po e" time = In (2) x 60 = 41.6 seconds (A.12) d REF. Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, t 2.4.6 top of p. 2-23 (A.13) c

. REF: - Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, Tabfe 2.3, pp. 2 2-42.

l ' (A.14) z c

~

REF
' (K,,v2 - K.eii) l(K. ink.,<2) ( 0.975 - 0.95)l(0.95 x 0.975) = 0.025/ 0.92625 = 0.02699 =

l 2.7% Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, 9.3.3.4, Example on top of p. 3-23.

(A.15) b-1

.REF: Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, 6 3.2.4, p. 3-12.

(A.16) a

% EFi Burn, R., Introduction to Nuclear Reactor Operations,
  • 1988, G

~

L _ _ _ _ _ _ _ _ _ - _

-Section A R Theorv Thermo and Facility Characteristics Pags 20 '

~

v I (A.17) c REF: Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, E E 8.2 - 8.4, pp. 8 ~ 8-14.

- (A.18) . a

' REF: Burn, R., Introduction to Nuclear Reactor Operations,

  • 1988, E 2.x, p 2-45 '

(A.19) . .d-REF: Burn, R., introduction to Nuclear Reactor Operations,

  • 1982, E 3.3, pp. 3 318.

e e. 88 '

> 9 &

)

3

)

see f-1 I

L_______1.______________._____. ._ _ -

Section B Normal. Emeroency and Radiological Control Procedu es - Pzga 21 (B.1) ~ c REF: . _10CFR20 Appendix B (B.2)' 'c' REF:

'(B.3) a, 20; . b,1; ' c,1; d,10 -

REF: 10CFR20.1004, table 1004(b)

(B.4) d REF: . .10CFR20.1003 Definitions (B.5) c

.BEF: Given 1 cm is a % thickness, Dose will decrease by (%)8 = % or a factor of 8. ,

(B.6) d REF: T.S.1.26 Surveillance Intervals.

-(B.7) b

' REF: 10CFR50.36.c.1.i(A),10CFR50.36.c.1.ii(A) and 10CFR50.36.c.2(l)

(B.8) a, SL; b, LSSS; c, LCO; . d, LSSS i REF: Technical Specifications 2.1.1, 2.2.1, and 3.1 specification 5. .

~ ~

(B.9) b REF: E-Plan Table il l i

(8.10) c REF: Emergency Plan 6 3.5.

(B.11) a, 6; b, 2; c,1; d, 2 REF: 10CFR55.21,10CFR55.55, and 10CFR55.59a(2) l (B.12) a, 0.1; b, 0.5; c, 2.5; d, 0.025; e, 0.054; f, 0.2; g, 2.7; h, 4.7 I REF: T.S. 51.0, definition 20 and 5 3.1 specifications 1,2,6,8,9 and 10.

(B.13) c-I REF: -T.S. 5 3.5 i i

. (B.14) d or c Second answer added perjacility comment.

REF: T.S. t,3.6, specifications 3, 5,,7 and 8.

(B.15) b '

REF: Emergency Preparedness Plan 52.0 Definitions.

(B.16) b  !

REF: Emergency Procedure EO-4, Attack Warning and CivilDisorder.

~

L l

! u i

.I

'.i Section C Facility and ' Radiation MonitodDg Svstems Pigs 22

. C.1 a .

REF: Study Guide for Key Access and introduction to Operator Training, instrumentation and

' Control Diagrams, first figure, Compensated lon Chamber.

,(C.2) 'a, 2; b, 4; c, 3; ;d, e, {4 ' .7; ' f,1 REF: ' SAR Figure 4.1, Core Arrangement . 1 (C.3) d.

REF: , Study Guide for Key Access and introduction to Operator Training, figure 3.5, Ventilation schematic, LTIR Primary coolant Diagram- R

~

(C.4) a

+, PREF: Study Guide for Key Access and introduction to Operator Training, figure 3.5, Ventilation

. schematic. ,

-(C.5) b _

REF:

Study Guide for Key Access and Introduction to Operator Training, ContainmentNentilation j System,15.

]

. (C.6) ' a,' 4; b, 4; c, 2;, d, 3; e, 5; f,1 REF: Study Guide for Key Access and introduction to Operator Training, ContainmentNenti ation f'

System,117 through 14 (pen & ink correction in 1 10.

(C.7)'d' REF: USAR, i 4.4.15.

'C.0) o . Question deleted per facility comment.

RET. 00A". pp. 0-20 end 0 34 (C.9) b

. Flow,,,, x bT,,,, v flow, x bTu i 1600 x 114*F - 103*F = X- 82'F 1500 .'

1x 11 *F + 82*F = X = 93.7*F 15 '

REF: (C.10) a. 2 b.' 2 . c. 3 ' d. 4 i c ;REF: . U. Mass - Lowell, USAR Appendix 10, pp.10-18 and 10-19.

.l e '\

(C.11) b .

REF: 'USAR, 8 4.2.2, Primary Coolant Systems

.m

'(C!12) a,4; i b,1 or 3; p c, 2; d, 5 Second answer added per facility comment.

LN REF: USAR 5 7.2.4, p. 7-5.

i

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l q

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J f 4

, j$ction'C' Facility and Radiation Monitoridatgma Pign 23

- (C.13) c;,

REF: USAR b 4.1.7 ControlBlade Drive System, and G 4.1.8 Servo-Controlled Regulating Rod Drive Element System

' (C.14) d i REF: USAR, 5 4.3.1, Thermal Column 1.

- (C.15) d -

REF: Procedure R0-9, Reactor and Control System Cneckout Procedures, steps 3.17 & 4.11.

(C 16) b

. REF: USAR ll,4A.5, 4.4.6 AND 4.4. 7_ (Power Supplios/

M 4

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'h ; ' . **

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I 1't L. . ..

,s U. S. NUCLEAR REGULATORY COMMISSION

-1 NON-POWER INITlAL REACTOR LICENSE EXAMINATION FACILITY: U. Massachusetts-Lowell REACTOR TYPEi GE POOL

, DATE ADMINISTERED: '1998/08/03-

- , " REGION: l CANDIDATE: -

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination. Points for each question are indicated in brackets for each question. A 70% in each section is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

.. ,  % cf Category % of Candidates Category Value .Inta] Score Value Cateaorv 20.00 33.3.. A. Reactor Theory, Thermodynamics and Facility Operating Characteristics .

.2Q1Q. 132. B. Normal and Emergency Operating Procedures and Radiological Controls l

104Q'.313 C. Facillity and Radiation Monitoring Systems

]

I

~3110_  % TOTALS l

FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature e-t b

,~

t

\W r

? c ,'

[, jJ i.

N NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During th9 administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denist of your application and could result in more severe penalties.

2,._ After the examination has been completed, you must sign the statement on the cover sheet

- indicating that the work is your own and you have neither received nor given assistance 7n completing the examination. This must be done after you complete the examination.

3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
4. Use black ink or dark' pencil anty to facilitate iegible reproductions.

. 5. Print your name in the blank provided in the upper right-hand comer of the examination cover sheet and each answer sheet.

' 6. Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO <

NOT WRITE ON THE BACK SIDE OF THE PAGE.

7. The point value for each question is indicated hi (brackets] after the question. <
8. If the intent of a question is unclear, ask questions of the examiner only.
9. When turning in your examination, asserrble the completed examination with examination f

questions, examination aids and answer sheets. In addition turn in all scrap paper. j

- 10. Ensure all information you wish to have evaluated as part of your answer is on your answer sheet. 4 Scrap paper will be disposed of immediately following the examination.

11. To pass the examinatio.o you must,, achieve a grade of 70 percent or greater in each category.

. 12.' There is a time limit of three (3) hours for completion of the examination.

l l

l

13. When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is stillin progress, your license may be denied or

)1

- revoked.

b'

1 i

EQUATION SHEER d = de, AT = M AH '= UA AT = (p-p)2 P,, g* = 1 x 10-* seconds l l

i l

X,, = 0.1 seconds ~' SCR = = CR,(1 -K,,,) = CR2(1 -K,,,)_

-p 1 -K,5 CR,(-p3) = CR 2(~P2) j P'

SUR = 26.06 '#

I #<r, 1 CR l p-p M= M 3 1-K,,, 1-K,, CR, l P .= Po 10"U) '

I P=P ca .i P= (1 -p) P, {

P-P SDM - (1 -K,y) #*

T= r T= .g*

-+

y-P K,, . p-Q p X,f i

\

Ap = K'A - K'A -.

T" = 0.693 (K,,-1) ~j P ~_

k,, x K,, A g*H i.

DR =DR, e ")a DR = 6CiE(n) og,g,2 = og,g,1 DR - Rem, Ci - curies, E - Mev, R - feet j

(P2 ~0)  :

(P ~0) '

i Peak, Peak, 1 Curie = 3.7 x 10* dis /sec 1 kg = 2.21 lbm I Horsepower = 2.54 x 10' BTU /hr 1 Mw = 3.41 x 10' BTU /hr 1 BTU = 778 ft-Ibf F = 9/5 *C + 32 r 1 gal (H2 O) a 8 lbm C = 5/9 (*F - 32) ci = 1.0 BTU /hr/lbm/*F c, = 1 cal /sec/gm/ C i

l L__ _ ____ _ _ ___ _ u_ .- -

I Section A R Theory. Thermo. and Facility Characteristics Page 4 1

A.1 abcd A.9 abcd A.2 abcd - A.10 a b c d A.3 a b c'd A.11 a b c d

~

A.4a 1 2 3 4 A.12 a b c d A.4b 1 2 - 3 4 A.13 a b c d A.4c 1 2 3 4 A.14 a b c d A.4d 1 2 3 4

,, . _ A.15 a b c d A.5 abcd A.16 a b c d A.6 -abcd A.17 a b c d l A.7 abcd A.18 a b c d A.8 abcd A.19 a b c d

. - se ,- 1

.m q, ..

I f

w g 3

Section B Normal /Emerg'. Procedures & Rad con Page 5 B.1 a:b c d .B.11a 1 2 4 6 B.2: a b c d B.11b 1 2 4 6 B3a 1 2 5 1015 20 B.11c 1 2 4 6 B.3b 1 '2 5 10'15 20 B.11d 1' 2 4 6 a

B.3c '1 2 5 1015 20 B.12a 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7_ ___

- B.3d 1 2 51015 20 B.12b 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7 __, i B.4 abcd 0.12c 0.025 0.054 .0.1 0.2 0.5 2.5 2.7 4.7 ' I B.5 abcd B.12d 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7 .__

1 B.6 abcd B.12e. 0.025 0.054 0.1 0.2 0.5 2.5 2 7 4.7 l

. B7 a b'c d ~ B.12f 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7 B.8a SL LSSS LCO __ B.12g 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7 B.8b SL LSSS LCO - B.12h 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7 _ _

B.8c SL LSSS LCO B.13 a b c d l

3 L B.8d SL LSSS LCO. , . B.14.a b c d j e j

! ' B.9 ' a b c 'd ' B.15 a b c d  ;

1

'B' 10 4abcd D.16 a b c d I

l

\

4 L >

i

Section C Facility ami Re.diation Monitoring Systems Page 6 I

1 C.10 'a b c d ,.__ . C.7 a b c'd

' C.2a 1 - 213 4;5 6 7 C.8 a b c d.

1 1

i C.2b 1 2. 3 . 4. 5. 617. . C.9 a'b c d- 1

' 1 i

C.2c ' 1 2 3 4 ' 5 6 7 C.10a 1234- I i

{

C.2'd 1 2 3 .4 "5 6 -7 C.10b - 1234 l i

C.2el 1 2 3 4 5 6 7 C.10c 1 :2. 3 4 ._ .

(- .C.2f ' 1 - 2 3. 4 ' S . 6 7 _,__ . . C.10d 1 2 3'4

    • ' ~

' C.3 'a b c d- C.11 a b c d

,, C4 abcd . C.12a 1234 C.5 abcd C.12b 1234 C.6a --1. 2 3. 4 5 C.12c 1234 C.6b 1 2 3 4 5 C.12d 1.2 3 4 ro C.6c .1. 2 3 4 5 C.13 a b c d ___, *

[. , c .,

LC.6d 1. 2 '3 4 5

a C.14 a b c d

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C.6e.1:2'3 4-5' C.15 a b c d E C.6* 1 '. 2 3 4 5 '.. . __ C.16 a b c d i  ;~

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U; S. NUCLEAR REGULATORY COMMISSION

' NON-POWER INITIAL REACTOR LICENSE EXAMINATION l n,

n, '

FACILITY: = U. Massachusetts-Lowell' REACTOR TYPE: GE POOL t I

, c,. , .DATE ADMINISTERED: 1998/08/03 4

REGICN: I .

CANDIDATE: _

INSTRUCTIONS TO CANDIDATf; '

3 Answers are to be written on the answer sheet provided. ' Attach the answer sheets to the j

examination. Points for each question are indicated in brackets for each question. A 70% in I each section is required to pass the examination. Examinations will be picked up three'(3) hours

. after the examination starts. '

. .,  % of Category % of Candidates Category

_ Value ' Total .. Score _ Vaiue Cateaorv 20.00. 33.3 A. Reactor Theory, Thermodynamics and Fccility Oparating Characteristics '

20.00 .313. B. Normai and Emergency Operating Procedures and Radiological Controls

.20.00 _33 1 C. Facillity and Radiation Monitoring Systems j 60.00  % TOTALS FINAL GRADE .

- All work done on this examination is my own. I have neither given nor received aid.

s

(

Candidate's Signature -

  • l Pwa'

_ . _ _ _ _ _ _ _ _ _ _ _ _ _ __ i_i

i j

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS l

l 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 l more severe penalties.

2, i After the examination has been completed, you must sign the statement on the cover sh,eet j indicating that the work is your own and you have neither received nor given assistance in j completing the examination. This must be done after you complete the examination. 1

3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating. f 1
4. Use black ink or dark pencil only to facilitate legible reproductions.

i

. . . 5. Print your name in the blank provided in the upper right-hand comer of the examination cover sheet I and each answer sheet.

)

6. Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO 1 NOT WRITE ON THE BACK SIDE OF THE PAGE.
7. The point value for each question is indicated in [ brackets) after the question.

i

8. If the intent of a question is unclear, ask questions of the examiner only. l
9. When turning in your examination, assemble the completed examination with examination j

questions, examination aids and answer sheets. In addition turn in all scrap paper.

10. Ensure allinformation you wish to have evaluated as part of your answer is on your answer sheet. f Scrap paper will be disposed of immediateY following the examination.

l

11. To priss t,he examination you must pchieve a grade of 70 percent or greater in each category.

)

12. . There is a time limit of three (3) hours for completion of the examination. *
13. When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is stillin progress, your license may be denied or f' revoked.

[ ,

~

l l.

h __ . - _ _ _ _ _ _ _ . - -- - _ _ _ - - - - - - - - - - - - - - - - -

EQUATION SHEET f= nic, AT = in An = UA AT P , , = (p _ p)2 g' = 1 x 10-4 seconds

.X,, = 0.1 seconds SCR _ ~

CR,(1 -K,,,) = CR,(1 -K,,,)

-P 1 -K,f ca,(_p,) = cg,(_p,)

'# P SUR = 26.06 I ~# <s, 1 CA:

~ p_p- M= -M-1-K,,, 1 -K,, CR 2 P=P o 10"M 1_

P=P e T P = p(1_p) P a

P-P

'V SDM =

K,,

<K T=

p-p T=E+ ~P p A,p g ' ,l# <#2 - #<5' (K,,-1)-

T" = 0.693 k k,,,x K ,,, K,,

DR '=DR, e -k DR = 6CiE(n) pg,c ,2 = pg g z22 R

DR - Rem, Ci - curies, E - Mev, R - feet (p2~0) ,' (P t~0)

Peak, Peak, \

1 Curie = 3.7 x 10 dis /sec 1 kg = 2.21 lbm {

i Horsepower =g 2.54 x 10$ BTU /hr 1 Mw = 3.41 x 10' BTU /hr l 1 BTU = 778 ft-lbf F = 9/5 "C + 32 ^

1 gal (H2 O) = 8 lbm C = 5/9 (*F - 32) i e,. = 1.0 BTU /hr/lbm/ F c, = 1 cal /sec/gm/ C ll

Section A R Theory. Thermo. and Facility Characteristics Page 4 A.1. abcd A.9 .abcd I

A.2 abcd A.10 a b 'c d A.3 a b~c d- A.11 a b c d A.4a 1 2. 3 4 A.12 a b c d i

i A.4b 1 -2 3 4 A.13 a b c d i

- A.4c 1 2 3 4 A.14 a b c d l 4

A.4d 1 2 3 4 A.15 a b c d A.5. abcd A.16 a b c d A.6 abcd A.17 a b c d A,7 abcd A.18 a b c d A.8 abcd. A.19 a b c d

- a-M ,

e f-i i

4 L

L i I

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Section B Normal /Emerg. Procedures & Rad Con Page 5 B.1- abcd B.11a 1 2 4 6 B.2 abcd B.11b 1 2 4 6 B3a 1 2 5 1015 20 ' B.11c 1 2 4 6 B.3b 12 51015 20 B.11d 1 2 4 6 B.3c 1 2 5 1015 20 B.12a 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7 m B.3d 1 2 5 1015 20 B.12b 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7 I i

B.4 abcd B.12c 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7

~

i B.5 abcd' B.12d 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7 B.6 abcd B.12e 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7 B.7 abcd B.12f 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7 B.8a SL LSSS LCO B.12g 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7 B.8b SL LSSS LCO B.12h 0.025 0.054 0.1 0.2 0.5 2.5 2.7 4.7 B.8c SL LSSS LCO B.13 a b c d

\

B.8d ' SL LSSS LCO __. B.14 a b c d B.9 a . b c d _._ B.15 a b c d ,,

8.10 a b c d B.16 a b c d 1

l 1

L_____________2

Section C- Facility and Radiation Monitoring Systems Page 6.

C.1 a'b c d' C.7 abcd C.2a .1 2 3 4 5 6 7 C.8 abcd '

i C.2b 1 2 3 4 5 6 7 C.9 abcd )

i C.2c !1 2 3 4 5 6 7 C.10a 1234 C.2d 1 2 3 4 5 6 7 C.10 1234 i

C.2e 1 2 .3 4 5 6 7 C.10c 1234  !

l C.2f 1 2 3 4 5 6 7 C.10d 1234 l

{

C.3 abcd- C.11 a b c d i

C.4. abcd C.12a 12345 i

. C.5 abcd C.12b 12345 C.6a 1 2 3 4 5 C.12c 12345 j C.6b 1 2 3 4 5 C.12d 12345 i C.6c ' ~1 2 3 4 5 C.13' a b c d C.6d 1 2 3 4 5 __ C.14 a b c d C.6e 1 2 3 4 5 C.15 a b c d l

l C.6f 1 2 3 4 5 C.16 a b c d '

l l

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