Text

Exam Rept 50-151/OL-90-01 on 901127-28 for Both Facilities. Test Results:Both Candidates Passed Exams
	ML20024F912
Person / Time
Site:	University of Illinois, 05000356
Issue date:	12/13/1990
From:	Jordan M, Shembarger K; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20024F910	List: ML20024F909; ML20024F912;
References
	50-151-OL-90-01, 50-151-OL-90-1, NUDOCS 9012270144
	Download: ML20024F912 (97)
	v • d • e

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U.S.

NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-151/OL-90-01

-Docket Nos. 50-151; 50-356 Licenses No. DPR-115; DPR-117 Licensee:

U..iversity of Illinois 214 Nuclear Engineering Laboratory 103 S. Goodwin Avenue Urbana, IL 61801 Facility Name:

University of Illinois Examination Administered At:

University of Illinois Examination Conducted:

November 27 & 28, 1990 RIII Examiner:

k. RhyvA0Nw talt';(%

K.

Shembarger 6 Date Chief Examiner:

75MMbM)A Iallsl90 K.

Shembarger 4

Date Approved By:

Ef N (v

/ //3!?O M.

Jbrdan, Chief Date Operator Licensing Section 1 Examination Summary:

Examination administered on November 27 and 28, 1990 (Recort No. 50-151/OL-90-01):

Written and operating examinations were administered to one senior reactor and one reactor operator candidate.

Results:

Both candidates passed the examinations.

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PDR ADOCK 05000151 PDR V

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REPORT DETAILS 1.

Exit Meetina a.

On November 28, 1990, an exit meeting was held.

The following personnel were at the meeting:

K. Shembarger - NRC Examiner C.

Pohlod - Reactor Supervisor b.

The following general observation was made by the examiner and discussed with the facility:

The Safety Analysis Report for the University of Illinois TRIGA reactor states that in the square-wave mode of operation, the reactor is operated at power levels between 0.3 and 1.0 FN.

On the contrary, the TRIGA reactor is operated at power levels up to and including 1.5 MW in the square-wave mode of operation.

As of November 28, 1990, a 50.59 review for operating outside the scope of the SAR had not been performed.

The licenseo should request an SAR change to reflect their current practice.

c.

The following generic weakness was identified during administration of the operating examinations:

Training in the area of Surveillance Procedure performance outside the control needs improvement.

2.

Written Examination a.

The following generic weaknesses were identified on the written examinations:

- Both candidates failed to identify a method to discriminate between a major and a minor primary system leak.

- Both candidates failed to identify a given set of conditions that would exceed power operation restrictions.

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FACILITY COMMENTS ON WRITTEN EXAMINATION SECTION A QUESTION 12:

Which ONE of the following describes the term "Subcritical Multiplication":

a.

The ratio of fission plus source neutrons divided by the number of fission neutrons.

b.

The multiplication of the source neutrons by tho fission neutrons.

c.

The inverse of the multiplication factor minus 1 (1/ (Kef f-1) ).

d.

Is equal to 25 when the reactor is in shutdown conditions and an external source does not exist.

ANSWER 12:

b.

REFERENCE 12:

NE351, pg.

1-2.

FACILITY COMMENT:

Answer should be " Multiplication of source neutrons by multiplying media (fissile material).

NRC RESOLUTION:

The reference.provided by the facility states that subcritical multiplication is the multiplication of the source neutrons by the fission neutrons.

No other reference was provided.

Therefore, the comment was not accepted.

QUESTION 16:

Which ONE of the following is equivalent to $1 of reactivity in the TRIGA reactor:

a.

delayed neutron fr6ction (delta k/k).

b.

0.01 delta k/k.

c.

0.0073 percent delta k/k d

reactivity when criticality is achieved.

ANSWER 16:

a.

REFERENCE 16:

NE390R, pg. 1-26.

FACILITY COMMENT:

This is a trick question due to distractor c, since another correct answer in addition to a. is 0.0073 delta k/k (0.73 percent delta k/k).

NRC RESOLUTION:

This is not considered a trick question, since the word

" percent" was clearly stated in the distractor.

Therefore, the comment was not accepted.

SECTION B QUESTION 6:

Which ONE of the following would require a manual trip if the reactor was critical (Assume a core with low hydride fuel elements installed in other than F or G hexagonal):

LOCATION OF FUEL ELEMENT FUEL TEMPERATURE a.

B - hexagonal 375 degrees F b.

C - hexagonal 375 degrees F c.

D - hexagonal 375 degrees F d.

E - hexagonal 375 degrees F ANSWER 6:

d.

REFERENCE 6:

Technical Specification 2.2, pg.

5.

FACILITY COMMENT:

Condition is unrealistic as temperature in the D Hex is only 380 degrees C at full power, and temperatures are similar at operation up to 1 MW.

Placing aluminum clad elements in D through B would probably preclude full power operation.

NRC RESOLUTION:

The question is based on the Limiting Safety System Settings for tho' fuel element temperature trip setpoints in the Technical Specifications, and is a valid question.

Therefore, the comment was not accepted.

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QUESTION 17:

Which ONE of the following would exceed the Power Operation Restrictions as set forth in " Contingency Procedure: Isolation Valves Not Operative".

(Power is provided for a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

Assume linear power changes):

a.

0800 0.1 MW 1100 0.3 MW 1800 0.5 MW 2400 0.3 MW 0800 0.1 MW b.

0800 0.0 MW 1200 0.5 MW 1300 1.5 MW 1400 0.2 MW 0800 0.0 MW c.

0800 0.25 MW 1400 0.25 MW 2000 0.25 MW 0200 0.25 MW 0800 0.25 MW d.

0800 0.0 MW 1400 0.1 MW 1800 0.2 MW 2400 0.3 MW 0800 0.4 MW ANSWER 17:

a.

REFERENCE 17:

Contingency Procedure: Isolation Valves Not Operative.

FACILITY COMMENT:

If the isolation valves were to fail today, this procedure would not be used without consultation with USNRC.

Voiding this procedure was discussed some years ago, but it was left in place for guidance.

If this failure occurred today, the most probable decision would be to limit operation to 250 kW for a 9 hour1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months operating day per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

NRC RESOLUTION:

The procedure is currently in place to be used by licensed operators.

The facility did not provide additional reference material that would be used by tr* operator in lieu of the procedure that is currently in place.

Therefore, the comment was not accepted.

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._m.__

SECTION C QUESTION 2:

Which ONE of the following describes the configuration of the TRIGA q'

reactor during' normal operation:

a.

1._

D-7 contains the Adjustable Transient Rod 2.

D-16 contains the External source 3.

G-2 contains_the' Fast Transient' Rod

.4.

G-35'contains the MRL Pneumatic System.

b.1 1.

D-7 contains the. Adjustable Transient Rod 2.

D-16 contains the Fast Transient Rod 3.

G-2 contains'the External Source 4.

G-35 contains the MRL Pneumatic System c.

1.

D-7 contains the External Source 2.

.D-16'contains the-MRL Pneumatic. System

'3.

G-2 contains the Adjustable Transient Rod 4.

G-35 contains the Fast Transient Rod d.-

1.

-D-7 contains the-External Source 2.

D-16 contains the Adjustable Transient Rod 3..

G-2 contains-the-MRL Pneumatic System 4.

G-35 contains the Fast Transient Rod ANSWER 2:'

.b.

REFERENCE-2:

Facility' Design, pg. 1-35'and 1-36.

' FACILITY COMMENT:

' The external source was recently-moved 1to G-1.

.NRC RESOLUTION:

LComment accepted.

The question was deleted from the examination.

1-k'

. _ -~..._... - _._-_ ---.--, _ -.-

U.

S.

NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:

Univ. of Illinois REACTOR TYPE:

ADV TRIGA DATE ADMINISTERED:

90/11/27 REGION:

3 CANDIDATE:

LICENSE APPLIED FOR:

INSTRUCTIONS TO CANDIDATE:

Answers are t9 be written on the exam page itself, or the answer sheet W

' Attach any answer sheets to the examinatlon. rite answers one side ONLY.

provided Points f r each ques ion t.re indicated in parentheses for A70%$neachsectIonisrequiredtopasstheexamination.

each question.

Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY

% OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 21.00 35.b A.

REACTOR THEORY THERMODYNAMICS AND FACILITY OhERATING CHARACTERISTICS 20.00 33.

B.

NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS lWe C.

PLANT AND RADIATION MONITORING SYSTEMS g qg r

-60lr00-4,(T.)

TOTALS Y1ti AL UKAUE All work done on this examination is my own.

I have neither given nor received aid, canaicace's signacure c

g,e

NRC RULES AND GUIDELINES FOR LICE!1SE EXAMINATIONS During the administration of this examination the following rules apply:

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

2. After the examination has been completed,is vour own 6nd you have notyou must sian the statement on the cover sheet indicating that the work donealtery$ucompletetheexamination.gtheexamination.

received ur iven assistance in completin This must be

3. Restroom trips are to he limited and only one candidate at a time may leave.

You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

4. Use black ink or dark pencil only to facilitate legible reproductions.

5. Print your name in the blank provided in the upper right-hand corner of tne examination cover sheet.

6. Fill in the date on the cover sheet of the examination (if necessary).

7. You may write your answers on the examination guestion page or on a separate shoot of paper.

USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

E. If you write your answers on the exam:, nation question age and you need more space to answer a specific quest:,on use a separa e sheet of the er rovided and insert it directl affer the s ecif c question.

DO NOT gggTEgNTHEBACKSIDEOfTHEEXAMIN{rTIONQUESTIOp1PAGE

9. Print your name in the uoper right-hand corner of the first page of each section of your answer sheets whether vou use the examination question pages or sebarate snects of paper.

Initial each page.

10. Before you turn in your examination, consecutively nu d er each answer on the..ncludino any add:.tional pages inserted when writlng your answers sheet examination questnen page.

number each answer as to cateaory and If you are using separate sheets,EPE # 10) and skip at least 3 lines 11.

number i.e. Plant Systems # 04 between(answers to allow space for grading.

12. Write "End of Category" at the end of your answers to a category.

13. Start each category on a new page.

14. Write "Last Page" on the last answer sheet.

15. Use abbreviations only if they are commonly used in f acility literature.

Avoidusingtgymbplssughas<or>signstoavoidasimpletransposition error resu ng in an ncorrect answer.

Write it out

16. The point value for each guestion is indicated

..n parentheses after the question.

The amount of blank space on an exam:. nation question page is NOT an indication of the depth of answer required.

17. Show all calculations, methods, or assumptions used to obtain an answer.

Therefore$: ANSWER ALL PARTS OF THE QUESTION

18. Partial credit mav be given.

NOT partial credit will NOT be AND DO NOT LEAVE ANY ADSWER BLANK.

given on multiple choice questions.

19. Proportional urading will be apolied.

Any additional wrong infomatnon that is prov ded may count aga).hst you.

For examnle if a question.s worth one no} int and asks for four responses each of which.is worth 0.25 n

points,ints.you give five responses, each ofIf one of your Yive responses i incorrect 0.20 will be anB our responses will be worth U.20 po deducted and vour total credit for that cuest on will be,0.80 instead of 1.00 even thoQgh you got the four correct answers.

30. If the intent of a question is unclear, ask questions of the examiner only.

7.1. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets.

In addition, turn in all scrap paper.

22. To pass the examination, you must achieve at least 70% in each category.

23. There is a time limit of (3)than the full examLnation is taken.) hours for completLon of the examination.

.(or some other time if less leave the examin-24.Whenyouaredoneandhaveturnedinyourexamination,dinthisar$a

- at:,on area as defined by th$11 $ miner.n progress, your license may be den ed or ex If you are foun whale the examination is st revoked.

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=

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=

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Page 5 of 5 DOIG_SUEEI elstCLLOWEDUS_1UE0Bd8110U_Icoottouedt:

i-10 CFR 20 Appendix B l..

ji Table !

Table !!

Energy Col I Col Il Col I Col !!

,l MEV per Air Water Air Water i

Material Hal f-! i f e Di si n t egr ati on uc/ml uc/ml uc/ml uc/ml

-6

~0 4x10 Ar-41 1.84 h 1.3 Sub 2x10

~7

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3x10 1x10 1x10 5x10 1-131 0.04 d 0.36 S

9x10~

6x10 1x10"IU 3x10

~D

-7

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9x10 4x10 3x10 1x10 "

~7

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~U

~

~A"

-6 Pu-239-2.41x10 y

0.000 5

2x10 1x10 "

6x10 5x10 4

-12

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1x10~

1x10 3x10

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1x10 Xe-135 9.09 h 0.25 Sub 4x10 Any si,ngle radionuclide with 7 2 > 2 hr

-9

-5

-10

-6 which does not decay by alpha br 3x10 9x10 1x10 3x10 spontaneous fission 2

Neutron Energy (MEV)-

Neutrons per cm Average flux to deliver equivalent to 1 rem 100 mrem in 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months 6

-thermal 970x10 670 6

0.02 400x10 280 (neutrons) 6 0.5 43x10 30 10 24x10 37 c,2 6

x

,,c Linear Absorption Coefficients p (cm~I)

Energy (MEV)

Water Concrete Iron Lead 1

0.5 0.090 0.21 0.63 1.7 1.0 0.067 0.15 0.44 0.77 1.5 0.057 0.13 0.40 0.57 2.0 0.040 0.11 0.33 0.51 2.5 0.042 0.097 0.31 0.49 3.0 0.030 0.089 0.30 0.47

A.

RX THEORY, THERMO & FAC OP CHARS Page 4

QUESTION: 001 (1.00)

Which ONE of the following describes the effect of an overaompensated TRIGA neutron detector on indicated count rate at low power levels:

Higher, since more gammas are counted.

a.

b.

Higher, since more neutrons are counted.

c.

Lower, since fewer gammas are counted.

d.

Lower, since fewer neutrons are counted.

(*****

CATEGORY A CONTINUED ON NEXT PAGE *****)

r

A.

RX TilEORY, Ti!ERl40 & FAC OP CllARS Page 5

i QUESTION: 002 (1.00)

Which ONE of the following is correct with respect to Xenon:

The time to reach equilibrium Xenon from zero power is flux a.

DEPENDE!1T.

The time to reach equilibrium Xenon from a step change from zero b.

power to 50% power is three quarters the time to reach equilibrium xenon from a step change from zero power to 100%.

c.

Equilibrium Xenon concentration is flux INDEPENDE!1T.

d.

Equ:1f br;.um Xenon concentrat:.on at 50% power is one half of equ:.1: br: um Xenon concentrat: on at 100% power.

(*****

CATEGORY A CONTINUED ON NEXT PAGE *****)

A.

RX THEORY, THERMO & FAC OP CHARS Page 6

QUESTION: 003 (1.00)

Wh;,ch ONE of the following is the reason that delayed neutrons al:.ow control of the reactor:

a.

Delaved neutrons decrease the average period for a reactivity addition.

b.

Delayed neutrons increase the a*/orage neutron generation time.

c.

There are more delayed neutrons than prompt neutrons.

andgedneutronsarebornathigherenergiesthanpromptneutrons Dela d.

ake longer to thertualize i

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(*****' CATEGORY A CONTINUED ON NEXT PAGE *****)

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RX TilEORY, Ti!ERMO & FAC OP CilARS Page 7

QUESTION: 004 (1.00)

Which ONE of the following describes a critical reactor:

a.

Effective multiplication factor is zero.

b.

Delayed neutron population decreasing from generation to generati c.

Linear power increase with the presence of an external source.

d.

Neutron population is decreasing from generation to generation.

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(*****

CATEGOhY A CONTINUED ON NEXT PAGE *****)

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RX THEORY, THERMO & FAC OP CHARS Page 8

QUESTION: 005 (1.00)

Which ONE of the following statements is correct:

The effective multiplication factor is the ratio between the number of neutrons in one ceneration and the number of neutrons in the a.

previous generation.

b.

fast neutrons produced by all neutron-induced fissions and the nymbgr of fast neutrons produced by thermal neutron-induced fissions.

c.

thermal neutrons absorbed in the core and the number of thermal neutrons produced in the core.

d.

fast neutrons produced from thermal neutron-induced fissions and the number of thermal neutrons absorbed in the fuel.

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

A.

RX THEORY,.THERMO & FAC OP CHARS Page 9

QUESTION: 006 (1.00) half life of the material:which ONE of the following is the closest to the Given the following data TIME ACTIVITY 0

2400 cps

\\

10 min.

1756 cps 20 min.

1285 cps 30 min.

940 cps 60 min.

368 cps a.

11 minutes b.

22 minutes c.

44 minutes d.

51 minutes l

(*****

CATEGORY A CONTINUED ON NEXT PAGE *****)

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RX THEORY, THERMO & FAC OP CHARS Page 10 QUESTION: 007 (1.00)

Which ONE of the following factors of Keff is MOST affected by the insertion of a SINGLE control rod three inchen:

a.

Fast non-leakage probability.

b.

Resonance escape probability.

c.

Fast fission factor, d.

Thermal utilization factor.

(*****

CATEGORY A CONTINUED ON NEXT PAGE *****)

A.-

RX THEORY, THERMO & FAC OP CHARS Page 11 QUESTION: 008 (1.00, Which ONE of the follow..ng describes why air-followers are included in the design of the trans:.ent control rods:

a.

To allow for withdrawal of the rods, b.

To ensure rods do not exceed the upper stop.

c.

To prevent local flux peaking.

d.

To provide improved accuracy in position indication.

(***** CATEGORY. A CONTINUED ON NEXT PAGE *****)

A.

RX THEORY, THERMO & FAC OP CHARS Page la QUESTION: 009 (1.00)

Which ONE of the following is correct with regard to criticality:

a.

Critical rod height does NOT depend on how fast control rods are withdrawn, Cr:.t:. cal rod height dictates the reactor power level when b.

cr:.t:.cality is f rst achieved c.

The slower the approach to criticality, the lower the reactor power level will be when reaching criticality, d.

The reproduction factor increases due to rod withdrawal during the approach to criticality.

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CATEGORY A CONTINUED ON NEXT PAGE *****)

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RX Ti!EORY, THERMO & FAC OP CilARS Page 13 QUESTION: 010 (1.00)

Which ONE of the following is the MOST accurate definition of the term reactivity:

a.

The rate of change of reactor power in neutrons per second.

b.

The rat:.o between the populations of two successive neutron generat.ons.

c.

The difference between critical and all control rods withdrawn for a given core.

d.

The measure of a reactor's departure from criticality.

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CATEGORY A LONTINUED ON NEXT PAGE *****)

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A.

.RX THEORY, THERMO 6 FAC OP CHARS Page 14 QUESTION:. 011

-(1.00)

WhichONEofthefollowin$1ngwaterpump: conditions will occur during a NORMAL start of the primary forced coo j

a.

With the isolation valves CLOSED, the pump is started, and suction pressure DECREASES.

b.

When the isolation valves are OPENED during-pump operation, pump discharge pressure INCREASES.

i c.

With the isolation valves CLOSED, the pump is started, and suction pressure INCREASES.

d.

When the isolation valves are OPENED during pump operation, pump suction pressure DECREASES.

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A.

RX TIIEORY, TIIERMO & FAC OP CliARS Pago 15 QUESTION: 012 (1.00)

Wh;.ch ONE of the following describes the term "Subcritical Mu..tiplication":

The ratio of fission plus source neutrons divided by the number of a.

fission neutrons.

b.

The multiplication of the source neutrons by the fission neutrons.

c.

The inverse of the multiplication factor minus 1 (1/(Keff-1)).

Is e al to 25 when the reactor is in shutdown conditions and an d.

exte@rnal source does not exist.

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

/s.

RX TIIEORY, TilETWO & FAC OP C}{ARS Page 16 QUESTION: 013 (1.00)

WhichONEofthef$cntonoperationoftheTRIGAreactor:llowing describes the effect of the Fuel Temperature neactivity Coeffic hydrogen atoms in the fuel At WW temperatures in the reactord the energy is transferred to a.

matrix go into an excited state an thermal neutrons.

b.

At LOW temperatures in the reactor, more neutrons are absorbed by the control rods and an increased number are lost by leakage.

At i!}Gil temperatures in the reactor, hydrogen atoms in the fuel ce c.

matr.x help in the moderation of the neutrons.

9 d.

At ilIGli temperatures in the reactor, the thermal utilization and thermal non-leakage probability values decrease.

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A.

RX THEORY, THERMO & FAC OP CHARS Page 17 QUESTION: 014 (1.00)

Which ONE of the following describes the effect of Forced Convective Cooling (vs Natural C'ooling) on reactor operation:

If forced cooling is STOPPED at high power levels there will be a a.

decrease in the power level if the control rods ar,e not moved.

If forced cooling is STOPPED at high power levels posative b.

reactivity is added due to the corresponding incre,ase

.n fuel temperature.

c.

At higher power levels, there is a LARGER delta T in the fuel and cladding,ith forced circulation.which results in a LOWER fuel temperature (thermocouple) reading w le there is SMALLER delta T between the Athigher$ owe [ng,velswhichresultsInaLOWERfueltemperature d.

fuel and c add (thermocouple) reading with forced circulation.

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A.

RX TIIEORY, TilERMO & FAC OP CHARS Page 18 l

Q"iSTION: 015 (3.00)

Which ONE of the following is correct concerning the Fast Non-Leakage Probability:

a.

As moderator temperature INCREASES, the fast non-leakage probability INCREASES.

the fast Astheg.umberofrg{ectorsusedinthecoreINCREASES, b.

non-lea age probabi ty DECREASES c.

As the number of vcids in the core INCREASE, the fast non-leakage probability IliCREASES.

d.

As neutron age IliCREASES, the fast non-leakage probability DECREASES.

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CATEGORY A CONTINUED ON NEXT PAGE *****)

A.

RX THEORY, THERMO & FAC OP CHARS Page 19 QUESTION: 016 (1.00)

Whicli ONE of the following is equivalent to $1 of reactivity in the TRIGA reactor:

a.

delayed neutron fraction (delta k/k).

b.

0.01 delta k/k c.

0.0073 percent delta k/k d.

reactivity when criticality is achieved.

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A.

RX THEORY, THERMO & FAC OP CHARS Page 20 QUESTION: 017 (1.00)

The TRIGA reactor is critical Subsequently an external source is removed from the reactor.

Which ONE of the f,ollowing describes the effects of removing the source:

When the source is removed, power level will decrease...

for a short time (due to a deficiency of the equilibrium fraction a.

of delayed neutrons) before leveling off to a constant value, b.

for a short time (due to a deficiency of prompt neutrons) before leveling off to a constant value.

(due to a def: ciency of the equilibr: un fraction of delayed c.

neutrons) unt:.1 the reactor is subcr:.tical.

d.

(due to a deficiency of prompt neutrons) until the reactor is subcritical.

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A.

RX Ti!EORY, TIIERMO & FAC OP CilARS Paga 21 QUESTION: 018 (1.00)

Which ONE of the following are two of the three MAIN poisons in the TRIGA reactors a.

Moderator and Control Rods, b.

Xenon and Fuel Cladding, c.

Control Rods and Samarium.

d.

Moderator and Xenon.

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A.

RX THEORY, THERMO & FAC OP CHARS Page 22 QUESTION: 019 (1.00)

The TRIGA reactor has been operating at steady state power for one week.

Which ONE of the following describes Xenon in the reactor:

a.

Xenon formation IS DEPENDENT on the number of Xenon atoms.

b.

Xenon burn-out IS DEPENDENT on the neutron flux.

c.

Xenon formation IS NOT DEPENDENT on the neutron flux.

d.

Xenon decay IS NOT DEPENDENT on the number of Xenon atoms.

i

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A.

RX THEORY, THERMO & FAC OP CHARS Page 23 QUESTION: 020 (1.00)

Which ONE of the following will INCREASE the worth of a rod (consider all conditions separately):

a.

Coolant temperature goes from 108 degrees F to 100 degrees F.

i b.

Xenon-135 change shortly after a power decrease.

c.

Rod is moved closer to the core periphery.

l d.

An adjacent rod is withdrawn.

l-l

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i A.

RX THEORY, THERMO & FAC OP CHARS Page 24 QUESTION: 021 (1.00) hggh gli{

f the following is correct concerning the Resonance Escape INCREASES, the Resonance Escape tiosssilityEiChiiSis."-238 d

IN REASE the Resonance Escape

$!osasiffyrin8KEAsiB?ratur b-1

'53 c.

As the number of volds DECREASES, the Resonance Escape Probab.l DECREASES.

,', 'J k d.

As the broadness of the U-238 resonance peaks INCREASE, the Resonance Escape Probability INCREASES.

-c

(*****

END OF CATEGORY A *****)

0

B.

NORMAL /EMERG PROCEDURES & RAD CON Page 25 QUESTION: 001 (1.00)

In accordance with the Radjat19n Safety Manual, which ONE of the following describes the normal location in which dosimetry should be worn while working in radiation areas:

a.

Between the knee and waist.

b.

Inside the shirt pocket.

c.

Between the hip and shoulder.

d.

Inside the pants pocket.

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}

<. 'i;OREBL/EMERG PROCEDURES & RAD CON Page 26 QUESTION: 002 (1.00)

For the radiation hacards identified below which ONE of the following delineates the hazards from LEAST hazardous,(most harmful to the body):(least harmful to to MOST hazardous 1.

External exposure to neutrons 2.

External exposure to beta radiation 3.

Ingesting radioactive materialy into the body 4.

External exposure to gamma radiation a.

2, 4,

3, 1

b.

2, 4,

1, 3

c.

4, 2,

3, 1

d.

4, 2,

1,.3

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 27 QUESTION: 003 (1.00)

Which ONE of the following descr..bes the status of the Auxiliary Coolino System (dance with " Reactor Shutdown":when shutt:.ng down the reactor at the end of the day Purification) in accor PRIMARY SECONDARY a.

Left In Operation Left In Operation b.

Left In Operation Shut Off c.

Shut Off Left In Operation d.

Shut Off Shut Off

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 28 QUESTION: 004 (1.00) which ONE of the In accordance with " Reactor Start-Up And Operation"fervals no greater following sets of parameters must be recorded at in than 30 minutes for th9 first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for continuous operation.

Assume power level of 75 kW with minimum cooling required:

a.

1.

bulk water temperature 2.

fuel temperature 3.

reactor tank level b.

1.

rod position 2.

reactor tank level 3.

bulk water temperature c.

1.

reactor tank level 2.

rod position 3.

fuel temperature d.

1.

rod position bul}i; water temperature 2.

fue temperature 3.

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 29 Eb QUESTION: 005 (1.00)

)

AtraineoinadvertentlypushesIhemanualtripbutton,WhchONEofthefollowingactons$ately but ortu the reactor does not scram.

s required:

Fill out a deficiency report and continue power operation if required for experiments, a.

b.

... verify automatic trips are operational.

)

shut down the reactor.

c.

Jj d.

... evacuato the control room, l

I

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 30 QUESTION: 006 (1.00)

Wh:.ch ONE of the following would reautre a manual trip $f the reagtor was than F or(Assume a core with low hydride fuel elements installed in other cr;.tical G hexagonal):

LOCATION OF FUEL ELEMENT FUEL TEMPERATURE a.

B - hexagonal 375 degrees F b.

C - hexagonal 375 degrees F c.

D - hexagonal 375 degrees F d.

E - hexagonal 375 degrees F

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 31 QUESTION: 007 (1.00)

Which ONE of the following is a condition that must be met for the reactor to be considered secured in accordance with Technical Specifications:

a.

An SRO is in charge of any work in progress on the control rods, e inserted to assure subcriticality by Sufficientcontrolrodsa{ty b.

at least $1.00 of reacti c.

Fuel elements are removed from the core.

d.

All control rods are fully inserted into the core.

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 32 QUESTION: 008 (1.00)

Prior to a reactor startup, it is discovered that total transient rod worth is $4.55.

Which ONE of the following actions should be taken:

a.

Startup the reactor if all conditions (except transient rod) are satisfactory.

b.

Deenergize 1 transient rod, then startup may be commenced.

c.

Limit reactor power to 250 kW.

d.

Do not proceed with the startup.

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B.

NORMAL /EMERG PROCEDURES & RAD CON page 33.

QUESTION: 009 (1.00)

Which ONE of the following conditions has a Technical Specification Reactivity Limit of $5,00 Reactivity worth of a single experiment if only 2 experiments are a.

in the reactor.

b.

Excess reactivity.

c.

Total reactivity worth of all experiments, d.

Maximum reactivity worth of all non-transient control rods.

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 34 QUESTION: 010 (1.00)

Which ONE of the following is the reason that the secondary cooling system is started before the primary cooling system:

a.

Ensure adequate heat removal capabilities are available for the primary system, b.

Provent the release of radioactive effluents to the environment, Avoid placing a heavy load on the secondary pump while it is coming c.

up to speed d.

Minimize leakage from the secondary system into the primary system.

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 35 QUESTION: 011 (1.00)

A 21 year old radiation worker muet work in a radiation field of 20 mrom/hr.

He has already received a cumulat$ve dose of 0.85 rem during this quarter.

Which ONE of the followinc is the MAXIMUM time he can work in the 20 mrem /hr field without exceeding his normal (10CFR20) quarterly whole body limit:

a.

0.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months b.

20.0 hours0 days 0 hours 0 weeks 0 months c.

40.0 hours0 days 0 hours 0 weeks 0 months d.

200.0 hours0 days 0 hours 0 weeks 0 months

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B.-

NORMAL /EMERG PROCEDURES & RAD CON Page 36 QUESTION: 012 (1.00)

Which ONE of the following posting /hr per 10CFR20:s is required for an accessible area with a radiation level of 150 mrem

-a, restricted area b.

radiation area c.

high radiation area d.

exclusion area 1

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D.

NORMAL /EMERG PROCEDURES & RAD CON Page 37 QUESTION: 013 (1.00)

Which ONE of the following would require an immediate shutdown during a startup-of the TRIGA reactor (assume a reactor power of 250 kW):

a.

Loss of primary forced cooling water, b.

Unplanned radiation alarm.

c.

Loss of the facility ventilation system.

d.

Incomplete health physics daily checklist.

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 38 QUESTION: 014 (1.00)

Which ONE of the following activities requires a Senior Reactor Operator to be present at the TRIGA operating console:

a.

Reactor operation with an open beamport, b.

Startup following an unscheduled scram, c.

Changes to the primary cooling line-up, d.

Changes to the " shielding configuration" around the beam ports.

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1

B.

NORMAL /EMERG PROCEDURES & RAD CON Page 39 QUESTION: 015 (1.00)

Which ONE of the following would be ind4cative of a MAJOR primary system leak (vs. a MINOR leak in accordance with " Potential Malfunction of Systems or Components"):

a.

Sump lights in the tunnel are lit, b.

Summary of the water make-up to the reactor tank indicates make-up required c.

Sump lights in the vault are lit.

d.

Frequent operation of the 3 gpm solenoid.

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 40 QUESTION: 016 (1.00)

In accordance with " Installation And Removal Of Items In Core Region Of which ONE of the follcwing provides positive indication that Reactor", handling tool is in the locked position and firmly engaged on the fuel the fuel element:

a.

1.

Visual observation 2.

Slight jerking motion with the tool aid b.

1.

V;sugl observation 2.

W:, thin 100 lbs. of design fuel weight on scale c.

1.

Slight jerking motion with the tool aid 2.

Observing proper neutron flux increase in nuclear instrumentation d.

1.

Observing proper neutrgn flux increase in nuclear instrumentation 2.

Within 100 lbs. of design fuel weight on scale

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 41 l

QUESTION: 017 (1.00)

Which ONE of the fol1 wing would exceed the Power Operation Restrictions 9

as set forth in " Contingency Procedupe: Isolation Valves Not Operative".

(Power is provided for a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

Assume linear power changes):

a.

0800 0.1 MW 1100 0.3 MW 1800 0.5 MW 2400 0.3 MW 0800 0.1 MW b.

0800 0.0 MW 1200 0.5 MW 1300 1.5 MW 1400 0.2 MW 0800 0.0 MW c.

0800 0.25 MW 1400 0.25 MW 2000 0.25 MW 0200 0.25 MW 0800 0.25 MW d.

0800 0.0 MW 1400 0.1 MW 1800 0.2 MW 2400 0.3 MW 0800-0.4 MW l-l l

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.B.

NORMAL /EMERG PROCEDURES & RAD CON Page 42 JOUESTION:'018 (1.00)

The' reactor is at 1.0 MW.

An attempt to return a sample from the reactor

.using the MRL Pneumatic Transfer (Rabbit) System is unsuccessful, and the problem cannot be resolved.

Which ONE of-th9 following describes the actions that should be taken in accordance with "Use Of The MRL

. Pneumatic Transfer (Rabbit) System":

a.

Maintain power and initiate an investigation of and repair to the system.

b.

If--the sample cannot be returned within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , perform a controlled reactor shutdown.

c.

Perform a controlled-reactor shutdown.

d..

SCRAM the reactor and initiate' repair of.the-system.

1:

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 43 QUESTION: 019 (1.00)

Which ONE of the following in accordance with " Tornado Response" would require the operator to SCbiM the reactor:

a.

Notification via the telephone alert system that a tornado has been sighted on campus.

b.

Three one minute blasts of the siren occurs, warning of a tornado on

campus, c.

Visual observation of strong winds and hail on campus, d.

Campus meteorological department declares a Tornado Watch.

l

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 44 QUESTION: 020 (1.00)

]

Which ONE of the following describes the operation of the Emergency Core Spray System:

to verify The Emergency Core Spray System shall be operatedgallons pe(1) that it is capable of spraying (2) r mT6K6 on the core.

{!} tR"!D Y

{ssfi"s"Y

{s} VR?sP

{s)VissY d-(*****

END OF CATEGORY B *****)

C.

PLANT AND RAD MONITORING SYSTEMS Page 45 QUESTION: 001 (1.00)

Which ONS of the following' excess::.bes how the count-rate channel fission descr counter is protected from

.ve burnout at high power levels:

a.

The fission counter is withdrawn from the core, b.

Power is removed from the fission counter, Fission counter operation is limited to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months time c.

period.

d.

Frequent surveillance is performed on the fission counter to detect degradation.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

C.

PLANT AND RAD MONITORING SYSTEMS Page 46 j

QUESTI 02 (1.00)

Which ONE b the following dgscribes the configuration of the TRIGA reacter duri normal operation:

a.

1.

D-7 con ins the Adjustable Transient Rod 2.

D-16 con Ains the External Source 3.

G-2 contains the Fast Transient Rod 4.

G-35 contain the MRL Pneumatic System b.

1.

D-7 contains the Adjustable Transient Rod 2.

D-16 contains thq Fast Transient Rod G-2containstheIxternalSou[cc 3.

G-35 contains the MRL Pneumat c System 4.

c.

1.

D-7 contains the External Source 2.

D-16 contains the MRL Pneumatic System 3.

G-2 contains the Adjust &ble Transient Rod 4.

G-35 contains the Fast Tr nsient Rod d.

1.

D-7 contains the Extgrnal Source 2.

D-16 contains the Adjustable \\ Transient Rod 3.

G-2 contains the MRL PneumaticsSystem 4.

G-35 contains the Fast Transient Rod b.O (fd lYd')f0D

((In $

l

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'C..

PLANT AND RAD MONITORING = SYSTEMS Page-47 fQUESTION: 003 (1.00).

i

.Which ONE of the-following describes an interlock associated with the rod control system:-

In the steady-state modo, application of air to the adjustable a.

- ransient rodLcannot be made unless the rod cylinder is fully nserted.

In the' steady-state mode the simultaneous. withdrawal of more than one b.

motor-driven rods cannot,be done.

In the-steady-state mode the withdrawal of only one transient rod c.

with the other. rods remov,ed from their down position is permitted.

rod is permitted., the withdrawal of only one manually operated In the-pulse mode

'd.'

o p

,.s.

l

(.

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5

C.

PLANT AND RAD MOllITORING SYSTEMS Page 48 QUESTION: 004 (1.00)

Which ONE of the following describes the operation of the Heat Removal Control System:

a.

For LARGE power INCREASES, flowrate through the cooling tower is DECREASED to control heat removal, For LARGE power INCREASES,to control heat removal, primary flowrate is DECREASED and secondary b.

flowrate is HELD CONSTANT flowrate through the cooling towers ForSMALLgowerINCREASES,D to control heat removal c.

is INCREAS For SMALL power INCREASES,to centrol heat removal. primary flowrate is DECREASED and secondary d.

flowrate is HELD CONSTANT i

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C..

PLANT.ANDLRAD. MONITORING SYSTEMS Page 49

- QUESTION: 005-

-(1. 0 0)

~Which ONE of the following-describes the operation of the core isolation

. valves:

When~the isolation valves' receive a signal to close,ing time of a valve retards a.

the rate of air leaving the piston to provide a clos greater than 10-seconds, b.

When the isolation valves receive a signal to close, the primary pump shuts down to prevent water hammer in the pipes.

c.

A solenoid valve on the actuator closes the' isolation valves.when 70 psi is supplied.from the pneumatic system.

'd.

A-five second isolation valve closing time is designed-into the system to allow the momentum of the coolant to be dissipated.

4 8

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,- - r

C.

PLANT AND RAD'MO!!ITORING SYSTEMS Page 50 QUESTION: 006 (1.00)

Which ONE of the following describes the locations of the coolant temperature sensors:

a.

1.

entrance to core 2.

return line from cooling towers 3.

discharge of prlmary pump 4.

entrance to cooling towers b.

1.

secondary exit from heat exchanger 2.

entrance to core 3.

return line from cooling towers 4.

entrance to cooling towers c.

1.

secondary exit from heat exchanger 2.

discharge of primary pump 3.

exit from core 4.

entrance to cooling towers d.

1.

entrance to core 2.

secondary exit from heat exchanger 3.

return line from cooling towers 4.

exit from core i

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C.

PLANT AND RAD MONITORING SYSTEMS Page 51 QUESTION: 007 (1.00)

Which ONE of the following describes the operation of the adjustable transient control rod:

The Adjustable Transient Control Rod

.s pneumatically inserted and withdrawn by either decreasing or a.

.ncreasing the pressure on the cylinder.

b.

remains inserted in the core except when air is re;_aved from the cylinder.

c.

is electromechanically inserted and withdrawn by adjusting the position of the cylinaer, electr{rolledbythepistonbyvaryingthevoltagetothe is con d.

c drive

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C.

PLANT AND RAD MONITORING SYSTEMS Page 52 I

QUESTION: 008 (1.00)

Which ONE of the following describes the operation of the Control Rods:

The upper stop of one of the two transient rods can be adjustol only a.

when air is applied, b.

Both transient rods have air-followers to prevent flux peaking in the area when the rod is fully inserted, The manually driven rods are manually Qriven by motors, which allow c.

rods to travel a total distance of 18 inches, more even flux distribution ir. the core.y-driven rods to gain a Fuel-followers are used with the manuall d.

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C.

PLANT AND RAD MONITORI!4G S'! STEMS Page 53 6,

QUESTION: 009 (1.00)

Which ONE of the following describes the operation of the start-up instrumentation channel:

a.

It utilizes a BP3 tube which gives about 8 cps with the reactor shutdown.

b.

It utilizes a fission chamber with an interlock that prevents withdrawal of manually-driven rods when a count rate of I cps exists.

It utilizes a compensated ion chamber,t panel.in which compensating c.

voltage adjustment ic made on the fron It utilizo an uncompensated ion chamber, which provides indication d.

upto30kglowatts l

t i

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C.

PLANT AND RAD MONITORING SYSTEMS Page 54 QUESTION: 010 (1.00)

The TRIGA reactor is beino operated in the square wave mode.

The ad1ustable transient rod is fired and power has stabilized at 500kW.

Which ONE of the following conditions Would cause an automatic reactor scram:

a.

Primary coolant pump trip.

b.

A reactor period of 2 seconds occurs.

c.

Two area radiation alarms are received.

d.

Linear power channel fails upscale.

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C.

PLANT AND RAD MO!11 TORI!1G SYSTEMS Page 55 QUESTIO!!! 011 (1.00)

Which ONE of the following TRIGA reactor control circuits provides an interlock to prevent a sourcoless startup:

a.

Log Count-Rate Channel b.

Log-N Channel c.

Linear Micromicroammeter Channel d.

Percent Power Channel

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C.

PLAllT AllD RAD MO!11 TORI!1G SYSTEMS Page 56 QUESTIO!1: 012 (1.00)

Which ONE of the following Radiation Monitoring Channels would be in alarm based on the given readings (Assume norm 61 settings are set):

a.

Channel 1 (Reactor Top) indicates 180 mR/hr.

b.

Channel 2 (Domineralizer) indicates 5 mR/hr.

c.

Channel 3 (Storage Cage) indicates 18 mR/hr.

6.

Channel 4 (Thermal Column) indicates 24 mR/hr.

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C.

PLANT AND RAD MONITORING SYSTEMS Page 57 Q'IESTION : 013 (1.00)

Which ONE of the follownng actions would occur in the event of high count rates on the Cont: nuous Air Particulate Monitor:

The Building Exhaust System would automatically REDIRECT air flow through the HEPA filters to remove 100% of particles above 0.3 microns a.

in size.

b.

HEPA filters to assure the removal of iodino particulates.

charcoal filters to remove 99.97% of particles above 0.3 c.

microns in size.

d.

charcoal filters to assure the removal of iodine particulates.

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C.

PLANT AND RAD MONITORING SYSTEMS Page 58 I

QUESTION: 014 (1.00)

The TRIGA reactor is operating at 1.2 MW with a primary forced cooling system flow rate of 1500 gpm.

Subsequent 1v the primary centrifugal D mp trios off and cannot be restarted.

Which ONE of the following k 11 occbr:

The primary forced cooling system throttle valve will fully open a.

to provide additional flow.

b.

The secondary flow throttlina valve will fully open to provide additional cooling of the primary flow.

c.

The reactor will scram when forced cooling system flow decreases to less than 550 gpm.

d.

The reactor will scram when the primary temperature increases to 40 degrees C.

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C.

PLANT AND RAD MONITORING SYSTEMS Page 59 QUESTION: 015 (1.00)

Which ONE of the following describes the automatic operation of the i

Emergency Core Spray Cooling System.

If Reactor Tank level decreases to...

provided from the domineral;.z,ers.pm of spray flow will be 10 inches below normal leve:.

3g a.

provided from the domineraliz,ers. gpm of spray flow will be 15 inches below normal level 5-8 b.

18 inches below normal level, 3 gpm of spray flow will be c.

provided directly from city water.

provideddgelownormallyvel,ter20 gpm of spray flow will be 21 inchen d.

rectly from c ty wa i

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P C.

PLANT AND RAD MONITORING SYSTEMS Page 60 QUESTION: 016 (1.00)

Which ONE of the following

..s the reason the aluminum tube used to insert camples into the central thamble contains a bend:

a.

Prevent water leakage from the reactor pool, b.

Ensure sample removal can be made within maximum Technical Specification time limits.

c.

Prevent radiation streaming from the core.

d.

Ensure samole insertion does not result in exceeding Technical Specification reactivity insertion limits.

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1 C.

PIANT AND RAD MONITORING SYSTEMS Page 61 QUESTION: 017 (1. 00)

Which ONE of the following describes why lead is used in the outer corc region:

1 a.

To minimize gamma heating of the concrete.

b.

To provide a radiological shield for lab workers.

i c.

To improve fuel efficiency.

l d.

To prevent neutron Icakage from the core.

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C.

PLANT AND RAD MONITORI!JG SYSTEMS Page 62 QUESTION: 018 (1.00)

Which ONE of the following is the function of the delay tanks:

a.

Slow the flow to prevent pipe damage.

b.

Allow time for the decay of N-16.

c.

Ensure adequate net positive suction head for the primary pump, d.

Provide emergency water source.

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C.

PLA!1T AllD RAD MONITORIllG SYSTEMS Page 63 1

l QUESTIOll: 019 (1.00)

Which ONE of the following describes why flow through the purification l

loop is limited to 2-3 gpm:

To prevent clogging the filter at the bottom of the resin tank.

a.

b.

To ensure adequate flow through the heat exchanger.

c.

To avoid streaming in the resin tank.

d.

To prevent pump cavitation.

- - - END OF CATEGORY C *****)

(*****(******

END OF EXAMINATION **********)

A.

RX THEORY, THERMO & FAC OP CHARS Page 64 AllSWER:

001 (1.00) d.

REFERENCE:

NE351, pg.

1-8.

I AllSWER:

002 (1.00) a.

REFERENCE:

.NE390R, pg. 1-31.

A!!SWER:

003 (1.00) b.

REFEREllCE:

lie 390R, pg. 1-19.

ANSWER:

004 (1.00) l --

C.

(

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A.

RX THEORY, THERMO & FAC OP CHARS Page 65 REFEREllCE:

!!E3 90R, pg. 1-27.

ANSWER:

005 (1.00) a.

FEFEREllCE :

NE390R, pg. 1-21 AllSWER:

006 (1.00) b.

REFEREllCE:

llE390R, pg. 1-30.

ANSWER:

007 (1.00) d.

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A.

RX THEORY, THERMO & FAC OP CHARS Page 66

REFERENCE:

NE390R, pg. 1-23 and 1-22.

ANSWER:

008 (1.00) c.

REFERENCE:

NE351, Reactor Operations, pg.

1-9.

ANSWER:

009 (1.00) a.

REFERENCE:

NE351, pg. 1-13.

ANSWER:

010 (1.00) d.

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,.y e.

A.

RX TiiEORY, Tl!ERMO & FAC OP CilARS Page 67 REFERE!1CE:

llE390R, pg. 1-26.

AllSWER:

011 (1.00) d.

REFERE!1CE:

11E390R, pg. 1-41.

A!1SWER:

012 (1.00) b.

REFERENCE:

11E3 51, pg.

1-2.

ANSWER:

013 (1.00) d.

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A.

RX THEORY, THERMO & FAC OP CHARS Page 68 REFEREllCE:

NE351, pg.

1-5.

ANSWER:

014 (1.00) a.

RLFERENCE:

NE351, pg.

1-6.

A!1SWER:

015 (1.00) d.

REFERENCE:

NE390R, pg. 1-21.

ANSWER:

016 (1.00) a.

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A.

RX THEORY, THERMO & TAC OP CHARS Page 69

REFERENCE:

NE390R, pg. 1-26.

ANSWER:

017 (1.00) a.

REFERENCE:

NE390R, pg. 1-27.

ANSWER:

018 (1.00) c.

REFERENCE:

NE390R, pg. 1-30.

ANSWER:

019 (1.00) b.

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CATEGORY A CONTINUED ON NEXT PAGE *****)

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A.

RX THEORY, THERMO & FAC OP CHARS Page 70 PEFERENCE:

lie 390R, pg. 1-31.

ANSWER:

020 (1.00) d.

REFERENCE:

NE351, pg.

1-6.

A!!SWER:

021 (1.00) a.

REFERENCE:

NE390R, pg. 1-22.

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END OF CATEGORY A *****)

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B.

HORMAL/EMERG PROCEDURES & RAD CON Page 71 ANSWER:

001 (1.00) c.

REFERENCE:

Radiation Safety Manual, Section 1B, pg.

4.

ANSWER:

002 (1.00) b.

REFERENCE:

Radiation Safety !!anua.1, pa. 1 ANSWER:

003 (1.00) b.

REFERENCE:

Reactor Shutdown, pg.

1.

ANSWER:

004 (1.00) d.

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B.

NORMAL /EMERG PROCEDURES & RAD COli Page 72 REFERE!1CE:

Reactor Start-Up And Operation, pg.

3.

ANSWER:

005 (1.00) c.

REFERE!!CE:

Technical Specification 3.5, pg. 14.

ANSWER:

006 (1.00) d.

REFERENCE:

Technical Specification 2.2, pg.

5.

ANSWER:

007 (1.00) b.

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B.

NORMAL /EMERG PROCEDURES & RAI) col 1 Page 73 REFERE11CE:

Technical Specifications, Definition 1.2, pg.

1.

AllSWER:

000 (1.00) a.

REFEREllCE:

Techniwal Specification 3.1.

A!1SWER:

009 (1.00) c.

REFEREllCE:

Technical Specification 3.1.

AllSWER:

010 (1.00) b.

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D.

NORMAL /EMERG PROCEDURES 6 RAD CON Page 74

REFERENCE:

NE390R, pg. 1-40.

ANSWER:

011 (1.00) b.

REFERENCE:

10CFR20 ANSWER:

012 (1.00) c.

REFERENCE:

10CFR20 ANSWER:

-013 (1.00) b.

l

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B.

110RMAL/EMERG PROCEDURES & RAD CON Page 75

REFERENCE:

Rules and Regulations, jg.

8.

ANSWER:

014 (1.00) b.

REFERENCE:

Rules and Regulations, pg. 4 and 5.

ANSWER:

015 (1.00) d.

REFERE11CE:

Potential Malfunction of Systems or Components, pg.

3.

A11SWER:

016 (1.00) a.

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 76 REFEREllCE:

Installation And Removal Of Items In Core Region Of Reactor ANSWER:

017 (1.00) a.

REFERENCE:

Contingency Procedure: Isolation Valves Not Operative.

ANSWER:

018 (1.00) c.

REFERENCE:

Uso Of The MRL Pneumatic Transfer (Rabbit) System, pg.

3.

ANSWER:

019 (1.00) a.

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l!-

B.

110RMAL/EMERG PROCEDURES & RAD COli Page 77 REFEREliCE :

Tornado Response, pg.

1.

AllSWER:

020 (1.00) c.

P EFEREliCE :

Technical Specification 4.4, pg. 24.

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END OF CATEGORY B *****)

7

C.

PLAllT AND RAD MONITORING SYSTEMS Page 78 ANSWER:

001 (1.00) a.

REFERENCE:

FSAR, pg. VII-5 and VII-7.

A11SWER:

002 (1.00) b-hb 6D (Ilo'))90

REFERENCE:

(,w g e

Facility Design, pgs. 1-35 and 1-36.

'N ANSWER:

003 (1.00) a.

REFERENCE:

FSAR, pg. VII-29.

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l

hhhnka$ShefhicSklok'3.3

, ANSWER:

012 (1.00) d.

l

REFERENCE:

l Instructions For Completing Health Physics Daily Checklist.

l l

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C.

PLANT AND RAD MONITORING SYSTEMS Page 82 ANSWER:

013 (1.00) cl.

REFERENCE:

NE390R, pg. 1-42.

ANSWER:

014 (1.00) c.

REFERENCE:

NE390R, pg. 1-37 and 1-39.

ANSWER:

15 (1.00) a.

REFERENCE:

FSAR, pg. '< I - 8

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--rww r,

w n-w-

-C.-

PLANT AND RAD MONiTOPING SYSTEMS Page 83 AN3WER:

016 (1.00) c.

REFERENCE:

NE390R, pg. 1-36.

~ ANSWER:

017 (1.00) a.

REFERENCE:

NE390R, pg. 1-36.

ANSWER:

018 (1.00) b.

REFERENCE:

NE390R, pg. 1-39.

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C.

PLANT AND RAD MONITORING SYSTEMS Page 84 ANSWER:

019 (1.00)

C.

REFERENCE:

NE390R, pg. 1-38.

( * * *

f ** ** ** ** ** EN D O F C ATEGORYEN D OF EXAMIN ATIOt! * *

C *****

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