ML20137N816

Exam Rept 50-151/OL-86-01 on 860115 & 16.Exam Results:Senior Reactor Operator Candidate Passed

ML20137N816
Person / Time
Site:	05000356, University of Illinois
Issue date:	01/29/1986
From:	Higgins R, Mcmillen J, Mcmiller J, Reidinger T ILLINOIS, UNIV. OF, URBANA, IL, NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20137N802	List: ML20137N799 ML20137N816
References
50-151-OL-86-01, 50-151-OL-86-1, NUDOCS 8602040257
Download: ML20137N816 (42)

Text

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U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-151/0L-86-01 Docket Nos. 50-151 and 356 Licenses No. R-115 and 117 Licensee: University 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: January 15 and 16,1986 Examiners:

R. L. Hig ins ll2.9ff(

Date

$, V T. D. Reidinger/ /l27 Date w l'.

Approved By: .

. McMi len, Chief perating Licensing Section

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,7 Examination Summary Examination administered on January 15 and 16, 1986 (Report No. 50-151/0L-86-01) to one senior reactor operator candidate.

Results: The senior reactor operator candidate passed.

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e REPORT DETAILS

1. Examiners

• R. L. Higgins T. D. Reidinger

• Chief Examiner

2. Examination Review Meeting An examination review meeting is no longer conducted. Fa'cility ccarcents, follcwed by the NRC response, are listed below.

Question H.03. Fac_il_ity_ Cogrrent:

Answer should refer to the cell effect as the behavior of Zr H 7 provides abcut 55'a of the negative fuel temperature coefficient. DoppidtBroadening is a secondary effect and is respcnsible for about 20% of the negative fuel ter.perature coefficient. Reference NE 390 notes Section A Reactivity Coefficient Fuel Temp.

NRC Response:

Ag ree . The answer was changed to: "The basic reason for this reactivity decrease comes frcm heating the zirc hydride that is mixed with the fuel. As temperature is increased, the hydrogen atcms go into a vibraticnal state with an energy of 0.13 ev and may go to a second state with an energy of 0.26 ev. When a thermal neutron (0.025 ev) collides with the hydrogen atom, the energy is transferred and hence the neutron is essentially de-thermalized. (1.0)

Part of the reactivity decrease is also attributed to the Doppler broadening. The resonance peaks are broadened due to the heating of U-238, which increases the resonance absorption as the neutrons slow down." (1.0)

Question H.05~ Facility Conment:

First part of answer on antirony should not be necessary to answer the question asked.

NRC Response:

Disagree. Antimony - berylium is a secondary source: the antin.ony is stable until it absorbs a neutron. This fact rust be mentioned in order to receive full credit.

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r Question H.06.a. Facility Comment:

First sentence of question is ambiguous.

NRC Response:

Agree. The question should have been phrased: " Assuming a neutron source strength of 100 counts per second, . .. The examinee had no problem interpreting the question during the examination.

Question H.06.b. Facility Comment:

Will solve with natural logs. Answer will be nearly the same.

.001 = Keff" In.001 = In.999 n n = In.001 = 6904 gen.

in.999 Could also have used n = In.001

.001 as in Keff = .999 approximately equal to .001 NRC Response:

Agree. Either of the above methods is satisfactory and will be awarded full credit.

Question H.08. Facility Comment:

Answer is correct for LOPRA but incorrect for TRIGA, it is also correct if one assumes no reactivity change associated with removal of the source. In the TRIGA removal of the source includes removal of a void from the core and hence a positive reactivity addition so power would increase.

NRC Response:

Agree. If the examinee specifies in his answer the specific reactor he is describing, either of the above answers will be awarded full credit.

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Question H.10. Facility Comment:

Not very relevant.

NRC Response:

Disagree. Though no xenon oscillations occur in the TRIGA or LOPRA, xenon oscillations are described in facility literature and are thus legitimate examination topics.

Question I.05.a. Facility Comment:

There is only one damper in the exhaust system. This was corrected in some SAR Drawings and is correct in the 390R Drawings.

NRC Response:

Agree. The answer was modified to eliminate all reference to the damper in the main exhaust duct. The facility is admonished to correct the

erroneous reference material. It is impossible to create an accurate answer key if the facility reference material is filled with incorrect information.

Question I.06. Facility Comment:

Not Necessary NRC Response:

Disagree. The phrase was taken word-for-word from the TRIGA FSAR. If the delay tanks are not necessary, the facility literature should be revised to reflect this. In any event, the word "necessary" does not affect question interpretation.

Question I.08. Facility Comment:

This has changed a great deal over the years. Reactor personnel are also not involved. We call the health physics office.

NRC Response:

Partially agree. The answer for part "a" was changed to " Notify the health physics office to arrange for disposal." The facility literature should be changed to reflect current solid waste disposal procedures.

Though reactor personnel do not personally package or transport solid waste they nevertheless should know which organization must be contacted in order to properly dispose of solid waste.

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Question I.09. Facility Comment:

Same as I-8.

NRC Response:

Partially agree. The answer key was modified to also grant credit for the response " Notify the health physics office to arrange for disposal."

Question I.12. Facility Comment:

Answer is only in case evacuation is necessary. Otherwise he only scrams the reactor.

NRC Response:

Disagree. This question is taken from the Radiation Emergency Plan.

If the procedure should be revised, the facility should revise it.

Question J.02. Facility Comments:

Two facility comments were made, and the NRC will respond to each one.

Facility Comment 1:

Not relevant.

NRC Response:

Disagree. The term " albedo" is mentioned in the LOPRA SAR, and the examinee should understand what it means.

Facility Comment 2:

In this case albedo refers to reflected neutrons.

NRC Response:

Agree. The answer was changed to "The fraction of neutrons reflected."

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Question J.10. - Facility Comment:

The Shim Rod is not used to maintain power on the squarewave. The

" Slave" system does not work because the shim differential rod worth and Reg rod worths are not the same when the change over is made (i.e., Reg out to shim out, Reg in).

NRC Response:

All mention of the shim rod being automatically adjusted was removed in the answer key. Facility literature should be revised to reflect current operating practices.

Question K.01.b. Facility Comment:

Values range from .3 to .5 C/ division.

NRC Response:

Agree. The answer key was changed to "$.003 to $.005."

Question K.01.e. Facility Comment:

60$ - last amendment to Technical Specifications on LOPRA.

NRC Response:

Agree. The answer key was changed to "$.60."

Question K.02.a. Facility Comment:

Second tool is kept in the TRIGA Tank.

NRC Response:

Agree. The answer was changed to require the mention of a second tool in the TRIGA tank in order to receive full credit.

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Question K.05.c. Facility Comment:

Correct setpoints are:

high level (stop primary pump, close valves, high level scram)

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-1 3 gpm flow stops

-6 8 gpm flow starts

-12 low level (stop primary pump, close valves; low level scram)

NRC Response:

Agree. The answer was changed to reflect these revised setpoints. The facility is a admonished to revise its literature to reflect actual plant setpoints.

Question K.07. Facility Comment:

1. No longer moved due to broken winch.

2. First answer is required only if LOPRA is made inoperative by Technical Specification Definition.

NRC Response:

1. Agree. Moving the assembly is one of two possible correct responses.

Full credit will be awarded if the examinee states: " place a neutron-absorbing screen between the thermal column and the LOPRA."

2. Disagree. This is required by the LOPRA SAR and is therefore required for full credit. The facility is admonished to revise its literature to reflect current operating practices.

Question L.08. Facility Comment:

Hopke's Lab is the Environmental Studies Institute.

NRC Response:

Agree. Full credit will be awarded if "Hopke's Lab" is used instead of

" Environment Studies Institute Annex."

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Question L.14. Facility Comment:

Could have picked a more meaningful definition.

NRC Response:

Disagree. " Shutdown Reactivity" is a fundamental term with which the examinee should be familiar.

3. Exit Meeting On January 16, 1986, at the conclusion of the oral examination, the chief examiner held an exit meeting with facility representatives Craig Pohlod, the Reactor Supervisor, and Gerry Beck, the former Reactor Supervisor.

The chief examiner informed the facility representatives that the SR0 candidate clearly passed the oral and plant walk-through portions of the SR0 examination.

The following additional items were mentioned:

1. The literature used by the Chief examiner to prepare for the examination was incorrect and incomplete. The facility representatives agreed and assured the chief examiner that the literature would be corrected prior to the next NRC license examinations.

2. The components (pipes, valves, heat exchangers) were not labeled.

3. Some portions of the Reactor Building were quite dirty, and there was a large amount of extraneous material cluttering certain areas of the Reactor BJilding.

4. Two beam ports were not adequately locked shut.

5. There was no Tornado Response procedure.

6. Several radiation instruments were not properly calibrated. The portable neutron detector was almost six months overdue for calibration. The Continuous Air Monitor for the ventilation system has a missing calibration sticker.

j 7. The chief examiner thanked the facility representatives for their i

cooperation during the course of the examinations.

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U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILI1Y: UNIVERSITY OF ILLINDIS REACTOR TYPE: TRIGA ADV DATE ADMINISTERED: 86/01/15 EXAMINER: HIGGINS, R.

APPLICANT: _________________________

INSTRUCTIONS TO APPLICANT:

Use separate paper for the answers. Write answers on one side only.

Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category.

Exac,: nation papers will be picked up si: (6) hours after the examination starts.

% OF CATEGORY  % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 20.00

________ ______ ___________ ________ H. REACTOR THEORY

_ I __ _ 1 ___________ ________ I. RADIDACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS 20.00 20.00

________ ______ ___________ ________ J. SPECIFIC OPERATING CHARACTERISTICS i

' 20.00 20.00

________ ______ ___________ ________ M. FUEL HANDLING AND CORE PARAMETERS

, 20.00- 20.00 L. ADMINISTRATIVE PROCEDURES.

CONDITIONS AND LIMITATIONS i.

l100.00 100.00 TOTALS i

FINAL GRADE  %

iAll work done on this examination is my own. I have neither r 31ven not received aid.

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H. REACTOR THEORY PAGE 2

, OUESTION H.01 (1.00)

What will happen to a neutron outside the nucleus if it never gets absorbed?

4 OUESTION H.02 (1.50)

Why is the value of /3ef f dif f er ent f rom /3act?

OUESTION H.03 (2.00)

Explain why an increase in fuel temperature decreases reactivity.

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OUESTION H.04 (1.00)

Why is a neutron source needed for reactor startups?

OUESTION H.05 (1.50)

Explain how the two TRIGA neutron sources produce neutrons.

QUESTION H.06 (2.00) .

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a. Assuming a neutron source strength of 100 ne'-tr:nc per second, what will I be the equilibrium count rate if the source is placed in the presence of a reactor assembly which has an effective multiplication constant (Keff) of .99? Show your work. (1.0)

b. If Keff is raised to .999, how many neutron senerations must elapse before the count rate attains 99.9% of its equilibrium value (within 0.1% of its equilibrium value)? Show your work. (1.0)

! OUESTION H.07 (1.50)

If the TRIGA has a Keff of .96, how much reactivity, in dollars, must be added to make the reactor critical? Show your work.

(unrur CATEGORY H CONTINUED ON NEXT PAGE nrzum) i L

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H. REACTOR THEORY PAGE 3 QUESTION H.08 (1.00)

What would happen if the neutron source is removed froni a reactor which is just critical?

DUESTION H.09 (2.00)

With a reactor period of 50 seconds, how long will it take for reactor power to increase from 50 watts to 1 kilowatt? Show your work.

QUESTION H.10 (2.00)

Explain how rod n otion can cause xenon oscillationr.

QUESTION H.11 (1.50)

What will reactor power be immedistely after a retetor trip fron 1 hW.

assuming $8.00 of negative reactivity is added by the control rods?

Show your work.

QUESTION H.12 (1.00)

Why don't delayed neutrons cause fission in U-2389 QUESTION H.13 (1.00)

Choose the correct response. Samariusi as a poison in the core reaches an equilibrivni reactivity value in approximately*

a. 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> i

b. 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />

.c. 4000 hours0.0463 days <br />1.111 hours <br />0.00661 weeks <br />0.00152 months <br />

d. the time depends upon the neutron flux level.

(avans CATEGORY H CONTINUED ON NEXT PAGE *****)

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i H. REACTOR THEORY PAGE 4 OUESTION H.14 (1.00)

Which one of tha following will NOT affect the peak power of a 12 pulse:

e. delayed neutron fraction.

b. average neutron lifetime.

c. number of f u e '. elements in the core.

d. heat capscity of the fuel.

(***** END OF CATEGOPY H *** n)

I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 5 DUESTION I.01 (1.00)

What are the three NRC limits for extern 61 radiation exposure?

OUESTION I.02 (1.00)

What three criter ia must be satisfied / observed to allow a radiation worker ,

to exceed the NPC external whole body radiation exposure limits? -

GUESTION I.03 ( .50)

What external whcle body radiation exposure limit must be observed for individuals unde

• 18 years of age?

DUESTION I.04 (1.00) i Nac.e two fissicr. products, other than iodine. which att gases at r o o r, temperature.

QUESTION I.05 (2.00)

a. What automatic action takes place to limit iodine release through the ventilation system? (1.5)

b. What detector is used to cause this automatic action? (0.5) 4 QUESTION I.06 (2.50)

According to the FSAR, it is necessary that the radioactive coolant water

, emerging from the core be delayed about 90 seconds before being introduced into areas that may be occupied.

a. Write the equation for the formation of the radioactive is. tope which makes this delay necessary. (1.0)

b. What is the half-life of this radioactive isotope? (0.5) i

c. What design feature (s) is/are installed to provide this 90 second delay? (1.0) l I

(umarr CATEGORY I CONTINUED ON NEXT PAGE **ns*)

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, I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 6 4

QUESTION I.07 (2.00)

What is the function of the Bean. Catchers?

j OfjESTION I.08 (3.00)

I a. Describe how the University of Illinois disposes of high-level solid radioactive wastes. (2.0) l

b. Where are high-level solid radioactive wastes stored at the University of Illinois? (1.0)

GUESTION I.09 (1.00)

How does the University of Illinois dispose of lie,vid radioactive westes from the retention tank if the activity in the tank is too high to allow I release to the ssnitary sewer system?

QUESTION I.10 (1.00)

I How is radioactive Argono41 produced?

DUESTION I.11 (1.00'

s. What sound does the atdible alarm for the Tracerlab 5-Channel Ion Chamber Systen. make? (0.5)

b. What sound does the audible alarm for the Air Particulate Monitor

make? (0.5) l DUESTION I.12 (3.00) f j What s i

< immediate actions must the licensed operstor take if high off gas activity occurs while the reactor is in operation?

(*r*** CATEGORY I CONTINUED ON NEXT PAGE *****)

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- I. RADIDACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS GUESTION I.13 (1.00)

c. True or False. Rubidiosi-88 is a Radon daughter. (0.5)

b. True or False. Materials cosiposed of elenients with high atos.ic weights make the best neutron shields. (0.5)

(*summ END OF CATEGORY I *****)

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4 PAGE B J. SPECIFIC OPERATING CHARACTERISTICS GUESTION J.01 (1.00)

Explain how and why the reactivity of the LOPRA will change if the LOPRA is coved from it: normal position next to the bulk shieldin3 thermal column.

QUESTION J.02 (1.00)

The LOPRA SAR states that 'the portion of the t he r nia l c o l u nin containing

two feet of graphite is lined with polyethylene te provide a greater albedo.' What is ' albedo'?

OUESTION J.03 (3.00)

Explain how the natural convective cooling loop is designed to allow natural convection to auton.stically comn.ence upon loss of forced convectior while avoiding interference with the coolant flow dur ing f or ced Convection.

QUESTION J.04 (3.00)

a. What are the two functions of the eniergency core spray cooling system? (2.0)

b. What design feature is installed in the emergency core spray cooling system to prevent a leak in the emersency core spray cooling system piping fros draining the Reactor T a r.k ? (1.0) t QUESTION J.05 (2.00)

Explain why a reduction in the level of the bulk shielding facility could cause a LOPRA scram.

i OUESTION J.06 (2.00)

Why would a leak in the primary coolant lines between the TRIGA core and i the isolation valves not result in the con.plete draining of the Reactor Tank?

(rzurm CATEGORY J CONTINUED ON NEXT PAGE *****)

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J. SPECIFIC OPERATING CHARACTERISTICS PAGE 9 i

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GUESTION J.07 (2.00) '

Explain why all the TRIGA rods scram when electt ital power is lost.

QUESTION J.08. (2.00)

During forced convection, the temperature rise through the core will double if reactor power doubles. During free convection, the t e m;. e r a t u r e rise

., through the core will increase, though by less than a factor of two, if reactor power doubles. Explain why the increase i ri the temperature rise across the core is less for the f ree corevection case than it is for the forced convection case. ,

i 00ESTION J.09 (2.00)

[ a. The poison section of the TRIGA control roc. consists of _____. (0.5)

b. The _____ roos are 'fvel followet* rods. (0.5)

c. Why is the adjustable transient rod constructed with an air i follower? (1.0)

GUESTION J.10 (2.00)

How are rods cor. trolled during square-wave operation?

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K. FUEL HANDLING AND CORE PARAMETERS PAGE 10 QUESTION K.01 (2.50)

a. E: urn-up of U-235 for a TRIGA reactor is estimated to be _____ per MW day of operation. (0,5) b..A single rod division is worth approximately _____ in reactivity. (0.5)

e. The equilibrium reactivity value of Xenon for the TRIGA at 1.5 MW i s a ppr o x i nia t el y _ _ ___ . (0.5)

d. The equilibriun. reactivity value of S a n. a r i u m for the TRIGA is approximately _____. (0.5)

e. The excess reactivity in the LOFRA is limited to _____. (0.5)

DUESTION (1.50)

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s. Where se the fuel hendling tool kept? (1.0)

b. Whtt piecaution is tafen to prevent unzuthot 1:ed movenient of the "

• fuel-moderator clet:nts? (0.5)

GUESTION K.03 (1.00)

Which two individuals control the keys to the roon, where the cold fuel elements are stored?

QUESTION K.04 (2.00)

Explain how irradiated fuel elements can be placed inside the fuel transfer cask without exposing fuel handling personnel to hi3h radiation fields.

(waarm CATEGORY K CONTIr;UED ON NEXT PAGE maman)

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K. FUEL HANDLING AND CORE PARAMETERS PAGE 11 4

1 QUESTION K.05 (6.50)

a. The normal Reactor Tank water level (reference point) is _____ above the top grid ,alste of the core assen.bly. (0.5)

b. The two interniediate level trips are _____

below the reference point and

_____ ,the reference Poir.t. (1.0)

! c. What automatic action occurs if the Reactor Tank water level drops to the' lower intermediate water level trip setpoint? (0.5)

d. What automatic action occurs if the Reactor Tank water level rises to the upper intermediate water level trip setpointo (0.5)

e. The emergency level trips are set at _____ below and _____ above the reference point. (1.0)

f. What is,the basis for the higher emergency water level trip?

g. What D & autometic actions will t el e place if water level drops to the lower emergency water level trip setpoint? .

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• Q) j OUESTION K.06 (1.50) j a. How m a r.y s c r a n.- c a p a b l e rods does the LOPRA have? (0.5)

b. What neutron-absorbing n.aterial is used in the LOPRA control rods? (0.5)

c. Movenients of LOPRA fuel shall not be made e:: cept under t.n direct supervision of _____. (0.5)

QUESTION K.07 (2.00)

! List two niodifications which must be done to the LOPRA if the TRIGA is to be operated above one kilowatt and no experimental work with the LOPRA

is in progress.

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(***** CATECORY K CONTINUED ON NEXT PAGE  ::: )

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K. FUEL HANDLING AND EORE PARAMETERS PAGE 12 QUESTION M.08 (3.00)

a. The reactivity worth of a single e x p e r i m e rit n.u s t be less than _____. (0.5)

b. The TRIGA may be operated for a manimum time of _____

when the ventilation system is not in operation, provided that reactor power is not raised abcve _____. (1.0)

c. The total of the absolute values of all e x p e r i n.e ri t s i r. t h e TRIGA must be less than .____. (0.5)

d. A fuel temperature stran will occur if the n. z : I n.u ni fuel t e nipe r a t u r e of a E:-r ins iris tr un erited eier.ent e::c e e d s _____. (0.5)

e. A water ter.pe t s t or e sctEm will CLcur if the bulk water t e n.pe r a tu r e of the core e:: i t coolant e::ceeds _____. (0.5)

(r**** END OF CATEGORY M *****)

'L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 13 4

OUESTION L.01 (1.00)

Whet is the Shutdown _Marsin requirement for the TRIGA?

- QUESTION L.02 (1.00) d Escorted visitors may be taken into the reactor area only with the approval of the --___ or the _____.

d DUESTION L.03 (2.00) l s. What is the whole body dose limit for saving a life? (0.5)

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b. Whose perniission n ust be obtained prior to exceediris nors a1 occupational r adi etion e::posur e l i n,i t s ? (0.5)

c. Whose Fer nissi on ntus t be obtained prior to re-entering the reactor beilding efte- i radiation emergency? (0.5)

d. ' ve or Felse. A. y i.. e h. L e t of Group E: can take any action which he deen;s necessar y if he considers a delay to be deterimental to the cefety of personnel in the imn.ediate area. (0.5) i j GUESTION L.04 (1.00)

a. f. radiological emergency which r equires evacuation of the reactor '

- building would be classified as a(n) _____. (0.5)

b. A radiological emergency which requires evacuation of adjacent buildings would be classified as a(n) -__--

. (0.5) j DUESTICN L.05 (1.00)

NEp the two bes;c checks which are used to determine whether Ell personnel l

who hsd beer. in the reactor building prior to an evacuation have left the i b: 11 dins.

I 0'JE S T IO N L.06 (1.001 Where sre personnel who have evacuated the reactor building required to r e a s s enibl e ?

(marr* CATEGORY L CONTINUED ON NEXT PAGE musum) d e

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L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 14 00ESTION L.07 (1.00)

What is the primary means of cosin unication used to notify the onsite an.ergency organization during an eserjency?

DUESTION L.08 (1.00)

In which buildings are the alternate emergency support centers located?

OUESTION L.09 (1.00)

What environmental factor is used to decide which emergency support center to use?

DUESTION L.10 (1.00)

What is meant by the terni ' Reactor Shutdown *?

DUESTION L.11 (2.00)

What is meant by the term " Reactor Secured'?

DUESTION L.12 (1.00)

What are the two TRIGA Safety Limits?

DUESTION L.13 (1.00)

State two actions which must be taken imsiediately af ter a TRIGA safety limit is exceeded.

QUESTION L.14 (2.00)

What is meant by the term ' Shutdown Reactivity'?

(***** CATEGORY L CONTINUED ON NEXT PAGE riman)

L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 15 QUESTION L.15 (1.00)

.Who can make tesporary changes to a TRIGA operating procedure, assuming the changes do not modify the procedure's original intent?

GUESTION L.16 (2.00)

List two of the six general categories of Abnormal Occurrences.

(zurum END OF CATEGORY L marum)

(rumwansamarrs END OF EXAMINATION sans********n**)

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E()UATIONS $

• REACTOR THEORY RADIATION '

FI.UIDS/TilERHO/ HEAT TRANSFEit T

t SUR.t _Ag

• P = P,e /t = P,10 N.Ne ,

9 m . A191V1 = A202V2

,{.,8-p ,g p A = IN q . A1V1 = A2V2 P AP AD -px I=Ie = I 10 -x/TVT E in

=E out

+ AE stored k-l km - ki 0

1. 38 k k 2 kg R ATis = 0.693 E = KE + PE + U + pV + Q + W cpnz 1-k 1 R/hr @ d feet = $ ,

Y g g k<1 cpal I1-k 2 g 2 , g 2 point source 8c

, V, 1

1

-=1-k Ildi=1d2 2 - line source b"gc H

, R/hr x time = R reduced for - turbine, SG pump, nozzle, 1_ , cps

• Rad x QF = Rem orifice, condenser, pipe, Rx M cPa n

• x flow a /dp Tb = Bio g,R a d "nat *O# doppler + # mod + # void Th3 g, + Ti sRad or head loss a V headloss=ih c heau loss a op

+#e+#m+#Pu X S

• P=h + p ,, , g ,

v2 pBoron + prod + pfuel + F = pA E c

Ar2 phase AP1 phase x K 0

Poisons) k - f(quality & Pres ure) k 2 = kt + 3k Pump laws speed u flow (speed)3 0 pressure 6k=k-1 MATil (speed)8a power Q = kAAT = hAa7 = UAAT suu=26;os , , , n . ,, 3r p

E*Y log b=4 0 " "Oh

p. + y Q = tcT 3.1 x 1018 c log x = c log x all = m c 4T x P I = No 1 8-=1 8 x - 108 y AU - m c AT 4 = nv 1 S xy = 1 g x + 1 g y H = U + pV Defect =

Coeff x a Parameter AS " SS T

pV = nRT PlVI . ELV1 T1 T2 i CV + C2Va - Ca(Vi + Vi)

H. REACTOR THEORY PAGE 16 t

ANSWERS -- UNIVERSITY OF ILLINDIS -86/01/15-HIGGINS, R.

! ANSWEP H.01 (1.00)

E: eta decays to a proton (hydrogen).

REFERENCE ,

NE 390R Notes, p3 ANSWER H.02 (1.50)

. Pr onipt neutt oris are born at a higher average energy than d e l a ye c; I neutrons (.75), so a smaller percentage of delayed neutrons is lost while slowing down (.75).

! REFERENCE I

NE 390R Notes, p2 O fN, /MMMM ANSWEF H.03 (2.00) 2 #- _ 7,t.

Doppler _E:r oadening.

msA e 24 mo:ma (Y.C)

Wh e n U-2N t e n'.p e r a ti.ir e increases, the 7 elative motion

- between the neutrons and U-238 s t on:s increases, broadening the resonant absorption peaks 64d50 . The probability of parasitic neutron absorption by U-236 increases, deeLeasing the probability that neutrons will reach thermal energies (d) .

REFERENCE i' NE 390R Notes, p5 ANSWER H.04 (1.00)

Provide a neutron level which is high enough to be detected by nuclear instiunentetion-(0.5). allowing reactivity changes taking place in the ieactor to be observed (0.5).

REFERENCE NE 3o0R Notes, p 6 L

r H. REACTOR THEORY PAGE 17 ANSWERS -- UNIVERSITY OF ILLINDIS -86/01/15-HIGGINS, R.

ANSWER H.05 (1.50)

1. Radium emits an alpha (.25). The alpha ersters a E:e-9 nucleus which then splits, emitting a neutron (0.5).

2. A n t i nio ny 123 absorbs a neutron, b e c o n> i ng a r.t i n.o r.y 124 (.25). Antimony 124 e n. i t s a gamnE which strikes a E: e - 9 nucleus, causing it to emit a neutron (0.5).

REFERENCE NE 390P Notes, p6 ANSWER H.06 (2.00) 5 Count rate = S/(1-Keff) = 100/(1 .991 = 100/.01 = 10,000 coun'.s per seconc (1.0'.

t. C o t r. t iste = E (1+Meff+Keff1+...+Meff"+...) (.2) reff = 0.1% = .001 (.2)

.999 = .001 (.2) n 1o3(.999) =

1o3(.001) = -3 (.2) n= -3/1o3(.999) = -3/.0004345 = 6905 generations (.2)

REFERENCE NE 3?OR Notes, p8 and 9 ANSWER H.07 (1.50)

Ag = ( g _ g , ) / ( g2 II Ms) = (1 .96)/(1 : .96) = .04/.96 = .041667 (.75)

Ag = . 0 416 67 :: ($1/.0073) = $5.71 (.75)

PEFERENCE NE 390r Notes, p 9 ANSWER H.08 (1.00)

The power level would decr ease for a short t i nt e (0.5) before leveling off at a censtsnt value (0.5).

REFERENCE NE 390R Notes, p 10

H. REACTOR THEORY PAGE IS ANSWERS -- UNIVERSITY OF ILLINDIG -86/01/15-HIGGINS, R.

ANSWER H.09 (2.00)

P = Po .: e e x p ( t /3') (0.5)

P/Po = e exp(t/7) (0.5)

In(P/Pc) = t/T (0.5) t = 3' I ri ( P / Po ) = (50 secorids ) "

I ri( 1000 w / 50 w ) = 50 I r. ( 2 0 ) = 50 x 3 t = 150 secorids (0.5)

REFERENCE NE 290R Notes. p 11 ANSulR M.10 (2.00)

If a c orit r o l rod is removed, f 10; i ri the vtczted r e g i cri i ric r e a s e s ,

i n c r e c s i rig , e n o n b u r r.o u t (0.5). X e : i o r. c orit e nt r a t i on temporarily decreases.

forther incrersire the 1ccallred f lu: (0.5).

If a control rod is I ris er t ed , f 1 v- 1 r. the vicinity decreases, d e c r e a s 2 rig the xeriori but riout (0.5). X e rio ri c oric e rit t a t i e ri t e r.por a t 11 y i re c t e a s e s .

futher decreasing the localized f1w (0.5).

REFERENCE NE 390R Notes, p 15 ANSWER H.11 (1.50)

P = P, [4/ (6 -/))] (.75)

P= 1 MW E$1/($1 - $8)J = 1 MW C1/93 = 111 KW (.75)

REFERENCE NE 390R Notes, p 11 ANSWER H.12 (1.00)

Delayed rieutr ons ate borr. at lower energies t h a ri the threshold energy for U-236 f i s s i o ri .

PEFERENCE NE 390R Notes, p 2

H. REACTOR THEORY F' A GE 19 ANSWERS -- UNIVERSITY OF ILLINDIS -86/01/15-HIGGINS, R.

ANSWER H.13 (1.00) d REFERENCE NE 390R Notes, p 15 ANSWER H.14 (1.00) a.

REFERENCE NE 451 Final Exan, 76/07/30, 47 i

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I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 20 ANSWERS -- UNIVERSITY OF ILLINDIS -86/01/15-HIGGINS, R.

ANSWER I.01 (1.00)

Whole E:ody - 1.25 rems per quarter. (0.5)

Extremities - 18.75 rems per quarter.

(.25)

Skin - 7,5 rems per quarter. (.25)

- REFERENCE 10CFR20.101 ANSWER I.02 (1.00)

1. Dusrttely dose does not exceed 3 ren,s (.3)

2. Lifetime e::pos ur e does not exceed 5(N-18) (.4)

3. NRC Forni 4 is conpleted (.3)

REFERENCE 10CFR20.101 ANSWER I.03 ( .50)

.125 rems per quarter REFERENCE 10CFR20 104 _

ANSWER I.04 (1.00)

Krypton (0.5) and Xe on (0.5).

REFERENCE FSAR V-14 ANSWER I.05 (2.00)

a. T ;.e . . w. ,- e : - : : -t h; a n e , . i . w.r i .i c t will b e c l o s e4-e+Wa, etic +4-l y . '5) eere The da n.pe r in the duct containing the charcoal filter will be opened ( N (l,T)

b. Air Fatticulate Monitor (0.5).-

I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 21 ANSWERS -- UNIVERSITY OF ILLINCIS -86/01/15-HIGGINS, R.

REFERENCE

, FSAR V-15b

- ANSWER I.06 (2.50)

s. Oxygen-16 plus a neutron gives Nitrogen-16 plus a proton. (1.0)

b. 7 seconds. (0.5)

c. Two delay tanks are installed in the pr in4ary cool ant systeni on the outlet loop f r o n> the reactor. (1.0)

REFERENCE FSAR IV-2 5 i

AN?uER I.07 (2.00)

Reduce.the tscLgr ound r adiation during usage of a bean; port.

-REFERENCE FSAR IX-13

-M ,T_ h.....,,@,.- .vw<c..uv3m

.__m_ . _.

t.

-_c,.

fu m......_~ scuin3e vos.. su uccu o ..

I w lavc1 2metinmetivo use+e ri_c? t h e r, p:::s3rd im 55 3ctio;, 3Lem12 f e ;:- .6 shioned tru : d yc;al fac-litj . '1,0t.

b. Four storage pits located in the floor of the truck bay. (1.0)

REFERENCE t FSAR XI-1 ANSWER I.09 (1.00)

Tank contents can be discharged through the hose bleed valve into a tank truck.

{ REFERENCE l FSAR XI-5 i

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

I. RADIDACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 22 ANSWERS -- UNIVEP.SITY OF ILLINDIS -86/01/15-HIGGINS, R.

ANSWER I.10 (1.00)

Neutrori capture by the naturally-occurring Argon-40 in the atmosphere.

REFERENCE FSAR XI-6 ANSWER I.11 (1.00)

a. Loud horr.. (.5)

b. Eor tinuous pulsir s of the alarm bell. (0.5)

REFERENCE FSAR XI-25 ANEWER I.1: (3.00)

1. Initiate building evacuattori. (0.5)

2. S c r e c. the reactor. (0.5)

3. Turn off both water circulatiori systems. (0.5)

4. Close the isolation valves. (0.5)

5. Turri off the c i r c u l a t i o ri f a re for the air c o rid i t i orie r . (0.5)

6. Close the diverting valve o ri the exhaust sytter.. (0.5)

REFERENCE Radiation Emergency Plan, p 10 ANSWER I.13 (1.00)

a. False (0.5)

b. False (0.5)

! REFERENCE I FSAR XI-24,25 1

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J. SFECIFIC OPERATING CHARACTERISTICS PAGE 23 ANSWERS -- UNIVERSITY OF ILLINDIS -86/01/15-HIGGINS, R.

ANSWER J.01 (1.00)

Reactivity will decrease, since graphite in the thermal column serves as a reflector.

REFERENCE LOPRA FSAR III.C.3.c J.02 (1.00) * -

ANSWER e<.Awh The fraction of elcct c--?Onetic cdictlar '3cer: c y_7 reflected.

REFERENCE Webs ter 's New Collegiate Dictionary ANSLER J.03 (3.00)

Fiple3 connects the plenuni below the reactor to the outer housina abovc t ?. c reactor (.75). Located in this pipins is an automatic control valve with a counterbalanced lever systen. (.75). When forced circulatior, is talins place the valve is held shut by the force of the flow (.75). If forced circulation is lost, the counterbalance weight will cause the valve to open, allowins natural circulation flow to begin (.75).

REFERENCE FSAR VI-2 ANSWER J.04 (3.00)

a. 1. Supply deminerall:ed water so the chamber above the core r e n.a i ris full of water (1.0).

2. Supply water to the core for cooling should all water disin fton the core (1.0).

b. Anti-syphon check valve (1.0).

REFERENCE FSAR VI-9, 10 and 11

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J. SPECIFIC OPERATING CHARACTERISTICS PAGE 24 ANSWERS -- UNIVERSITY OF ILLINDIS -86/01/15-HIGGINS, R.  :

i i ANSWER J.05 (2.00)

As the level drops, shielding is reduced, raising the radiation level above the bulk shielding tank where the samma monitor is located (1.0). If the

! radiation level rises high enough. the samma monitor will generate a LOPRA

, s c r e r; (1.0).

REFERENCE LOPRA SAR p 10 and 13 ANSWER J.06 (2.00) 4 The prin,ary coolant lines pass through a tunnel which has e sesled bsrt ier

! located in it to lin.it the tunnel's volume to less than the volvce of the Reactor Tank. -

I REFERENCE

ISAR VI-13 -

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ANSWER J.07 (2.00)

+

1. The motor driven rods are held in position by an electrical signet which will deenergire UPon loss of electrical power, allowing the r ods to drop

by sisvity (1.0).

i 2. The transient rods depend on electrically operated solenoid valves to retain the necessary pressure to hold them in the UP position. If

electrical power is lost, the solenoid deenergizes, allowing air j

-pressure to diminish, causing the rods to drop by gravity (1.0).

REFERENCE i FSAL VII-24 ANSWER J.08 (2.00)

In the free convection case, as power increases, the ten per civr e rise j' thr ough the core increases, increasing the density dif f er ence between the

inlet and outlet coolant, thus i nc r e a s i r.g free convection flow. Conc of 2

the power increase is absorbed by the trecreased core flow (1.01 In the f orced cor. vection case, the increased power is only reccVed by incressing the enthalpy of the coolant as it passes through the coree j since the core flow remains constant (1.0).

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- - -.- ..w.,n,--,v, --,,-n.-.-~,---nv,e,.,-,,c-,- - _ n n - ,m n -,- - ---. _ ,--n,w.

J. SPECIFIC OPERATING CHARACTERISTICS PAGE 25 ANSWERS -- UNIVERSITY OF ILLINDIS -86/01/15-HIGGINS, R.

REFERENCE FSAR IV-34 ANSWER J.09 (2.00)

a. Graphite impregnated with boron carbide (0.5).

b. harivally driven (0.5).

c. To diniinish the flu: peaking if water filled the rod c h a ntie l after the rod wss withdrawn (1.0).

REFERENCE FSAR III-16 ANEuER J.10 (2.00)

The fast transient rod and the actor driven rods src vied to ot*tir, a ri initisl steady-state power level (.7). The adjustable t r r n t : c r *. rod is then fired to obtair, a rapid i ric r e a s e iri power (.7). T o c on peris ate f or the negative reactivity that occurs as the fuel t E i p e r a t u r e 1DCreases, the regulating =rs-  ; rode n$$fautomatically withdrawn to stabill:e power at the preset level (.6).

REFERENCE FSAR VII-11

K. FUEL HANDLING AND CORE PARAMETERS PAGE 26 ANSWERS -- UNIVERSITY OF ILLINDIS -86/01/15-HIGGINS, R.

ANSWER K.01 (2.50)

a. S.02 (0.5)

b. g803 to 4005 (0.5)

c. $3.53 (0.5)

d. $1.40 (0.5)

e. w $.60 (0.5)

REFERENCE NE 390R Notes, p 10, 15 and 17 LOPRA SAR, p i ANSWER K.02 (1.50)

a. It ided s i d th nerete shield ( ).

b. The fuel handling Yool is locked in place (0.5).

REFERENCE FSAR IX-6 ANSWER K.03 (1.00)

Reactor Supervisor (0.5) and Reactor Health Physicist (0.5).

REFERENCE FSAR IX-7 ANSWER K.04 (2.00)

! The lead plus is removed fron. the botton, of the cask (0.5). The cask is

, brought over the irradiated element, the fuel handlirig tool is e:: tended down through the cask onto the fuel e l e m e rit (1.0). The fuel e l e n.e n t is raised into the cask, at which time the lead plug is closed arid the fuel el enie nt is released froni the f uel haridlirig tool (0.5).

REFERENCE

. FSAR IX-8 ,

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K. FUEL HANDLING AND CORE PARAMETERS PAGE 27

' ANSWERS -- UNIVERSITY Or ILLINDIS -86/01/15-HIGGINS, R.

ANSWER K.05 (6.50)

a. 16 feet (0.5)

I

b. 6 inches (0.5); i inchese(0.5)

c. Turns on the S spn> esiersency core spray coolins make-up systen. (0.5)

d. Stops the addition of make-up water via the 3 spn> en.ersency core spray cooling systen. (0.5)

e. 4hk inches (0.5); finches (0 5)

f. Prevent water from over flowins the Reactor T s ni (0 5) 3 1. Reactor sc r z ni (0.5)

2. Coolins systeni isolation valves close (0.5)

3. Primary punip stops (0.5)

4. AV2 operis to incr ease emer sency cot e spr ay coolins niat e-up f low to 5 to 8 spm (0.5)

REFERENCE FSAR VI-10, VII-20 ANSWER K.06 (1.50)

c. 2 (0.5)

b. Cadmium (0.5) c.. Licensed operator of the LOPRA. (0.5)

REFEREFCE LOPRA SAR, p 26 and 36 k

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K. FUEL HANDLING AND CORE PARAMETERS PAGE 26 ANSWERS -- UNIVERSITY OF ILLINDIS -86/01/15-HIGGINS, R.

ANSWER K.07 (2.00)

1. Resiove enoV3h fuel elesients and plus the fuel holes so that Keff is less than .99 with the safety control and poison rods removed ( r e s. o v e two or more central fuel e l e nie n t s ) (1.0).

2. One of the following (1.0):

a. Hove the pl a tf or ni cont a i r.ing the grid plates and ren. air 1r.3 fuel e l e n, e rit s sever al feet f r o n. the t h e r n. e l colonn e ri d lock it into position. OR

b. Place a r.evtr on absorbing screen betweer. the thernotl colun' snd the LOPRA core.

REFERENCE LOPRA SAR, p 36 ANSWER K.08 (3.00)

a. $3.00 (0.5)

b. 2 days (0.5); 1 MW (0.5)

c. 15.00 (0.5)

d. 800 C (0.5) 753I

o. 120 F (0.5)

REFERENCE FSAR VII-30 Toch Spac's 3.1.c, 3.1.1 and 3.7

L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 29 ANSWERS -- UN!VERSITY OF ILLINDIS -86/01/15-HIGGINS, R.

ANSWER L.01 (1.00)

Croater than $.50 in the cold, xenon-free condition (u.5) with the highest worth control rod withdrawn (0.5).

REFERENCE Tech Spec 3.1.h ANSWER L.02 (1.00)

Reactor Supervisor (0.5); Reactor Health Physicist (0.5)

REFERENCE FSAR XI-26 ANSWER L.03 (2.00)

a. 25 rems (0.5)

6. Group A (0.5)

c. Unanimous consent of Group A (0.5)

d. True (0.5)

REFERENCE Radiation Emergency Plan, p 6, 7 and 13 ANSWER L.04 (1 00)

a. Alert (0.5)

b. Site Area Emergency (0.5)

REFERENCE Radiation Emergency Plan, p9 ANSWER L.05 (1.00)

The film badge r ack (0.5) and the dosimeter list (0.5).

5, i

L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMllATIONS PAGE 30 ANSWERS -- UNIVERSITY OF ILLINDIS -86/01/15-HIGGINS, R.

REFERENCE Radiation Emergency Plan, p 11 ANSWER L.06 (1.00)

In'the building at the siain south entrance of the Coordinated Scierice Buildiris to the northwest of the Reactor E:vilding.

REFERENCE Radiation Emersency Plane p 11 ANSWER L.07 (1.00)

Phone REFERENCE Ra dl e tt er En.er se ncy Plsrie p 13 ANSWER L.08 (1.00)

Nuclear Engineering Laboratory (0.5) and Envirorimental Studies Institute Anne:< (0.5).

REFERENCE Radiation Emergency Plan, p4 ANSWER L.09 (1.00)

Wind. Direction REFERENCE Radiatior Emer gency Plan, p 14 ANSWER L.10 (1.00)

Sufficient control rods are inser ted so as to assur e thct the reactor is svberitical by at least $1.00 (0 5) and an SRO is in charge of any work in progress (0.5).

L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 31

-ANSWERS -- UNIVERSITY OF ILLINDIS -86/01/15-HIGGINS, R.

REFERENCE Tech Spec 1.1 ANSWER L.11 (2.00)

1. Sufficierit control rods are inserted to asture suberiticality by

$1.00. (0.5)

2. Power to the control rod niagnets and actuating solenoids is off, and the key i s r enioved. (1.0)

3. No work is in progress involving fuel, in-cor e e::per inients or maintenance of the core structure, control rods, or control rod drive s.e e h a n i s n.s . (0.5)

REFERENCE Tech Spec 1.2 ANSWER L.12 (1.001

1. The temper atur e in a stainless-steel clad, high hydride fuel elenient shall not exceed 1000 C under any conditions of operation (0.5).

2. The temperatur e in a low hydride fuel e l enie nt shc11 not exceed 550 C under any conditions of oper ation (0.5).

REFERENCE Toch Spec 2 1 ANSWER L.13 (1.00)

Any two of the following (0.5 each):

1. The reactor shall be shutdown.

2. An immediate report of the occurence shall be niede to the Chairman of j the Nuclear Reactor C o ni ni i t t e e .

! 3. An impiediate r epo t shall be made to the Noelear Regulatory Con.n.ission

! in Washin3 ton, D. C.

! REFERENCE Tech Specs 6.4 and 6 7

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r L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 32 ANSWERS -- UNIVERSITY OF ILLINDIS -86/01/15-HIGGINS, R.

ANSWER L.14 (2.00)

The minimum reactivity worth required in the control and safety rod system at all times, starting from any permissible operating condition, such that tha reactor can be made soberitical by no less than the shutdown margin (1.0) assuming that the reactor is in the cold, :enon-f r ee condition ( .4) with the highest worth rod fully withdrawn (.3) and with the highest worth non-s ecur ed e:.per in.ent i re its niost reactive state (.3).

REFERENCE Tech Spec 1.26 ANSWER L.15 (1.00)

Reactor Supervisor REFERENCE Tech Spec 6.3 ANSWER L.16 (2.00)

Any two of the following (1.0 each)*

1. Operating with any actual ssfety system settirig less conservative than specified i r. Tech Specs.

2. Violation of a limiting condition for operation.

3. Malfunction of a required reactor or experiment safety system component which could r ender or threaten to render the system incapable of performing its intended safety function.

4. Release of 'ission preducts fron a fuel elec4ent.

5. An uncontrolled or unanticipated change in reactivity.

6. An observed irisdequacy in the in,plementation of either adn.inistrative or procedural controls, such that the inadequacy could have caused the enistence c' developn. tnt of an unsefe condition in connection with the operation of the resctor.

REFERENCE Tech Spec 1.14