Text

Unsigned Exam Rept 50-170/88-03OL on 880721.Exam Results: One Senior Reactor Operator Took & Passed Exam
	ML20155A883
Person / Time
Site:	Armed Forces Radiobiology Research Institute
Issue date:	07/21/1988
From:	Eselgroth P, Denise Wallace; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20155A839	List: IR 05000170/1988003; ML20155A836;
References
	50-170-88-03OL, 50-170-88-3OL, NUDOCS 8810060108
	Download: ML20155A883 (53)
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{{#Wiki_filter:I . , ' e a . U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Examination Report No.

88-03 (OL) Facility Docket No.

50-170 Facility License No.

R-84 Licensee: Armed Forces Radiobiology Research Institute (AFFRI) Facility: Armed Forces Radiobiology Research Institute Reactor Examination Date: July 21, 1988 Chief Examiner: David Wallace date Operations Engineer (Examiner) Approved By: peter W. Eselgroth, Chief date PWR Section, Operations Branch, DRS Summary: A written examination was administered to one Senior Reactor Operator (SRO).

The candidate passed the examination.

l ) l l 8810060103 0009aj PDR ADOCK 05000170 l Pru) l .

. - e . DETAILS Type of Examination: Retake Examination Results: The SRO candidate passed the written exam.

(Operating exam had been previously passed and was waived).

1.

Chief Examiner At Site: David Wallace 2.

Personnel Present at Exit Interview: USNRC D. Wallace AFFRI M.

Moore Attachments: 1.

Written Examination and Answer Key

NRC reply to Facility comment and modifications to the written examination after the facility review.

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ATTACHMENT 2 .. . ! ,

Facility written comments and NRC resolutions for the AFRRI senior reactor operations exam administered on_ July 21, 1988.-

, i Question H.02

' i Facility Comment: t ' "AFRRI Uses an AmBe neutron source because of its long' half-life.

, The situation presented in this question is not relevant t.- our r reactor. We do not use the term power level to indicate the ' ! suberitical r.ultiplication level, we use the term source level.

The . "power level of the present st:; sup" is confusing.

It could be !

interpreted as the startup neutron popula*. ion, but more likely, our

staff interprets it is as a cold critical conditions.

Interpreted as the suberitical neutron population, the source level _would be LESS i and interpreted as a cold critical condition the power would be about ! the same."

l s NRC Resolution: ! Comment noted. Question will be deleted.

i Questions H.06, b. and c.

Facility Comment: -

"Sections b. and c. are irrelevant to the AFRRI TRIGA Reactor."

i NRC Resolution: ' Comment is not valid. Under unusual conditions sections b. and c.

! would be relevant.

l Question 1.01

j Facility Comment:- . "The Pneumatic Transfer System is not used, has been removed from

!, the pool and should be deleted from the answer key."

NRC Re' solution i j Comment noted. Answer Key will be changed.

) Question 1.06 j j Facility Comment: } l "The words "high radiation field" and "relatively high levels of j contamination" are subjective dependent on: the situation, the actual n

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, radiation levels, the radioisotope in question, and the way the ' individual has been trained.

Sections b. and c. could realistically - ,

be answered either TRUE or FA!.SE."

f NRC Resolutton: ' The comment is not valid. The same "subjective" words are used in

the referenced procedure.

The candidate must be able to interpret

the meaning of the procedure.

Question 1.09 ! j Facility Comment: 1' "This question can be answered either theoretically or practically.

In j ! theory, GM detectors are not energy dependent.

In reality, we refer to

several different detectors (incorrectly) as geiger counters. A trainee

is taught to use the 6CEN to get an estimate of the dose expected from a ! source and to verify this using a "geiger counter".

It would not be > unexpected to receive either a "SAME" or "HIGHER" response to this , question."

! f NRC Resolution: ( i Comment is not valid.

If an operator uses a GM detector, he or she l .3 should understand that it is NOT energy dependent.

If an operator '

uses a detector that is energy dependent, then he or she should also

be aware of its capabilities.

' , ! Question J.03 l l Facility Comment: l "The answer to section b. is incorrect.

In the event that any/all l control rods remain stuck after a pulse, the reactor core would

i convert into a steady state power operation. At full power (IMW), l l the temperatures of the fuel safety channels do not exceed 450 l i degrees C.

At maximum calculated power, it is still below the 575 ,

degrees C. scram point as well as the 600 degrees C. Tech Spec '

limit. The reactor will not scram by temperature scram.

In fact, I we hold the "tail" of pulses for as long as 15 seconds at which time j i steady state conditions exist.

The power generated would be l ]! equivalent to a slightly higher than normal steady state operation."

!

NRC Resolution: J The comment is valid and will be incorporated into the answer sheet.

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Question J.04

Facility Comment: , I "This question is misleading.

In an exam situation, the pressure could

. easily cause a 0.2 to be read as a 2.0.

First, a false statement is ' l given and then, the examinee is asked "why this limitation is

, necessary." When the false statement is corrected, there are several additional answers that are acceptable: ) 1.

Minimize corrosion to reactor components.

j 2.

Minimize activation products in pool.

.

3.

Optical purity of water in reactor tank."

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, j NRC Resolution: ' ' The comment is valid in that a false statement is given and then the F examinee is asked "why this limitation is necessary".

Part a. will j.

be deleted and the answer to part b. will be changed to include the additional answers.

, Question J.06 Facility Comment: "The answer to section b. is incorrect.

In Mode 1A-AUTOMATIC, all manual upward motion of control rods is prohibited, therefore nothing would happen."

NRC Resolution: l Comment is valid. Answer Key will be changed.

Question J.07 ! Facility Comment: , ' "The answer to section b. is incorrect.

In the event of an j electrical failure, RAM-a as well as the criticality monitor R-5 are kept in service automatically by a battery backed electrical system."

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i NRC Comment: l

Comment is assumed valid. Answer Key will be changed.

It would be ! helpful to include this information in the operation manual in j Chapter 6.

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. P ) Question J.08 ' - Facility Comment:

"The power defect (referred to at AFRRI as the power coefficient of l reactivity)iscomputedincorrectly. The total power coefficient at ! 1 MW is $3.47 (this includes the $.59 to reach.100 KW). However the . question as stated was at the time of the rod insertion what was the l K-eff of the core, therefore, the power level has nothing.to do with the solution....." NRC Resolution: Comments are valid concerning calculation, however, it is doubtful that a candidate would interpret the question to be at the exact i moment of shutdown.

Since the candidate taking the exam interpreted the question correctly no further comment is necessary.

The answer key will be changed to correct the reactivity calculation.

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o. U.S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAM 1HATION Facility: AFRRI Reactor Type: TRIGA MARK-F Date Administereo: 88/06/21 Examiner: Robinson. G.E.

Candicate: INSTRUCTIONS TO CANDIDATE Write answers on one side only.

Staple Use separate paper for the answers.

cuestion sheet on top of the answer sheets.

Points for each ouestion are indicated in parentheses after the cuestion. The passing grade recuires at Examination papers will be picked up six (6) nours least 70% in each category.

after the examination starts.

Category % of Applicant's % of Category Value Total Score Cat. Value 20.00 20.00 H.

Reactor Theory 1.

Radioactive Materials 20.00 2Q,30 Handling Disposal and Hazarcs 20.00 20.00 J.

Specific Operating Cnaracteristics 20.00 20.00 K.

Fuel Handling and Core Parameters L.

Administrative Procedures, 20.00 - 22.22 Conditions and Limitations Totals 100.00 1Q0,03 Final Grade % All work done on this exam is my own.

I have neither given not recieved aic.

. Canoicate's 5ignature I < ^ ' ' - - - - - - - .-_..,7, _ _, _ _ __ _

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. 6 NRO RULES AND GUIDELINE 3 FOR LICENSE EXAMINATIONS uring the administration of this examination the f ollowing rules apply , Cheating on the examination means an automatic denial . of ycur applicetion Cnd coule result a n more severe penalties.

Restroom trips ere to be limited and only one candidate at a time me) . leave.

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

U e black ink or dark pencil SD1y to f acilitate legible reproductions.

. Print your name in the blank provided on the cover sheet of the . Gu ami nati on.

Fill in the date on the cover sheet of the examination (if ne:enbery).

. Use only the Dep9" provided for enowe"s.

Frint voor neno in the upper right-hend corner of the flert c;e oJ gg O . a ooctten et the ens er sheet.

ConsPCutivel) FU%er c'e C h en5WP" Fheet, W-2te "Enti of Cate;ory _ " es . epp"o?raete. Ete"t Wech cetegory on e Ogw peQe. write 2 13 gg ;;,e gigg of the pepee. in:' w"ite "Les, Fege" cn the lest enswere sheet.

Number e i.: h e n si.er es to ca.tegory end nucer. for enemelk. 1.4 6.7.

. 2. SI:1p et ;esst m sg lines between eecn enswer.

1. Seperete enswe* sheets f rom ped and piece fanished answer ancets Je:e cown on your c e s.5: e-teble.

. Une abbr evi etiens only if they are connenly unec in f acil;ty 1,Lt, g;t t,i;;g. 7. The point value fer each cuestion is indicatec in cerentheses #4te* tnt cuestien end car te used e s e quice f o-the depth 04 answer receirsc.

, a. Enow' 411 ce':vi#t::ns. methc:s. or essumotions use tc ettein in + s or ! . tc mathen.et a :# 1 pro:lems whetner i n ci c a t e:: in the cuestion er n:t.

I 7. Fcetial credit may be given.

There4cre, ANSWEF. ALL FARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER PLANM.

t. If parts of the examination are not clear as to intent, ask Questions cf tho guteltet cnly.

'. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given estistence in compl eting the examinati on.

This must be done ef ter the examinati on has boon completet.

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, . . C. When you con.plete your ex ana nat i ca, you shall .. o.

Assemble your examination as f ollows: (1) Exam ouestions on t op.

(0) Enem aics - figu es, tetles, etc.

t (3) Answer pages including figures which are part of the answer.

b.

Turn in your copy of the examination and all pages used to answer the examination questions.

c.

Turn in all scrap paper and the balance of the paper that you did not use for answering the Questi.1ns.

. ! d.

Leeve the examinetien t.ree, es defined by the enaniner.

I4 et ter l 1eeving, you are found in thir eree while the examination is st111 i n pro $t Of E. y o L' r l i t erie & niaY b& dentec o" PCVOled.

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REACTOR THEORY QUESTION H.01 (3.0)

A critical reactor is placed on a stable reactor period of 60 seconds at low power.

a.

What is the approximate reactivity which has been - inserted? (Assume lambda is 0.1/sec. and beta - effective is 0.007.)

SHOW ALL WORK.

(1.5) ,

b.

If an additional 0.001 reactivity is added to the j supercritical reactor, what would be the resulting ' l DOUBLING TIME.

Assume no heating effects.

SHOW ALL WORK.

(1.5) ., i , 't"(F,s> OUESTION H.02 (2.5)

, Your reactor haf not been oper ated f or a ong per iod of time because of building repairs and other necessary maintenance.

The neutron source strength is about half of l what it was when the reactor was l as t star ted up.

ALL j OTHER FACTORS are equal when criticality is reached.

' a.

Is the power level of the present startup GREATER, j LESS, or about the SAME as that of the previous ) startup? Brieft.v explain your answer.

(1.25) d l

b.

Are the critical rod heights for the Dr-etent

star tup HIGHER, LOWER, or about the SAME when i ccefipared with those of the previous star tup? l Briefly explain your answer.

(1.25) l i i ! ! l (*+*** CATEGCRY H CCNTINUED CU NEXT PAGE +++++)

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REACTOR THEORY QUESTION H.03 (2.0) Your reactor is located in position 567.

After several weeks of being shutdown the reactor is taken critical and the rod positions noted.

The regulating rod position was at 400 units.

The reactor is again shutdown, six days later after maintenance and tests on the primary cooling system, the reactor is again taken critical.

A sample worth a NEGATIVE $0.25 has been placed in the core and the pool temperature has decreased by 6 degrees centlprade.

If all rods except the regulating rod are placed in the same position of the previous criticality, what would be the new position of the regulating rod when criticality is achieved.

Assume no other reactivity changes occur.

Useful constants, equations, and reactivity curves are appended to back of the exam.

(2.0) QUESTION H.04 (2.0) Indicate whether the following statements concerning iission produet poisoning are TRUE or FALSE.

a.

The amount of positive reactivity needed to overcome the equilibrium value of xenon-135 poisoning at 100 per cent of full power is twice that needed to overcome equilibrium xenon-135 at 50 per cent power.

(0.5) b.

When increasing power from 50% pcwer (after < ' extended operation) to 100% power, the xenon-135 conc en tr a t i on i n i t i a l l >' de c r e a s e s 6nd then lneresses.

(0.5) c.

The equi)ibeium value of samarium-149 is NOT dependent on pcwer level.

(0.5) d.

Shutting dcwn the reactor f r om f u l l pcuer does NOT change the samarium-149 concentration.

(0.5) , F , (**+" CATEGORY H CONTINUED ON NEXT FAGE

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H.

REACTOR THEORY OUESTION H.05 (3.0) _ Your reactor is subcritical and K-effective is 0.98.

Your startup channel reads 50 cps.

a.

When the count rate has increased to 100 cps, what is the new K-eHec t ive? SHOW ALL WORK.

(2.0) b.

Would the reactor be suberitical, critical, or supercritical if enough reactivity was added to double the count rate again? SHOW ALL WORK.

(1.0) OVESTION H.06 (2.0) Will the f ollowing condi tions cause the f uel centerline temperature to increase, decrease, or remain the same? Assume the reactor is operating at 90 per cent of full power.

Consider each separately.

4.

Reactor power is decreased to 50 per cent.

(0.5) - b.

Crud builds up on the fuel elements.

(0.5) c.

Nucleate boiling occurs on the surface of the fuel element.

(0.5) d.

The primary cooling system pump is turned on.

(0.5) l OUESTION H.07 (2.5) t With the core in position 231, K-excess is found to be $3.55.

The core is then moued to position 567.

With the help of the AFRR1 parameters and graphs located at the erid of this exam, calculate the SHUTDOWN MARGIN of the reactor when in position 567.

(2.5) (***** CATEGORY H CONTINUED ON NEXT PAGE *****) - - _ _ _ _ _ _ _.

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REACTOR THEORY QUESTION H.08 (1.5) Your reactor has Just reached criticality after being shutdown for two weeks and is placed on a ninety second period.

Therafter no rod movement occurs.

Later, you find that the p ower increases by a factor of 10 in 300 , seconds.

Have you reached the point where temperature effects are noticeable? Justify your an swer and show all work.

(1.5) OUEST!ON H.09 (1.5) Brief1y exp1ain HOW and WHY the worth of a regulating rod would change if another rod is placed adjacent to it.

(1.5) , l l I t i (***** END OF CATEGORY H *****) ,

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RAD 10 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS OUESTION !.01 (3.0) a.

Briefly de scr i be how n i trogen-16 and argon-41 are produced by the operation of your reactor.

Include the source (s) of these radioactive isotopes and describe where the source (s) is found.

(2.0) b.

Indicate which of the above two radioactive isotopes is more likely to find its way into the environment outside the reactor building.

Briefly explain your answer.

(1.0) GUEST!ON 1.02 (3.0) Work must be performed in Exposure Room 1 where there is a 900 mrem /hr ganma radi a t i on f l e i d.

The person performing the work is 23 years old and has a lifetime exposure through last quarter of 23 Rem as indicated by his NRC FORM 4 and no exposure this quarter.

a.

In accordance with 10CFR20, how long is this person permitted to work in this area? (2.0) b.

In accordance with facility procedures hcw long is this person permitted to work in this area without obtaining special permission to receive a larger dose? (1.0) OVEST10N 1.03 (2.0) After working in an area for 2 hours, a worker discovers that his pocket deseme ter reads oH-scal e.

He inme di a t e l y

1 eaves the area.

A survey indicates that a radioactive source left out of its shield i s reading 1600 mr/hr ganma at a distance of 2 feet.

The man had been working about , 4 feet from the source.

Estimate the dose which the . worker received.

Show all calculations.

i (2.0) i i (***** CATEGORY I CCt4TINUED ON NEXT P AGE * * * * * ) . . ...

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RADIDACTIVE MATERI ALS HANDL ING DI SPOSAL AND HAZARDS OUESTION 1.04 (3.0) List the three conditions which must be satisfied before the exposure rooms may be opened WITHOUT A SAF monitor present.

Assume that no. radioactive material or equipment is to be remoued from the prep area, that the proper entries will be made in the exposure room log, and that the reactor has not been to power in that ER since the last suruey.

(3.0) GUESTION 1.05 (2.0) A radioactive sample was t aken f r om the air going into the stack.

(Assume only one isotope.)

The s-ample was counted at the following times: Time (minutes) Counts per Minute Initial Count 900

740

615

512 100 294 What is the half-life of the sample? SHOW ALL WORK (2.0) (***** CATEGORY ! CONTINUED ON NEXT PAGE

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RADI DACTIVE MATERI ALS HANDL ING DISPOSAL AND HAZARDS QUESTION 1.06 (2.0) In accordance with AFRRI INSTRUCTI ON 6310. ! F, "Management of Injured and /or Irradiated or Contaminated Personnel, indicate whether the follading are TRUE or FALSE.

a.

First aid usually takes precedence over decon-(0.5) tamination procedures.

' . b.

Do not move an injured person, even if he or she is in a high radiation field, until the injured person has been examined by a competent medical professional.

(0.5) c.

The presence of even relatively high levels of contaminat i on rarely cons t i tutes a ha:ar d to the individual.

(0.5) d.

The primary method for decontamination of an individual is through the use of a mild soap , ' and warm water.

(0.5) i OUESTION 1.07 (1.5) Does the biological effect of 10 REM depend on whether it is a neutron or ganea dose? Briefly explain your answer. (1.5) ,

QUESTION !.08 (1.5)

Two centimeters of lead placed at a certain location in a beam of gamma r ays reduced the gamma radiation level

from 400 mr/hr to 200 mr/hr.

What additional thickness of lead placed in this beam would reduce the genma level

! to 25 mr/hr.

Assume no buildup.

SHOW ALL WORK.

(1.5) . ' i j GUESTION 1.09 (2.0) ,

' Consider two point sour ces each having the same curie strength (for example, I curie each).

Source A gamma's i , have an energy of 1 MeV while source B ganma's have an i energy of 2 MeV.

Your obtain a reading fece the same Geiger counter 10 feet from each source.

Would the reeding i free source A be about twice, one-half, or about the same as tha t f rom source B? Briefly explain your answer.

(2.0) , ' l (***** END OF CATEGORY !

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J.

SPECIFIC OPERATING CHARACTER!STICS OUESTION J.01 (3.0) During operation of your reactor, what direction of move-ment of the control rod, if any, will be required to main-tain constant power level by the following changes.

Assume each change occurs independently.

BRIEFLY EXPLAIN YOUR ANSWER.

a.

An experiment containing air that is placed next to the core leaks and fills with water.

(1.0) b.

Conductivity of the primar y cool an t decreases.

(1.0) c.

A boron s_ ample is placed in the core via the rabbit system.

(1.0) OVESTION J.02 (2.0) Consider the Primary Cooling System a.

What is the purpose of the small holes drilled in the Suction and eeturn lines about 4 inches beneath the pool surface? (1.0) 6.

In the event of a large loss of water (belcw core height) due to a reactor leak, what means are ustd to provide water to maintain the reactor coolant level above the reactor core? (1.0) OUE i.T I ON J.03 (2.5) Con s i de r.

the pulse modt.

a.

Explain why the temperature channel norm *11y has no effect on 11miting the peak pcuer generated.

(1.0) b.

Explain under WHAT condition and HOW the temper-4ture channel will have an effect on limiting the pcwer being generated.

(1.5) (***** CATEGORY J CONT!NUED ON NEXT PAGE

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SPECIFIC OPERATING CHARACTERISTICS ' , i i < QUESTION J.04 ( 1. 5.)

Consider the Primary Water Purification Syttem. /hFj/ a.

TRUE or FALSE? Your t e c h;i s al specifications state s that "the reactor shall not L * operated if the

' conductivity of the water is LREATER than 0.2 '

mi crombos/cm a t the output of the purification { system, averaged over one week.

(0.5) i b.

Give two reasons why th6s limitation is necessary. (1.0) , ' i ! ' ' OUESTION J.05 (3.0) ' j Assume your reactor has been at ra ted power f or one week. .

The reactor is shutdown for a period of two hours.

During a ! , this time an experiment is inserted.

Also during this r i time the primar y coolant temperature decreases 5 degrees C.

i . Briefly describe what informat ion would be necessary to

' ' calculate the critical rod posi t i ons.

(3.0) ! i l OVEST10N J.06 (2.0) '

The reactor is oper ating at 500 kW in Mode 1A-AUTOMATIC.

Indicate whether the f oll maing ar e TRUE or FALSE.

Consider each statement separ a t e l y.

- i 6.

When the up button for the r egul e ting r od is pushed.

' the reactor increases in power.

(0.5) , i ! b.

When the up button for the safety rod is pushed, j the regulating rod moves in to the core.

(0.5)

c.

When the mode switch is changed to MODE 11, the

reactor automatically scrams.

(0.5)

i d.

When the mode swltch is changed to MODE !!, the

3-second period rod wi thdrawal prevent interlock ! is bypassed.

(0.5) I

) i (***** CATEGORY J CW4TINUED 04 NEXT PAGE * ** * *) 1, ,

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SPECIFIC OPERATING CHARACTER]STICS QUESTION J.07 (1.5) a.

Which TWO of the following receives i t s p owe r f r om transformer 428 ilocated in room 3152)? (1.0)

i.

G.E. Nuclear Instrumentation li.

Reactor Control Panel 111.

Reac tor Room Radi at i on Moni toring Equipmen t ! iv.

Control Console Voltage Regulator > b.

TRUE or FALSE - If all AC electrical p owe r is lost to , AFRR1, there will be no installed radiation monitoring ' system alarms operable except the cri t i cal i ty moni tor? (0.5) i I , QUESTION J.08 (3.0) '

Your reactor is operating at 1 MW in position 567 with the regulating rod withdaawn 625 units.

If the regulating red is fully inserted, what is K-effective l of the core at this time? Assume no change in pool l temperature or poi son concen trat ion.

Useful ' reactivity curves are appended to back of the exam.

<3.0) ' OVESTION J.09 (1.5) , { List three conditions thet must be satisfied before ER #1 door can be opened.

(1.5) i l )

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FUEL HANDLING AND CORE PARAMETERS QUESTION K.01 (3.5) Your reac tor has Just been taken critical after being shutdown for two weeks.

The follmaing data was noted: ' Core at position 567 ' Safe and Shim rods 100 percent withdrawn Transient rod 250 units Regulating rod 300 units a.

Using app.opriate curves appended to the end of this exam, compute K-excess.

SHOW ALL WORK.

(2.5)

i b.

Is excess reactivity within Tech Spec limits? JUST!FY YOUR 449JER.

(1.0) - QUESTION K.02 (2.0) i Give TWO reasons why your technical specl(i:ations limit the amount of elongation of a fuel element.

(2.0) ! , , i t QUESTION K.03 (2.0) l l In accordance with operat ing Pr ocedure VII, "Reactor Core l Loading and Unloading", indicate whether the follmaing i statements are TRUE or FALSE.

6.

It is permissible to unloed the core under the supervision of the Reector Oper a t i ons Supervi vor. (0.5) s , b.

It is permissible to load the core with Just one nuclear instrumentation channel operational.

(0.5) l c.

Fuel elements are loaded in the core with all rods but the safe rod inserted.

(0.5) i d.

Fuel elements are loaded starting with the Baring l , and C-ring thermocouple elements.

(0,5) i (***** CATEGORY K CG4TINUE0 ON NEXT PAGE

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FUEL HANDLING AND CORE PARAMETERS ^ QUESTION K.04 (? o> Consider the reactivity effect of replacing a fuel element

with new fuel near the center of the core (B-ring) versus the edge cf the core (F-ring).

Which new fuel element will add the most reactivity? Briefly explain your answer.

(2.0) ! QUESTION K.05 (2.5) s Consider the Technical Specifications concerning SHUTDOWN MARGIN.

a.

What is the minimum shutdown margin allowed? (0.5) 6.

For the core position 567 what would be the assumed position of the sh im r od, safe rod, regulating rod, and transient rod when calculating the shutdown margin? (Consider each rod separately.)

<2.0) , OUESTION K.06 (3.5) r The felicwing data was taken during a core loading No. of elements Detector A (CPM) Detector B (CPM)

60

12

44

ss gg

80

42 100 140

142 256 a.

Estime,te the number of fuel elements needed to go critical.

(Use graph peper provided.)

(2.0) b.

Which detector curve did you use for your pr* diction of criticality? JUST!FY YOUR ANSWER.

(1.51 (***** CATEGORY K CONTINUED ON NEXT PAGE +++++) - -

.

' . , ' * K.

FUEL HANDLING AND CORE PARAMETERS QUESTION K.07 (2.0) No week is in progress involving in-core fuel handling or refueling operations, there are no. insertion or withdrawal of in-core experiments, and the reactor is subtritical.

Maintenance is being performed on the regulating rod.

List ALL other required conditions that must be satisfied to secure the reactor.

(2.0) j QUESTION K.08 (1.0) The thermocouples in the ins tr umen ted f uti r od measure temperature (Choose the most correct answer.)

A.

on the surface of the fuel cladding B.

on the outer surface of the fuel , I C.

in the interior of the fuel-moderator sections i D.

in the center of the :irconium rod (1.0) , OUESTION K.09 (1.5) l When storing irradiated fuel other than in the re ac tor cor e, ! ,

what two conditions must be satisfied'in accordance with

Technir.a1 Specifications? your ! ' (1.5) l l I i , l

(***** END OF CATEGORY K ++++*)

I , - - . --.-- t

, . -

. L.

ADMINISTRATIVE PROCEDURES. CONDITI ONS AND L IMITATI ONS QUESTION L.01 (3.0) You are the SRO on duty.

You are al so the only per son at the console.

The reactor is operating at 1 MW in position 567 for an extended run.

If the fire alarm sounds, what are your immediate actions? (3.0) GUESTION L.02 (3.0) ' . The reactor is in the shutdown condition and is about to be secured when it is discovered that the console key ha*. been lost.

What are the minimum staff requirements for this situation? (3.0) OUESTI ON L.03 (3.0) Indicate whether or not each of the follpaing are violations of Technical Specifications.

Briefly explain why it is or is not a viciation.

a.

Operating at full power with one disabled Fuel Temperature Safety Channel (1.0) b.

The reactor is operated at full power for two hours with the purification system input water temperature at 40 degrees C.

(1.0) c.

The reactor was inadvertently pulsed with a ! 13.50 step insertion when a $2.50 pulse was ! planned.

(1.0) t I ! OUEST104 L.04 (2.0) I Give two Technical Specification BASES for the annual surveillance requirements to determine the reactivity worth of each control rod.

(2.0) i i (***++ CATEGORY L CONTINUED ON NEXT PAGE ****+) i i

. o , .

. . L.

ADMINISTRATIVE eROCEDURES. CONDITIONS. AND LfMITATIONS QUESTION L.05 (2.0) a.

Define "burnabler poison".

(1.0) b.

In accordance with your Technical Specifications, what l 11mitation is placed on use of "burnable poisons" in your reactor.

(1.0)

QUESTION L.06 (3.0) Technical Specifications require the f ol l owi ng r adi a t i on monitors to be operebl e dur ing r eac tor oper-at ion s i.

Two ARM detectors lorated in the reactor room (R) and R2).

ii.

One ARM detector placed near each exposure room pl ug door. iii.

A gas stack monitor.

iv.

An ai r par t i cu l a t e mon i t or-in the reactor room.

a.

Indicate the AUTOMATIC FUNCTIG45 (other-than alarms) associated with the above lis ted radiat i on mon i tors i and the purpose of these functions.

(1.0) 6.

What is the reason for placing an ARM detector near each exposure r ocm plug door S (1.0) ' c.

Which of the above listed radiation monitors give j . both an audible and visual alarm in the control room? (1.0) QUESTIO4 L.07 (3.0) a.

Defint Emergency Action Levels (EAL).

(1.0) b.

Briefly describe the difference between a class 0 and a class ! Emergency Action Level.

(2.0) (***** CATEGORY L CG4TINUED Ct4 NEXT F AGE + * ++ + )

. . .

. . L.

ADMINISTRATIVE PROCEDURES. CONDI TI Ce4S. AND LIMITATI ONS QUESTION L.08 (1.0) ! Consider the operating procedures required by your Technical Specifications.

a.

Who n.ay make temporary changes to the procedure providing these changes do not change the original intent? (0.5) b.

Who must eventually review the temporary change? (0.5) " r I . b I > , .

-

1 I ! . i -} r.

I , ' A f = I ,

! . <***** END OF CATEGORY L +++**) l n a - - - _ _ _. _ -, _ .. _ _. .___.r.

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R/hr.= (0.5 CE)'/c (meters)

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1 ga. = 3.78 liters c ' 1 ft = 7.48 gai.

1 kg = 2.21 lbe l Density = 52.4 lbe/f t3 1 hp = 2.54 x 103 8:u/hr

j ' Density = 1 ga/cm3 1 av = 3.41 x 106 8:u/hr lin = 2.54 cm ' Heat of vaporization = 970 5tu/1tc 'F = 9/5'C + 32 , i Heat of fusion = 144 Stu/1te 'C = 5/9 ( *F-32) ! 1 At= = 14.7 psi = 23.9 in. Hg.

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1 BTU = 778 ft-lbf _ _ _ . - - - - - --

.. ._ . ' . , 9 SEP 87 , AFR91-TRIGA REACTOR PARAMETERS . Prompt Neutron Lifetime 39 USec Beta effective (B,ff) 0.0070 Prompt Negative Temperature Coefficient of Reactivity-1.26 X 10-d ak/k/ C (-s0.018/ C)

0 . Steady State Temperature Coefficient of Reactivity-5.1 X 10-5 k/k/ C (-s0.007/ C)

Vold Coefficient of Reactivity-0.2 X 10-# 'k/k/1% Vold Tank Constant 1.40 C/100 KW-hr i

Power Coefficient of Reactivity j 15 Watts to 100KW $0.59 ' 15 Watts to 1 MW $3.47 Nominal Fuel Element Worth (compared to H2O)

RING %*k/k ($) B 0.89 1.27 C 0.73 1.04

0.57 0.82 E C. 31 0.44 F .0.20 0.28 Nominal Control Rod Worthst Stancard Control Rod $1.84 Transient Control Rod 3.66 Standard Control Rod Follower 0.20 Transient Control Rod Follower 0.30 , Other Magle Numberst l '

E = 3.1 X 10 fg33 gen 3fy,gg.3,enne v= 2.47 neutrons / fission REFLECTOR COEFFIENTS , Core Position Rod Position Measured Excess Difference from Pos 567 231 REG 63.3 $3.66 50.51 567 REG 43.2 4.17

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. _ _ _ - _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ - _ _ _Nt'W/'WT c*s tf .____ _ _ _ _. - _ $ikr&'/ A/VlWW We')/ - Ckc / ,e . !

, ( H.

OEACTO7 THEO7Y

i

ANSWERS -- ARMED FORCES RAD 10B10. RES-88/07/21-ROE!NSON, G.

ANSWER H.01 (3.0) -

a.

Rho = Beta /(! + Lambd6 x Tau)

.007/(! + 0.1 x 60) = '.001 (1.5) ! = i b.

Rho =.001 +.001 =.002 Tau = (beta - Rho) / (Lambda x Rho) l (.007 .002) / (0.1 x.002) = 25 seconds ( 1. 0 )

= Doubling Timt = Tau x In2 = 17.3 seconds (0,5) ! NOTE: If applicants answers e. e * + a.

incorrectly, use ! epplicant's answer to r**t 6.

to c61culate the I answer for r. 6 * t b.

i ', REFERENCES ! AFRR1 Refertnet Package, Ref+rence tou6tions l Reactor Ope r a tor RtQuel i f i c 6 t i on Pr ogr em H - 26.2 p.21 j Fundamentals of Nuclear Reactor Engineering p.

! i . ANSWER H.02 (2.5) .g, g 3,,, y g ggg a.

Present st6etup ocwer level will be icwer.

(0.5) ! For 4 given reac t ivi ty 4ddi tion, suber i t ical { l multiplication results.In 6 Icwtr neutron population t ' incetest for the r eactor wi th the icwtr initial neutron ' popul6 tion.

(0.75) { b.

Critical rod positions will be appr oxima tely the (0.5) s6me.

The eritical eod posl tion is dependent upon the potitive reactivity necessary to bring the etector critical and is independent of source magnituce.

(0.75) REFERENCE Schult:, M.

A., Control of Nucitar Rtectors and Fewer Plants p.

17, 372.

, l ANSWER H.03 (2.0) 6 degrets reactivity change = -6c x -80.007 / c = +s0.042 (0.5) At 400 units rod worth = so.54 (0,5) Total r ed wor th = 50.54 so.042 - 30.25 = so.74e (0,5) + Rod position is 475 units (0,5) REFERENCES AFRE! Reference PacKept Fundementals of Nucitar Reactor Engineering P.

,

. o l - . ..

N.

REACTOR THEODY ANSWERS -- ARMED FOROES RADICBIO. RES-88/07/21-ROBINSCN, G.

ANSWER H.04 (2.0) ! 6.

FALSE (0.5) I b.

TRUE (0.5) i c.

TRUE (0.5) l d.

FAL!E . (0.5) l REFERENCE Funcemental s of Nuclear Enginetring p.

64-91 l t , ANSWER H.05 (3.0) 6.

[1-2 = 1-(V-+441) = 2 = 1. 09

(K-eff2) =

(2.0) t CR-1 1-(K-+ff2) 1-(K-eff2) l b.

1-fV-+442)_= 1 = 1 .cc

(K-eff3)

0.9t5 (0,5) l = 1-(K-tif3) 1-(h-tif3)_ L i t THEREFORE THE REACTOR !! ST!LL SUBOR!TICAL (0.5) REFERENCE ! Fundament &ls of Nucitar Rt6ctor Engineering p.

144-146 l AFRR! Reftrence Pack +pt i ANSWER H.04 (2.0) i 4. Decetate to.5) b.

Increest (0.5) C. Decreest (0.5) ! c. Decreest (0.5) t REFERENCE Func6mentals of Nucitar Reactor Engineering p.

100-110 Lamer s h, J.

R., Introcyction to Nuclear Engineering p.

221-026, 342-350 l , l

1 . .

.____ ... . .. . .* ,

. r .. . H.

REACTOR THEOPY ANSWERS -- ARMED FORCES RADIOB10. RES SS/07/21-ROBINSON, G.

ANSWER H.07 (2.5) K-excess in position 567 = s3.55 + s.51 = s4.06 (1.0) Total red worth 9 3.46 + s t.86 + s t.32 + si, e5 = s p.19 (1.0) Shutdown margin a s?.19 - s4.04 = s5.13 (0.5) REFERENCE AFRRI glossary - r od wor' th, shutdcun margin, excess reactivity Reference pocket AN!MER H.08 (1.5) P(t) = P(o) exp(t/ tau); In 10 = 300 sec/ tau t 6v = 300 s ec/2.3 = 130.2 s e c on ds-(1.0) The period has become l onger, therefort the neg6tive temp &raturt coefficient has r educed the reactivity.

(0.5) REFERENCE Reactor Oper 6 tor Requal i fI c6 t i on Progr6m H-2e.3, p.

Fundamentals of Nucle 6r Re6ctor Engineering p.

64, 138 ANIMER H.09 (1.5) P16cing 6 second rod ed)6 cent to the first red will depress the flux in that are6 6nd thus decreast the worth of the first rod.

(1.5) REFERENCE Fundament 41s of Nuclear Reactor Engineering p.

_

_-

__ _ _ _ _ _ - _ _. - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.._____________ _-__ __ _ ____ - ____ _ _ _ _ _ _ _ _ _ _ _ _ - _ .

. , I.

RAD 10 ACTIVE MATERIALS HANDLING DISPOSAL c,qD w, Appg

r ANSWERS -- ARMED FORCES RADIOBIO. RES-88/07/21-ROE!NSON, G.

! ANSWER !.01 (3.0) i t a.

N-!d is produced by fast neutron activation of oxygen

in the coolant water in the vicinity of the core.

(1.0) l Ar-41 is generated by neutron activation of Ar 49, 6 constituent of air, disolved in the coolant water ' and in the air of ;r _ _.; t :" 't-

" the ^ ..... - - - exposure rooms.

(Each part werth 0.2tpointt.)

(1.0) , b.

Ar-41 is most Ilkely to end up in the environment.

(0.5) N-16 has 6 seven second hklf life and etcars befort ! , It becomet en environmental pr obl em.

(0.5) [ REFERENCE AFRRI SAR p.

22, 23 ! ! ANSWER !.02 (3.0) a.

5(2?-18) = 25 Rem (0.5) Lifetime limit = 25 - 23 = 2 Rem (0.5) l . With Form 4 on f i l e, per s on permi t t e d 3 Ren/q tr. l Ilfttime limit is more restrictive.

(0.5) 2.0 Rem /(0.9 Ren/hr) 133 minutes (0.5) = i b.

Feelinty ilmit is 50 mr/ cay (0.5) i 50 mr/(900 mr/hr) 3.3 minutes (0.5) = REFERENOE ! 10CFR20.102 Heatth Phytict Proceduet 3-1-3 I l l

ANSWER !.03 (2.0)

D1/(R2 X R2) = D2/(R1 X RI)! 1600/(4 X 4) = D2/(2 X 2) ! ' D2 = 400 mr/hr (1.5) For 2 hours he received 2 x 400 mr = 600 mr (0.5) REFERENCE Lamarsh, J.

R., Introduction to Nuciter Engineering p.

40? ~

- _ _ _ _ _ , . . . l, i ' f

, i !

1.

RAD 1OACTf UE MATERI ALS HW4DLING DISo0 SAL AND HAZARDS ANSWERS -- ARMED FORCES RADI CBI O. RES-08/07/21 -ROE!NSON, G.

l , t

ANSWER 1.04 (3.0)

2.

The last survey indicated that there were no radiation f levels in excess of 100 mr/hr in any area of the ER where ! l extenced stay time is possible.

(1.0) { l 2.

Survey meter readings at the door indicate saft entry I conditions (less than 1 mr/hr).

(1.0) ! 3.

The ER / Cam should be observed and its reading (net) [ shoulc be less than 200 CPM above background.

(1.0) ' REFERENCE l Operating Procedure ! Conduct of Experiments. Tab A-Se F+ actor Operator Recualification Program !!b p.3 > i ANSWER 1.05 (2.0) I , A = Aa e(-lambda x t) In(900/294) = lambda x 180 lambde =.00623/ min (1.5) t(one-half) = 0.693/lambca = 111 minutes (0.5) L REFERENCE

i Lamersh, J.

R., Introduction to Nuclear Engineering p.

{

I ! ANSWER 1.06 (2.0) { a. TRUE (0.5) b.

FALSE (0.5) i c. TRUE (0,5) l d. TRUE j (0.5) i REFERENCE i AFRRI Ins truc t i on 6310.1F ! {

! ! l L

_ - - - .

l . l [ .. . 1, RADIDACTIVE MATERI ALS HANDLING DI?POSAL #4D M?ARDS

s

4SWERS -- ARMED FORCES RADIOE',0. RES-86/07/21-Roelt4 SON, G.

i l ! l ANSWER 1.07 (1.5)

NO (0.5) ! l The unit REM considers the different effects. REM is e , bi ol ogi c al unit, t hute different radiation causing the same ' dose in REM should have the same effect.

(1.0) l l REFERENCE 10CFR 20 AFRR1 Glossary p.

t ! ! ANSWER !.08 (1.5) i One half thickness is 2 centimeters of lead.

(0.5) i Need three more half-thicknesses to r educe 200 mr/hr to ' 25 mr/hr.

Theref ore need six (6) additional centimettes

of lead.

(1.0) l . REFERENCE Ra di ol ogi c al Health Handbook p.

426 l ,

ANSWER !.09 (2.0) ' I About the same (1.0) ' Geiger counters are not energy dependent (1.0) t REFEREMCES Fundamentals of Nuclear Reactor Engineering p.

142 < i i l , , ! l l l i

1 - . - - - - -_ _ - -. -,. - - - - - - -

. ... . ._.

. . . . . . l ' ,

.

J.

EDEC1F!C ODERATING C E PAC T t,f)T', i ANSWERS -- ARMED FORCES RADIOUIO. RES-88/07/21-ROBINSON, G.

i .. t

45WER J.01 (3.0)

i . a.

Rod will be inserted.

(0.5) ' Water is a better reflector (scatterer) than air.

(0.5) b.

No ef f ec t.

(0.5) Variation of conductivity within the allcwable operating limits will have no effect on reactivity.

(0.5) c.

Rod will be withdrawn.

(0.5)

Boron has 6 largt absorption cross section thus

nepetivt re6ctivity will bt 6dded.

(0.5) ' REFERENCE ! Fundament +1s of Nuclear Engineering p.

40, 73

I ANSWER J.02 (1.0) 4.

These holes prevent water f rom being typhoned out of the reector pool and uncovering the core in the event , i of a prim 6ry coolant line leak or rupture.

(1.0) ! b.

An emergency illl line will be connected from an outside, i

d.locent hydr 6nt main to the primary cool 6ht loop.

(1.0) ! REFERENOE SAR p. 3-16 ! > ! , ANEWER J.03 (2.5) I a.

The timt constant of the temper 4ture channe1 is ! relatively long (seconds) when comptred to the pulse l width (mi}listconds).

(1.0) l b.

In the event that W culte red remains stuck in the , fully witherewn position, tM t +is p r e i, w e r wiimurl ! W - c w + t--4 F e -: i t ' i-t '-!N (0.75) Tni;

m: *.- 3 3. rm +

e.' ::.n g z geri+r e i; 4 W , i c u t t i n g t h'69 ttt"-of a.p uis ta:1.W tr-t r e n i 4 e r. 5 -th e n ou gh r s a c t i v i-ty-t o-e xc e e d-t h e~ 1 e mpir e s t ure= - j i

1 i yd.U.n "es alt.t x s yit err s + t-t rrrp (0.75)

l

REFERENCr.

i Tech Spec p.

Section 2.2 *Easis' !)cTC ' f T full P * wt ** ** A4 '4 Y* # * ' 'l C'

ll "*

' I mpw e es htg eSrh A j +Y?, 4'fr whf 1 * sh t! WoH /o's// l r br /s sa 1$g, (**iS *: ?c t e ** pH oe /. T!< y t *4 f M^ * S O V'** * * .elyo if foy kp flan tior n o / <r% 8' N 2 e.e. r o k J +: o i sp ei,~ . - - - . - - - .

__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ ____ __ __ _ _ -_______-_ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ ______ ____ _________ - _ - _ _ _ _ _ _ _ _ _ _ - v a

. . !. l J.

?pECIFIC ODERATING CERACTERfSTICS l ! ANSWERS -- ARMED FORCES RAD 10B10. RES-SS/07/21-ROBINSON, G.

i l l

l ANSWER J.04 (1.5) ! I a.

FALSE (0.5) b.

i. This value is an acceptable level of water-borne contaminants in an aluminum / stainless steel system.

Based on experience, activation at this level coes not pose a significant r adiological haz ar d.

(0.5) li.

This value is consistent with the fuel vendor's experience and with similar reactors (0.5) REFERENOE Tech Spec p.

12 and p.

13, Stetion 3.3 *Besis" AN!MER J.05 (3.0) Previous rod positions.

(0.6) Xenon shu tcewn vs. r e ac t ivi ty curves (or calculate it).

(0.6) Worth od experiment added (0.6) Reactivity cecrease due to burnup (0.6) Negativt temperature coefficient (0.6) REFERENCE Fundamentals of Nuclear Reactor Eng6neering p.

S0, EB, 97 ANSWEH J.06 (2.0) 6.

FALSE (0.5) b.

TiwE T W (0,5) c.

FALSE (0.5) d.

TRUE (0.5) . REFERENCE Operations Manuti p.

??, 9e AN!WER J.07 (1.5) 4.

3.

and lii.

(1.0) b.

T1ree r/u r-(0.5) FEFERENCE Operations Manual p.

L

. _ _ . _ _

. '. \\ , t j .- j J.

SPECfF1C ODEEATING C upACTEPTeT1CS i l

I ANSWERS -- ARMED FORCES RADICBlo. RES-86/0?/21-ROBINSCt4, G.

i s i ANSWER J.08 (3.0) ! Frewn regui s t i ng r od curve - inste t ing rto. r oc adds - $1.15.

(1.0) Pcwer ceftet free AFRR1 par amt ters = l 93.47 N (#} 41 - *!.15) x.007 = 0' # A l (1.0) I RACs N t (T ' . __ ."-

,;i.: .

g,, t /.e /4 T (1.0) I ' ' C wi.e k wseet k e sh***8***w) \\ REFERENCE ' AFRR! Re f er tric t P6cket AFRR3 Gl os s ar y, Fewer Cotificient of Reactivity !

AN%tER J.09 (1.5) ! i a.

Le ad sh i e l d door s. mus t t.t closed.

(0.5) , b.

Cort celly must bt in Position 3.

(0.5) ' c.

Ettetrical pcuer control box to ER #1 door must i be unlocked thd turned on.

(0.5) i F.IFERENCE ' operatiens Manuel p.

104 ! ! !

I I l i , I l . - - .

t l s ! . . l o ! ! , . K.

FUEL HANDLING #4D CORE PARAMETERS i j ANSWERS -- ARMED FORCES RADIOBIO. RES-88/07/21-ROBINSON, G j ! ' i

! i

45WER K.01 (3.5)

i I ! " 4.

K-excess " total transient rod worth - tr ansient rod

' worth at 250 units + tot 61 et, rod worth - re, rod j i worth at 950 units.

(1.5) i

s3.64 - so.7 + s t.22 - so.30 = S4.48 (1.0) ! ' b.

YEt, K-excess is within T.S.

timits (0.5) ! T.S. limit is 95.00 i (0.5) '! , j REFERENCE k Oper6 tion Procedure VI!!. TAE: D a Reittence P6cket i j Tech Epec 3.1.3 ! l i ! l

i ANSWER K.02 (2.0)

6.

To essume that the cleeding materit) will not be f l sub)tettd to stresses that could caust 6 loss of l l Integrity in the fuel containment.

(1.0) l b.

Assure acequate coolant flew (1.0) i < { . REFERENCES l i Tech Spec 5.2.2e

EA!!S*

p.

i j

{ i !

ANSWER K.03 (2.0) ! i 6.

TRUE (0.5) l b.

TRUE (0.5) c.

FALSE (All roes insertec) (0.5) ! ,

c.

TRUE (0.5) { i l REFERENCE . {

Oper6 ting Proceevre v 1, Re.ctor core toeding ane Inte6 ding

i

! l ._

- - _. - _ _ - - - - .- .- _. _. ~ - .. - .-_ -- l O l .,. , J , , i ' ! , ! i , M.

FUEL 4t*NDL ING #4D CODE PARA *iETERS

45WERS -- ARMED FORCES RADIOE!O. RES-SS/07/21-R00!NSON, O.

!

- J ' . i !

ANSWER K.04 (2.0) i a 4.

Near the center of the cor e (E-ring) (0.5) { l b.

Replacing a fuel element note the tage of the core does J ! nc.t add as much reactivity because more of the fission

l neutrons are lost due to leakage.

(1.5)

REFERENCE , Referene. R.evet ) Funcementals of Nuclear Reactor Engineering p.

i

l

) AN!WER M.05 (2.5) . ' i I I a.

Mi n imum s hu tdcun mar gi n is 90.t0.

(0,5) i b.

Transient rod fully withdrawn (0.5) = i Safe rod fully inserted (0.5)

- ) Shim rod fully inserted (0.5) - Regul a t ing r od - fully inserted (0.5) ' i

REFERENCE i j Tech Spec 3.1.5.b p.

I , l { s ' s !, ANSWER K.06 (3.5)

'

' j a.

55 tiements t (1.0) i l Freper calculation of Co/C (0.5) ! ) Reoper plotting of points (0.5) ! J b.

Detector E curve (0.75) l Detector A curve is nonconservative bec6use the t6ngent i to the curve h6s & continually increasing slope.

(0.75) ! ' i REFERENCE Fundament 61s of Nuclear Reactor Engineering p.

147-15C l

' I , l

! J ! l

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. ., . e . - k.

FUEL HANDLING AND CORE PARAME EAS ANSWERS -- ARMED FORCES RAD 10 BIO. RES-88/07/21-ROBINSON, G.

ANSWER K.07 (2.0) '.e reactor must be subcritical by $0.50 of reactivit s a SAv, dem " y wi t h the most reac t i ve rod removed. 4.e be+,v (3,c) The console key switch is in the "off" position and the key is removed from the console and is under the control of a licensed operator or it stored in a locked storage area.

(1.0) e t/orr - Tera, syse de k sn ee e t $8v t C ** N' It sufre n +r tol b 9 cose y REFERENCE Tech Spect 1.1? p.

ANSWER K.08 (1.0) C. In the interior of the duel-moderator section (1.0) REFERENCE SAR p.

4 - 14 ANSWER K.0? (1.5) a.

Stored in an array that will permit sufficient natural convection cool ing by air or water (0.75) b.

Storage shall be such that groups of stored fuel elements will remain tuberitical under all conditions of moder a t i on. (0.75) REFERENCE Tech Specs 5.8 p.

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ADMINTSTReTIUE PROCEDURES. CONDITIONS AND L!MITATIONS ANSWERS -- ARMEO FORCES RADIOBIO. RES-88/07/21-ROBINSON, G.

ANSWER L.01 (3.0) ' Scram the reactor.

(0.5) Secure any exposure facilities.

(0.5) Remove logbook, emergency guide, teletector tool Kit and keys.

(1.0) Report to EAS.

(0.5) Do not lock reactor doors.

(0.5) REFERENCE Operating Procedure VI, Emergency Procedures AFRRI, Emergency Scenerios (No. 2) ANSWER L.02 (3.0) , Since the reactor is NOT secured ' SRC on call (0.75) RO or SRO in the main control room (0.75) Radiation Control Technician on call (0.75) Another person within the AFRRI Complex (0.75) REFERENCE Tech Spec 6.1.3.2 p.

- ANSWER L.03 (3.0) I

. a.

T.S. viointion (0.5)

Two Fuel Temperature Safety Channels are required for operation.

(0.5) , 6.

No T.S. vi ol at i on (0.5) Above 5 kilowat ts and above 60 degrees C. woul d be a T.S. violation.

(0,5) c.

No T. S. v'i ol a t i on (0.5) Maximum step insertion allowed is $4.00.

(0.5) REFERENCE Tech Spec 3.2.1 p.

9, 3.3 p '. 12, 3.1.2 p.

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.= L.

ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS ANSWERS -- ARMED FORCES RADI OBI O. RES-88/07/21-ROBINSON, G.

ANSWER L.04 (2.0) a.

To assure that the required shutdown margin is available.

(1.0) b.

To provide an accurate means for determining the reactivity worths of experiments in the core.

(1.0) , REFERENCES Tech Spec 4.1 "b4 SIS" p.19 ANSWER L.05 (2.0) 6.

Any material with a large neutron absorption cross section which, when it aosorps a neutron, is converted into material wi th a l ow abs orp t i on cros s sec t i on. (1.0) b.

Any burnable poison used for the specific purpose of compensating for fuel burnup or long-term reactivity adjustments shall be an integral pcrt of the manufactured fuel elements.

(1.0) REFERENCE AFRRI Definitions Tech Spec 5.2.1d p.

ANSWER L.06 (3.0) 4.

Alarm of the air particulate monitor will cause closure i of the pos i t ive sealing dampers and (0.5) cause reactor room isolation.

(0.5) I b.

To detect streaming radiation (1.0) c.

Air particulate monitor (0.5) R1 of the reactor room ARM's (0.5) REFERENCE Tech Spec p.14 , Operations Manual p.

111-134 ' SAR p.

3-25 to 3-34 .

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ADMINISTRATIVE PROCEDUPES. C@aD'*rf 04S AND LIMITATI ONS ANSWERS -- ARMED FORCES RADIOBIO. RES-88/07/21-ROBINSON, G.

ANSWER L.07 (3.0) - a.

EALs are theshol ds f or establi shing (en tering) an l emergency, class (1.0) b.

Class 0, events less severe'than the l owe s t category, are even ts generally per ipher al to reactor operations. (1.0) Class 1, notification of unusual events, consists of a situation that exists or develops that presents a potentially serious ha:ard to the reacto'. (1.0) i I REFERENCE Emergency Plan p.30, 45 and 48 ANSWER L.09 (1.0) a.

Reactor Operation Supervisor or Reactor Facility Director (0.5) b.

Reactor Facility Director (0.5) REFERENCE Tech Spec 4.3.2 p.

34 }}

IR 05000170/1988003

Text

REGION I

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