ML20155C568

Exam Rept 50-186/OL-88-01 on 880912.Exam Results:One Candidate Passed Exam

ML20155C568
Person / Time
Site:	University of Missouri-Columbia
Issue date:	09/29/1988
From:	Damon D, Jordan M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20155C559	List: ML20155C555 ML20155C568
References
50-186-OL-88-01, 50-186-OL-88-1, NUDOCS 8810100100
Download: ML20155C568 (46)

Text

o U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-186/0L-88-01 Docket No. 50-186 Licensee: University of Misscuri Research Park Columbia, MO 65201 Examination Administered At: Columbia, Missouri Examination Conducted: September 14-15, 1988 Examiner: 7- 7!29/ft D. W Damon ,

Date Approved By: ((I I M. J. Jordan,' Chief 'Date Operator Licensing Section 1 Examination Summary Examination administered on September 14-15, 1988 (Report No. 50-186/0L-88-011) to one Reactor Operator candidate.

Results: The candidate passed the examination.

8810100100 880929 PDR ADOCK 050 6

s 0

, REPORT DETAILS

1. Examiners

0. J. Damon

2. Exit Meeting On September 16, 1988, the examiner met with Mr. W. Meyer to discuss the results of the examination. The examination was reviewed, with results as outlined below. Due to the fact that there was only one candidate, no comments of a general nature were made.

3. Examination Review The following comments were received during the review and are accompanied by their respective NRC resolutions.

Question F.04 Facility Comment

Although this answer is correct, the way the question is worded, another obvious reason for not allowing the startup exists. 50P I.4.2.E states that "Operations affecting changes in core reactivity, other than normal steady state power control, i.e., refueling, startup, etc., will be directly supervised by a senior operator "

The question asks "Do you let him perform the startup under your supervision?" Since our candidate is seeking to be licensed as a reactor operator and not a senior operator his answer would be "no", becausc he is not a senior operator.

If the question had asked "Should the senior operator or shif t supervisor have allowed such a startup," the original reason for answering "no" would ,

have been sufficient. '

NRC Resolution Comment accepted. Answer Key modified to accept the additional answer, l

1 Question F.05 1

Facility Comment The answer to F.05(0) should be False as per 50P II.1.3.B.3 which states "bring the reactor to the desired power level on a period > 35 seconds, utilizing the reg blade in such a manner as to insure that it is greater than 60% withdrawn when the desired power level is reached.

NRC Resolution Comment accepted. Answer key modified.

2

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hEACTOR TYPE: I F 5 T _ ,_ _ _ ,, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

DATE ADMINSTERED: 09/92/19_,,_,________,,,.,__

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EXAMINER: D A M 0 t h. _ D 1_ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _

CANDIDA1E _______.,______________ _

.U O T bU 91] uro . J o l egp! pA Ig1 une s t:n e r e t e poper for the answers. Writo answers on o") e side onlN.

Stziple question thunt on top of the answer sheets. Points f or each nu e.it i o n err indicated in parentheses a+ter t h e.s question. The pastino (1rade reautres, at leas t 7 f.4 an each category. E:< ami nati on papor n will he p 1 (,. 6 e d up ban t c,1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, ettur t r.e tasiatnataco ut 6r td.

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• ~ CATE0 CRY CATE60Ri con' I f AT E' S

_ 't' O L l l E. _10JAL _ ._ _ R l! h l _ . _ _ E d'eU E. _ _ _____________._ GAT QOhY

_IS. W _. _14 . A ' . A. F RINCIF LES OF fiEACT OR OF ERftT ION

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L. L;ENE hoL UFEhATINu CHAhsCTEh!S71CS

_ l h n _ _ _19 . s -- . _ _ _ . _ _ - . . _ . _ . . _ D. INSTRUMENTS AND CONTh0L5

_. ) D ' _ 19.4' _ _ _ _ _ . , _ . . _ . . . _ _ _ _ _ .

E. CAFETY AND EMEh0ENCY SYSTEM 6

_}h!"' _ 194 4i _ . _ _ . . _ . . ________

F. ElANDARD AND EMEhGENCY Ok'ERATING F- R OC E DURE S

_lb,N' 14 , 4 ::

G. RADIATION CONThDL AND EArETy  ;

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1 .s NRC F(ULES AND GUIDELINES FOR LICENSE EX AMINATIONS During the a'dministration of th10 examination the following rules apply l 1. Eheat'ing on the examination meann an automatic dental of your application and could result in more severe penalties.

2. Restroom trips are to be limi ted arid only one candidate at a time may leave. (ou niust avoid all contacts with anyone outsido the examinetton room to avoid even the appearance or possibility of cheating.

! 3. Uso black ink or dark pencil only to facilitate legible reproductions.  ;

4 Fr1nt your nane in the blenk pr ovi ded on the cover Rheet of the examination.

5. Fall in the date on the cover chnet of the examination (if necessary).

)

c. Use cnly the paper orovided tor answers.

]

) 7. Feint your name an the upper right-hand corner of the first page of each

, section of the answer sheet.  ;

i C. Connecutivolv r o mbe r cich Ennwer shent. write "End cf Categcry __" as appropriate, start esch category on a new page, write only on one side t of the p.,per. and writtr "Last Page" on the last answer sheet.

4 9 Numcer each answer as to category and number, for example. 1.4, 6.3.

4

10. Sb ip at leant three 11 net between each answer.

11. Separato enroor sheets from Dad and place finished answer sheets Feco 3

down en vcur desh rr a table.

12. Usn ebbreviationt Shly if tht'y are commonly uted in facility lateraturr.

) 1

12. The point value for each question as indicated in parentheses after the  !

questic,n and con be used at a guide for the depth of ansuor required.

J j 14. Show all calculations, methcds, or assumptions used to obtain an antwer I to matScnaticol pr ot> l om s whCther indicated in the Question or not.

], 1 1 1 *; . Fartial credit may De given. Therefore. AN DER ALL FARTG OF THE )

DUE311 ON AND DO NuI LLWE ANY AN5WER 14 ANL ,  !

1 4 l j lo. If parts of the eaamination are not cleer au to Intent. att cuest i cos of j the e cmt ner on t v.

I 1 '/ . You moet cign the statement en the cover sheet that Indicates thet the w7r 6 1s scur own and sov hase not received or been given assistance in conpieting tne esamination. This m u ti t be done after the enamination h a t.

been concleted, l

4 1

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. . . .. ~ -

j . I c.

18. When vou complete your examination, you shall i

. a. Annombic your examination as follows: .

i (1) Exam questions on top.

l (2) Exam aid s - f igures, tables, etc. l (3) Answer pages including figures which are part of the answer,

b. Turn in your copy of the examination and all pages used to ar.swer the examination questions,

c. Turn in all scrap paper and the balance of the paper that you did i not use for answering the questions. .

4

d. Leave the e;t aminati on area, as defined by t he ex eini nor . If ofter ;

leaving, you are found in than .*rea while the examination tu ntill  :

sn prc.greto, yeur licente mey be denied or revoted.

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Volume 10  :

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3 1 gm/cm = 62.4 lbm/ft Density of water (20 C) = 62.4 lbm/ft f 3 [

i 1 gal = B.345 lbm 4

3 1ft = 7.48 gal Avogadro's Number = 6.023 x to

- 7 1 gal = 3.78 liters Heat of Vapor (H O) = 970 Btu /lbm

2 1 lbm = 454 grams Heat of Fusion (ICE) = 144 Btu /lbm

e = 2.72 1 AMU = 1.66 x 10" 4 grams  ;

i f n = 3.14159 Mass of Neutron = 1.008665 AMU e

!  ! KW = 7JB ft-lbf/sec Mass of Proton = 1.007277 AMU 1 kW = 3413 Btu /hr Mass of Electron = 0.000549 AMU i

1 HP = 550 ft-lbf/sec One atmosphere = 14. 7 psi a = 29. 92 in. Hg J

1 HP = .746 KW 'F = 9/5 'C + 32 '

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g = 32.2 lbm-ft/lbf-sec c = 931 MEV/ AMU l

8 1 inch = 2.54 cm C=3x 10 m/sec

~0 Btu /hr ft R*

r = 0.1714 x 10 1

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Pcgo 4 cf 5 08IO SOEEI eVEseQE_lutadeL.CONQuCIIVIIY_1El deteclel E 0.025 Cork Fiber Insulating Board 0.028 M:ple or Oak Wood 0.096 Cullding trick O.4 Window Glass 0.45 Concrete 0.79 1*/. Carbon Steel 25.00 1% Chrome Steel 35.00 Aluminum 110.00 Copper 223.00 Silver 235.00 Water (20 psia, 200 degrees F) 0.392 Steam (1000 psia, 550 degrees F) 0.046 Uranium Dioxide 1.15 Helium 0.135 Zircaloy 10.0 d1SCELLeNEQUS.INEQBdel10N 2

E = mc 2

KE = 1/2 mv PE = mgh V, =VO + at Geometric Object Area Volume Triangle A= 1/2 bh /////////////////

Square A = 5' ///////////////5 koetangle A=Lx W /////////////////

Circle A = wr 2 /////////////////

Rectangular Solid A = 2(LxW + LxH + WxH) V4 Lx Wx H Night'Ctreular Cylinder A= (2 nr2)h + 2(wr'l) V = wr#h A=4 we z V = 4/3 ter2)

Sphere 3

Cube ///////////////////////////// V=S

Pcgo 5 of 5 00IO_SUEEI d1SLCLL*tMduS_7.NEQBb8I1ON_1coattowedi 10 CFR 20 Appendix B Table I Table II Gamma Energy Col I Col II Col I Col !!

MEV per Air Water Air Water Material Half-Life Disintegration uc/ml uc/mi uc/ml uc/ml

-6 ~8 Ar-41 1.84 h 1.3 Sub 2x10 ----- 4x10 ------

~7 ~0 -0 Co-60 5.27 y 2.5 S 3x10 1x10"I 1x10 5x10

~D 1x10 ~10

~'

1-131 8.04 d 0.36 S 9x10" 6x10 3x10

~3 ~#

Kr-85 10.72 y 0.04 Sub 1x10 ----- 3x10 ------

~3 ~8 ~4 Ni-65 2.52 h 0.59 S 9x10~' 4x10 3x10 1x10

-12 -4 ~I" -6 Pu-239 2.41x10" y 0.008 S 2x10 1x10 6w10 5x10

~

~D ~11 ~7 Sr-90 29 y ----- S 1x10 ' 1x10 3x10 3x10

-6 Xe-135 9.09 h 0.25 Sub 4x10 -----

1x10"# ------

Any single radionuclide with T > 2 hr 0 9x10 ~0 which does not decay by alpha br

-6 3x10" 1x10 3x10 cpontaneous fission 2

Neutron Energy (MEV) Neutrons per cm Average flux to deliver equivalent to 1 rem 100 mrem in 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> 6

thermal 970x10 670 6

0.02 400x10 - 280 (neutrons) 43x10 66 0.5 30 ----------

10 24x10 37 g,2 x ,,c Linear Absorption Coefficients p (cm~A)

Energy (MEV) Water Concrete Iron Lead 0.5 0.090 0.21 0.63 1.7 1.0 0.067 0.15 0.44 0.77 1.5 0.057 0.13 0.40 0.57 2.0 0.048 0.11 0.33 0.51 2.5 0.042 0.097 0.31 0.49 3.0 0.030 0.088 0.30 0.47

,81.[_EBINDIELEp_DE_BE8CIQB_QEEB8IlON Page 2 QUESTION A.01 (1.00)

Briefly explain the difference between K effective and K infinity.

QUESTION A.02 (2.25)

Describe what is meant by each of the f ollowing terms: (.75 ea)

a. Prompt Neutrons

b. Delayed Neutrons

c. Thermal Neutrons DilFSTION A.03 (1.50)

You are required to increase power from 1 watt to 10 KW in 10 minutes on a smooth ramp. Calculate the reactor period required to accomplish this.

Show all work.

DUESTION A.04 (1.50)

How much reactivity has been added to a subcritical reactor if the count rate has increased from 75 cos to 150 cps and if the initial value of Keff was .95?

DUESTION A.05 (0.50)

You are performing a reactor startup and add enough reactivity to double tne count rate. If the same amount of rec.ctivity were again added to the st.:b c r i t i c a l reactor. what condition would the reactor be in? Limit your answer to SUBCRITICAL, CRITICAL. OR SUPERCRITICAL.

(4to** CATEGCRY A CONTINUED ON NEXT FAGE **44*)

)

,8t__EBINCIBLES_OE_8E8QIQB_OEE88IlgN Page 3 QUESTION A.06 (0.75)

The -80 second period (-1/3 DPM SUR) following a reactor trip is caused by which of the following?

a. The decay constant of the longest lived group of delayed neutrons precursors,

b. The ability of U-235 to fission with source neutrons.

c. The amount of negative reactivity added on a trip being greater than the Shutdown Margin.

d. The amount of negative reactivity added on a trip being greater than beta.

QUESTION A.07 (1.50)

Assume that a Plutonium-Peryllium neutron source used in a reactor was a S curie source when it was manufactured 30 years ago. If that source were replaced by a new 5 curie source, what would be the change in counts per second seen on the startup channel? Show all calculations and state all assumptions. Hasume,that today's c .nt rate before replacement is 1000 counte per second.

DUESTION A.08 (1.50)

Describe the nuclear reactions that take place to produce neutrons from a Plutonium-Beryllium (Pu-Be) source.

QUESTION A.09 (3.00)

For each of the following terms from the four-factor formula. give a werd i

definitions (1.0 ea)

a. fant f i ssi on factor (epsilon)

b. reproduction factor (eta)

c. thermal utilication factor (+)

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l I

($4*64 CATEGORY A CUNTINUED ON NEXT PAGE *64**)

l

f Pago 4

. 6t__EBING1ELEji_QE_BE6GlQB_QEE8611QN s

QUESTION A.10 (1.50)

An irradiated sample, just removed from the reactor. reads 21 mrem /hr on an Eberline beta-gamma instrument. A survey 30 minutes later shows 1.2 mrem per hour. Calculate the half-life of the irradiated sample.

i (6**6* END OF CATEGORY A *96**)

1 et__EE81UEgs_QE_ESClLIIX_QE@l@N Page 5 i

1 1

l OUESTION B.01 (1.50)

Describe the makeup of the fuel material, including materials used and enrichment.

QUESTION B.02 (1.00)

What two conditions must be satisfied before the control rod startup interlock may be bypassed?

QUESTION B.03 (2.00)

What are four kinds of c:: p er i men t al facilities at MURR7 l

l CJESTION B.04 (3.00)

List or describe 6 signals or conditions that will result in a rod run-in.

QUESTION B.05 (2.00)

Per Technical Specifications, what are the four major loads that the emergency generator must be able to supply?

DUESTION B.06 (2.50)

Concerning the pressuri:or system l

a. Briefly describe automatic pressure and l evel control of the pressuricer. (1.0)

b. What scram functions are initiated from the pressurt:er system?

Setpoints not required. (1.5)

DUESTION D.07 (2.50)

Describe the automatic operation of the emergency generator system, from -

the time of a loss of site power until the generator system secures.

(***** CATEGORY b CONTINUED ON NEXT PAGE **44*)

'b

Pa_ _EE91gBgg_OE_E8g1611LQgglgd Page 6

.O QUESTION B.08 (0.50) ue or False:

The control blades cannot be operated in gang control except during hot startup approach to critical following a scram.

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l (444$4 ElJD OF CATEGORY b 46444) I l

l Page 7

,9t__QENg686_QPEB811Ng_Gb888CIES.19I190 1

i

. I DUESTION C.01 (3.00)

For each of the following parameters, state the upper limit during steady state operations, and explain the reasons fo: the limit. (1.P ea)

a. primary coolant pressure

b. pool temperature QUESTION C.02 (3.00)

What are the four maj or harards invol ved wi th beamport experiments?

OUESTION C.03 (2.00)

Technical Specifications lint two ma.ior negative reactivity coefficients whi ch can hal t the rapid power escalation following a positive step resetivity insertion. Identify the coefficients and state their values as listed in Technical Caecifications DOEST 10N C.04 (3.00).

The reactor chall be considered secure wnenever it contains insufficient fuel in the reactor core to establich criticality with all control rods removed. Describe three other conditions that W111 also meet the reactor secured criteria.

QUESTION C.OS (1.50)

Per Technical Specifications, what is the minimum shutdown margin requirement at the MURR7 t

I (4**** CATEGORY C CONTINUED ON NEXT PAGE 6**4*)

ct_jgEUtB96_OPEgeIJug_gueBSCIEBl@IICS J Page 8

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OUESTION C.06 (1.50)

Per Technical Specifications, cemplete the followings (.5 ea)

a. the max 2 mum rate of reactivity insertion for the four shim blades operating simultaneously shall not e:: c eed ________ d el t a k/sec.

b. the react.*.vity worth of each secured removable experiment shall be limiteo to ______._ delta k.

c. the regulating blade maximum rate of reactivity insertions shall be

________ delta k/sec.

1 (44444 END OF CATEGORY C 44***)

s a Dt _INSIBudgNIg_SUQ_CQUI69LS Page 9 QUESTION D.01 (2.00)

Describe how an uncompensated ionization chamber detects incident thermal neutrons, including in your answer any nuclear reactions that take place in the dutector.

OLIESTION D.02 (3.00)

At low power, adjusting the compensating voltage on a compensated ion chamber (CIC) will have a very noticeable effect on the output of the detector. However, as power level approaches full power, the effect on the CIC output of changing compensating voltage is almost neglioible. Explain this phenomenon.

QUESTION D.00 (1.00)

Why is the bridge ARMS placed in the upscale position prior to removing a control blade offset mechanism?

DUEST1ON D.04 (3.00)

What are the setpoints for the f ollow2 ng scrams? (.5 ee)

a. period.

b. primary coolant low pressure,

c. htqh power.

d. pool l evel .

e. pressuriner low level.

f. pressuri:er high pre ssur e.

)

DUESTION D.OS (2.00)

The reactor i s not allowed to be sterted up unless there is adequate j neutron flux l evel monitoring. Name the two ways which are mentioned in i Technical Spectfacetions by which this requirement can be satisfied.

1

(**464 CATEGORY D CONTINUED ON NEXT PAGE *64$6)

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Page 10

. Ec INSIEUt1ENTS_ANQ_GQNT8QLQ OUESTION D.06 (2.00)

What is the minimum nuclear instrumentation for a reactor startup? Include number of channels required.

DUESTION D.07 (1.00)

Explain why. during normal operating conditions, the reactor will scram if the Reactor Convectivo Loop Valves 546A and 546B are opened. (1.0)

OUESl 1014 D.08 (1.00)

Concerning the nuclear instrument intermediate range channels:

s. What does the Period Automatic Control Interlock Trip prevent? .(.5)

b. Flow is the Period Scram Trip reset? (.5) l I

4 l

1

(*4*** END OF CATEGORY D *****)

E.. . .- .AS F F. 7----------

Y AND EMER G..ENCY ------.YSS- T

. -E- -M- -S- Page il QUESTION E.01 (3.00)

The reactor is operating at 5 Mega':atts wi th a core inlet pressure of 65 p.,$ whf or some unenplained reason pressure slowly begins to increase to Describe all actions (including alarms) that will be taken by 115 pulg.

the pressuricer and safety sy?tems to control or mitigate this pressure increase. (Include set pol ni. a. )

OUESTION E.02 (2.00.5

a. Describe how a koottor Loop Low Pressure Scram initiated by signals from pressure transmitters PT944A or PT944B must be reset. (0.75)

b. Enplain why this type of lockout was installad. (0.75)

c. When can this type of scram be bypassed? 10.5)

OUESTION E.07 (1.00)

Which of the followinq component (s) can be supplied with air from the Emergency Eiac k u p 41 r . Lompr essor ? (Note: mor e than one answer may be correct.)

(1) Fool Loop Inolation Val ve 509 (2) heactor Loop Isolatica Valve 507(i (0) Containment E<u l l d a n o E:< h au s t I nol at i on Valve 16A (4) Emeroency Generator (5) Fretoht Door 101 Gasket DUESTION E.04 (3.OOs

a. From what two locations can the Fac112 t v Evacuation Alarm be menually initsated. (l.0)

h. Dnscribo four automatic actions which will rotult from a Fac111tv Evacuatton alarm. (2.0)

I (9**** CATEGORY E CONTINUED ON NEXT PAbL $*$$$)

Et_'_SBEEIY_8UD_EDEBgENGY_SYSIEUS Page 12 o

QUES 110N E.05 (2.00)

Which of the following conditions will result in a reactor scram?

(1) Source Range Monitor Channel 1 Inoperative (2) Low Pool Level (3) Thermal Column Door Open (4) High Off gas Activity '

(5) Low Reflector Differential Pressure (6) Low Pressurizer Level (7) Low Pool Flow DLIESTION E.06 (2.00)

What is the reason for having a scram associated with differential pressure across the reflector region? Consider both high and low delta P. Include the possible cause of the high and low delta P.

)

DUESTION E.07 (2.00)

The annunciator system is equipped to back-light windows in two colors other than white. State the other two colors, and what each of the THREE colors nie a n .

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l l

l l

(*4'444 END OF CATEGORY E ***4t)

4 EA__318NDSBD_@ND_EMEBGENCY_OPEB911NQ_ESggEDURES Page 13 QUESTION F.01 (3.00)

Per Technical Specification 2.2, "Limiting Safety System Settings",

complete the following: (.5 ea)

a. Safety System Settings during Mode 1 oper Ations:

Reactor Power 12a% Full Power (_____ MW) (max )

Primary Coolant Flow _____ gpm either loop (min)

Reactor Inlet Water Temperature _____

degrees F (max)

Primary Coolant Pressuri er Pressure _____

psi a (min)

b. Safety System Settings during Mode 2 operations:

Reactor Power 125% Full Power ( _____ MW) (max)

c. Safety System Settings during Mode 3 operations:

Reactor Power 125% Full Power ( _____ kW) (man)

OUESTION F.02 (1.50)

Technical Specification 3. 2, "Control Blade Operation", specifies how the shim blades shall be operated when power level is above 100 KW in order to prevent fluv t31 ting. Explain the method of operation as described 2m this Technical Specification.

OUESTION F.03 (2.00)

Per Technical Specifications. define an "eMperiment".

DUESTION >4 (2.50)

Assume that you are the licensed reactor operator on duty at MURR. A visiting profest.or from the University of Wisconsin asks if he may perform a startup. He currently holds a tentor operater license on the UW Madison Triga reactor. All personnel requirements of the Technical Specifications are met. Do you let him perform the startup under your supervision?

Enplain why or why not.

(***6* CATEGORY F CONTINUED ON NEX1 PAGE *****)

. E1__S16dDSBD_OND_EMEBgENgy_QEESSIJNQ_EBQGEgyBES Page 14 QUESTION F.05 (2.00)

True or False:

a. When increasing reactor power, the reactor power level shall be increasing on no greater than a 100 second period.

b. When performing a reactor startup, the stable period shall be no less than 30 seconds.

c. Prior to assuming automatic control for reactor operation, the period ss indicated by both IRM-2 and IRM-3 must indicate not less than 35 waconds,

d. When in automatic control for reactor operation, the reg blade must be utill:ed in such a manner to insure that it is less than 60% withdrawn when the desired power level is reached.

QUESTION F.06 (1.00)

Who can authorize a reactor startup following a scram where the cause has not been determined but all systems are found to be normal?

DUESTION F.07 (3.00)

Describe the three conditions that must be catisfied before the Reactor Short-form Pre-critical Checksheet can be used.

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(*6444 END OF CATEGORY F 44**4)

Os__BBDIBIION_CQUISQL_GUD_SOEEIY Page 15 QUESTION G.01 (1.00)

Which of the following radiation exposures would infl;'ct the greatest biological damage to inan t 1 Rem of GAMMA, 1 Rom of ALFMA. or 1 Rem of NEUTRON 7 Explain. ,

OUESTION G.02 (2.00)

One of the imitediate actions steps of SEP-4, "Site Area Emergency Procedure". is to send an operator to the west tower with a radiation monitor. List or describe 4 actions that this individual must perform.

OU'ESTION G.03 (2.50) .

A onmc,a source emits 8 R/hr at one foot. How long could a pt>rson work at a distance of 4 feet from the source without exceeding the quarterly whole body limit in 10 CFR 207 Show your work.

OUESTION G.04 (1.50).

A 23 year old individual has accumulated a lifetime occupational dose of 24 rem of whol e body exposure documented in accordance with 10 CFR 20 and has recelved no exposure during the present calendar quarter. How long may he work in a ' mren/hr area and not exceed any 10 CFR 20 limits, if he works an G hour day? Show your work.

1 l

OUESTION G.05 (1.50)

Fer 10 CrR 20. an inds>idual in a restricted area may be allowed to receive a wnole body dose in excess of the quarterly limit under certain conditions. Describe these three conditions. (1.b)

)

($$*** CATEGOR( G CONTINUED ON NEXT PAGE *6***)

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,,0t__B8018I19N_GQN1896_ONQ_@8 EELY Page 16 DUESTION G.06 (3.00)

Calculate the length of time it would take a person to reach their cuarterly whole body dose in each of the following fielda. Treat each case separately and assume that there is no previous done received for this quarter. (.75 ea)

e. 400 mr/hr gamma

b. 100 MRAD /hr fast neutron t

c. 300 MREM /hr beta

d. A +ield containing all of the above DUESTION G.07 (2.00)

Define the following per 10 CFR 20:

6. RADIATION AREA (1.0)

b. HIGH RADIATION AREA. (1,0)

DUESTION G.UO (1.50)

A fuel element is removed from the reactor and the radiation dose rate at 10 feet is 10 mr/hr beta-gamma. At what distance from the fuel el ement would you post a "Radiation Area" sign?

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(***** END OF CATZCORY G ***66)

(***4****** LND OF EXAMINATION **$4+4**e*)

i

82_ _ E BI O.CIELE S_9E _6 ESCIgB_ QE E BBIJ 96 Page 17 e

ANSWER A.01 (1.00)

K effective takes into account the non-leakage factors that K infinity ignores. UC infinity assumes no leakage.)

REFERENCE Gl asstone and Sesonske, sec 4.4 Training modulo 3. 1.3-2 ANSWER A.02 (2.25)

a. prompt neutrons are born directly from the fission process b, delaved neutrons are born from unstable fission daughters

c. thermal neutrons have energy levels in equilibrium with their environment (usually less than 1 ev)

REFERENCE Glasstone and Seconske, sec. 1.32 2.164 to 2.169 Training module 3, 1.5-1 to 1.5-2, S.1-2 to 5.1-4 ANSWER A.03 (1.50)

Pn Po t>;p (t/T) or T = t/(In P/Po) ( 75)

P= 10E3 watts Po=1 wctt t=600 seconds (.25) ,

l T= 600 sec/(In 10E3) = 600 / 9.2 = 65 seconds (+/- 1 sec) (.5)

REFERENCE Trainino module 3, 6.4-2 to 6.4-3 l

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(**tt* CATEGORY A CONTINUED ON NEXT FAGE *446*)

- - - - - - - -.-,-----n- w- - - , , , - ...n - , , - - - - - -

. 6t__EBINGl[66@,,QE_6E@QIQB_QEEB@IlgN Page 18 ANSWER A.04 (1.50) ,

cri /cr2 = (1-Kef f 2) / (1-Kef f 1) --> 75/150 = (1-Keff2) / (1-0.95) therefore Keff2=.975 (.75) rho =(Keff-1)/Keff ==> rho 1= .0526 and rho 2= .0256 and delta rho =+.02699 OR delta rho = In (Keff2/Keff1) = In (.975/.95) = +.026 OR delta rho = (Kef f 2 -Kef f 1) /Fef f 2*Kef f 1 = .02699 (0.75)

(all answers allowed a tolerance of +/- 0.001)

REFERENCE Glasstone and Sesonske, Sec. 5.14 Training module 3, 6.1-3 ANSWER A.05 (O.50) supercritical REFERENCE .

Glasstcoe and Seconste. sec 5.14 Training module 3, c.1-3 ANSWER A.06 (0.75) a REFERENCE Glatstone end Seconste. Sec. 2.196 to 2.172. 5.00 to 5.32. 5.46 to 5.47 Training module 3. 5.2-2 to 5.2-4, 6.2-1 to 6.2-4

(*646* CATECORY A CONTINUED ON NEXT PAGE 444/4)

..et__EB1UglEL55_gE_BEsgIgB_gEgBeligN Page 19/

. l ANSWER A.07 (1.S0)  !

Plutonium has a half life of 2.411 x 10E4 years. Using the formula N = No exp ( .693t/ halflife), after 30 years the production of alphas by the plutonium would be

-(30 yrs x .693/2.411 x 10E4 yrs) e = .9991 times its initial value, or the new source would be producing 1/.9991 =1.0009 timen more than the old source. Therefore the change in i count rate is about 0.1%. This is about 1 count per second. (Will accept a statement that the change in not noticeable as long as the proper calculations are performed.)

i REFERENCE t Glasstone and Sesencke. Sec. 2.4

~1 raining mooule 2. 10.3-1 to 10.3-2 Training module 2, 11.3-1 to 11.3-2 i

ANSWER A.OG (1.SO) l 239 235 4 Fu --? U + He (u.75) 94 92 2 9 4 12 1 De + H e -- > C + n (0.75) 4 2 6 O R EFEF; ENC E Glasstene and 5esor %k e. Sec. 2.71 to 2.72 Training module 2. 11.3-1 to 11.3-2

(*444* CATEGORY A CUNTINUED ON NEXT PAGE 49444)

1 1

. 1 Ot__EBIUGIELE3_9E_SE6CIgB_gEEB6I190 Page 20  !

ANSWER A.09 (3.00)

a. number of neutrons from all fissions number of neutrons produced by thermal neutron fi ssions

b. average number of neutrons produced directly f rom fission number of neutrons absorbed in fuel

c. number of thermal neutrons absorbed in fuel total number of thermal neutrons absorbed (1.0 ea)

REFERENCE Glasstone and Sesonske. Sec. 4.1 to 4.14 Training module 3, 2.1-4 to 2.1-5 ANSWER A.lO (1.50).

A = Ao e::p ( .693 t/halfitfe) (.5) helfltfe = (.693 t) / (In A/Ao) (.25) half 15+e = (.693

• 30) / (In 21/1.2) = 7.26 minutes (.75)

REFERENCE Trainino module 2. 10-4.1 to 10.4-3 i

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(*6t** END OF CATEGORY A 44449) l l

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..Et__ FEATURES OF FACILLIY_DE@lGij Page 21 ANSWER B.01 (1.50) ,

U-Al alloy (.75), 93.5% U-235 enrichment (.75)

REFERENCE Hazard Summary Report, sec 4.2 ANSWER Ei. 0 2 (1.00) manter sHttcn in the "test" position rod magnets are de-energtred (.5 ea)

REFERENCE Ha:ard Summary Report, 9.5 j ANSWER B.03 (2.00) l any f our 3 .5 eat flux trap .

beamports irradiation baskets pneumatic tubes thermal column REFERENCE Hazard Summory Report. 8.2, 8.3, 8.4 6.b. 0.6 AN9WER B.04 (3.00) any 6 & O.5 eat short period high power low pool level vont tank low level antiuiphon 1tno high level i od not in cohtect with rug n et regulating rod bottomed

. regulat)ng rod <= 10% withdrawn truck entry cpen i

(*644* CATEDORy' D CONTINUED ON NEXT F' AGE 44664)

61__EEBIYEES_DE_EGCILLIY_QEgl@U Page 22 REFERENC,E Training Manual, 11-65 to II-66 Ha:ard Summary Report, Fig 9-34 r ANSWER B.05 (2.00) ,

emergency lighting system reactor exhaust system reactor instrumentation air lock doors (.5 ea)

REFERENCE luchnical Specification 4.D ANSWER B.06 (2.50)

a. Constant pressure is maintained by automatically feeding in or bleeding out nitrogen gas. (.5) Water level is automatically maintained by pumping in or draining out water. (.5)

b. h1 pressuri er pressure (.5) lo pressuri er pressure (.5) lo pressuri:er level (.5)

REFERENCE ,

Training Manual, I-4e to I-48 ANSWER B.07 (2.50) after a time delay, the engine starts (.5) i alternator supplien the loedu continuously for 5 minutos after site power l 1s restored (1.0) generator syctem then f.ecures end reverts to ready standby mode ( 1. v >

l REFERENCE Training Manual. 111-0 to 111-9 i

ANSWLk D.08 (0.50)

False 1

i (4#444 CATEGORY B CONTINUED ON NEXT PAGL 4**6*)

)

~ . . _ __ __. . _ . - . _ . . _ _ _ . . -

1

, , Bt _ F_ E. A.IU._ R_ E..S_

. _OF _ F A_ C IL._ I.T Y _ D_ E S_

_ _ _I G_ N page '3 4

REFERENClE SOP I.4.3.D and E e

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.: n.... uno or c,ueoony e .....,

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Ct__GEUEBGL_DE6BSIIN@_CdSBBCIEB15I105 Page 24 ANSWER C.01 (3.00)

a. 110 psig (.5) Assures that the system design pressure of 125 psig is not exceeded (1.0)

6. 120 degrees F (.5) Assures the adequate cooling of pool components during all modes of operation (1.0)

REFERENCE Technical Specification 3.4 ANSWER C.02 (3.00)

1. changes in reactor reactivity due to beamport ac ti vi ti es (such as draining or flooding a beamport)

2. exposure of personnel to rad 2ation (as a result of movements of botelding or inadequate shieldtng)

3. release of radioactive gases (such as Ar-41) which are produced in the beamport

4. production of explosive or toxic materials in the beamport.

(.75 ea)

REFERENCE '

SOf VIII.4.1.A ArJ5WER C.O! (2.00)

Void coefficient ( . S) -2.0 : 10E-3 delta P/ percent void (.5) temperature coefficient ( . 5) -6.0 x 10E-5 delta k/ degree F (.5)

FEFERENCE Technical Specificetion 3.1 (4o44* C"TEGORY C COtJT INUED OtJ NfXT PAGE *****)

. .. Gz__DEUgB96_OEEB811Ug_GUSBSGIEBl@IIGS Page 25' ANSWER C.04 (3.00) any 3 9 1.0 eat

a. All shim rods are f ully inserted.

b. One of the following conditions exists:

1. The "Master Control" switch is in the "off" position with the key locked in the key box or in the custody of a licensed operator.

2. A licensed operator is present in the Control Room and the dummy load control rod test connectors are installed,

c. No work is ir, progress involving transferring fuel in or out of the Core. p

d. No work is an progress involving the control rods or control rod drives with the exception of installing or removing dummy load control rod test connectors.

L. The reactor pressure vessel cover is secured in position and no work is an progrunn ch the pressure vessel or its supports.

REFERENCE icchnical Specification 1.20 ANSWER C.05 (1.50) i r.? reactor shall be subcritical by a margin of at least .02 e (.75), with any one uhtm blade fully withdrawn (.75).

REFERENCE Technicel Speci f i cat i on 3.1.e 1

fin 5WEh C.06 (1.50)

a. Z. . V :- 10E-4 (.5 ea)

b. .000

c. 2. 5 ;- 10E-4 i

l REFERENCE Trchnical Specifications 3.1.a. d, g. b, c, e 1

khhkkh 4 )

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..Dt__lBEIBUdEUIg_68Q_GOdlB96@ Page 26 ANSWER D.01 (2.00)

Neutrons interact with the boron in the detector according to the following formula:

10 1 11 6 7 4 B+ n-> ( B) -> Li + He + electrons 5 0 5 3 2 (1.0)

The ions are accelerated in the electric field of the detector, causing additional ionizations in the gas. When the ions reach the electrodes, o pulse is generated. (1.0)

REFERENCE Glasstone and Sesonske. Sec. 2.64 Training Manual, II-4 to II-7 ANSWER D.02 (3.00)

At low power, gamma current i s relatively large compared to the neutron current in the detector. (.5) Thus, changing compensating voltage will have a laroe effect on the totel current output of the detector since this etfects only the gamma portion of the detector current. (1.0)

At high power. g A mc.a current is relatively small compared to the neutron current. (.5) Changing the compensating voltage again changes only the camma portion of the detector current, but since the percentage is so small. the effect is almost not noticeable. (1.0)

REFERENCE I

Training Manual. Il-7 to II-9 ANSWER D.03 (l.00)

Prevent a buildinc. inolation clarm while the blade ir being handled cut of '

water.

hEFEFeENCt1 SDP 11.3.2.4 i

(et4e* CATEGOht D CONTINULD ON NEXT PAGE se et)

. Dt__JN5IByd5UI5_AUD_GONIBQLS Page 27

= ,

a ANSWER D.04 (3.00)  ;

a. O seconds

b. 63 psig

c. 120%

d. 23 feet

e. 13-14 inches below centerline J. 78 ostg REFERENCE l

50P 1, Table IV ANSWER D.05 (2.00)

1. Source range indicates at least 1 cps and wide range indicates a power level greater than 1 watt. (1.0)  ;

2. Source range indicates at least 2 cps and is verified to be responding to neutrons just prior to startup. (1.0)

REFERENCE Tech Spec 3.4.e

• l ANSWER D.06 (2.00) 1 (.25) Source Range (.25) 2 (.25) Intermediate Range (.25) 2 (.25) Power Range (.25) 1 (.25) Wide Range (.25) >

REFERENCE SOP I.4.3.H ,

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ANGWER D.07 (1.00) o Will cauce water to bypass the core resulting in low differential pressure.

(0.5) Differential pressure swi tch 929 s i g n.n l will cause trip unit to reach flow scram setpoint. (0.5)

(49944 CATEGORY D CONTINUEC ON NEXT PAGE ****:)

i 4 9t__1U516Ut!EUIS 6UD_GOUIB065 Page 28 REFERENCE Tras ning Planual , p. I-26 f4NGW'i.R D.08 (1.00)

a. Prevents the reculating control rod from being operated in the automati modo (0.5)

6. reset using the reset switch 40.5)

REFE'5NCE 1 raining Pla n u al , p. 11-70, 11-32. 11-52.

1 (l64** F.ND OF CATEGOR'Y D 4446*)

• Et__SOEEIX_8SD_EdESQEUCY_DYSIEdQ Page 29 i

ANSWEF: E.01 (3.00)

When pressuri:er pressure sexceeds 105% of 70 psi valve 545 will open to bleed off nitrogen gas to the offgas system. (0.75) If 'ronsure e:teneds 110% of 70 psi pressuri:er high pressure alarm will sound in the control room. (0.75) A reactor scram occurs at 115% of 70 pai.

(0.75) 4t 100 psig the excess pressure will be vented through safety relief valvo 537 to the offges system. (0.75)

REFERENCE Training Manual, I-46 to I-47 ArJ5WE R E.02 (2.00)

a. Master Control Switch (1S1) has been turned to "test" and then back to "on". (0.75)

b. With the present antisiphon system the core stays pressuri:ed and the 944s can remake. causing cycling of the pumps and valvet if not fcr the circuit loclout. (0.75)

c. Can be bypassed in 50 kilowatt mode. (0.5) l REFERENCE l Training Manuel, 1-34, 11-75 l

ANSWER E.03 (1.00)

(3) and (5)

FtEFCRENCE Trasning Manual. IV-5 (t**** CATEGORY E CONTINUED ON NEXT FAGE 444tt>

O 6x__@@E61Y_99Q 6Mg69EUCY_SYS160S Page 30 1

ANSWER E.04 (3.00)

a. Reactor Control Room (0.5)

Lobby Control Center (0.5) i

b. any 4 of che following & .5 ea

, Reactor scrams t i Containment ventilation system isolation doors close i Containment exhaust isolation valvos close Facility horn sounds Flathing red Itght exterior to the containment personnel airlock j door is energized [

i-REFERENCE FEP-1, p. 1.

j ANbWER E.05 (2.00) l (2). (5). (6), (7)

} (4 required - 0.5 pte each - Will subtract 0.5 ptc. f or each incorrect i

anrwer given up to total value of question) i REFERENCE l SDP I-IS t o I-18 i i

{ ANSWER E.06 (2.00) f j  :

l hi delta F - poseable core blockage (.75) I lo delta P - indicates reduced flow (.75) }

both st>rve as a beckup to pool coolant low flow scram (.5) [

4 f

l RErLRENCE k

, s Training Menuel. II-o7. 11-70 i

Technical Specification 3.3  !

i  !

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. ANCWER E.07 (2.00) [

Red (.25) - scram condition (.5? (

Dlue (.25) - rod run-in concation (.5)  :

Wh?.te - simol e al arm condition (.5) l e

i i j (*te** CATEGCTW E CONTINUED ON NEXT PAGE *****;

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Et__@BEEly_@Up_gbgBQgbGy_Sy$lgd$ Page 31 REFERENLt Training Manual, II-67 9

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• Ex _SI8ND8BD_8ND_EMEB950GY_9EE68IIND_EB9GEDUBES Page 32 ANSWER F.01 (3.00)

a. 10 MW (0.5 ea) i 1625 gpm 155 degrees F l 75 psia b; 5 MW

. 50 kW REFERENCE Technical Specifications 2.2.a. 2.2.0. 2.2.c ANSWER F.02 (1.50)

The maximum distance between the hiohest and lowest shim blade (.75) chall not exceed one inch. (.75)

REFERENCE Technical Specification 3.2.b 1

ANSWLR F.03 (2.00) j Any device or material which is exposed to significant radiation from the reacter end is not part of the reactor. (1.0)

Any oper ati on designed to measur e or monitor reactor characteristics or '

parameters. (1.0) 1

) REFEhENCE I

Technical Specification 1.5 l

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(4*444 CATEGORY F CONTINUED ON NEXT PAGF $4444) ,

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• i. _SI9000Bp_000_(dE60EEgy_QEEEGIlNQ_CRQCEQUBES Paoc 33 ANSWER F.04 (2.50)

W :uld not allow him to perform the ctortup. (.75) 10 CFR 55 allows non-licensed persons to manipulate the controls of a reactor under supervision only if it is part of the non-licensed individuals training program. The professor is not in training. (1.75)

(Will allow full credit for allowing startup af candidate states the assumption that the professor meetu the requirements of being in training as defined at MUhR. Credit deducted if allowance i s made for the Triga license.)

(Will alen .w r c e p t P::pl a i n at i on that the RO cannot r>upervise reactivity manipulations) b F.F E FE NC E 10 CF N SS . I .-

ANSWER F.05 (2.00)

a. false

b. true C. true

d. f al t.e (.5 ea)

REFERENCE 50P ll.1.4.C.1. 11.1.1.1. II.1.3.A.1, II.1.3.B.3 ANSWER F . O i, (1.00)

The heactor Manaaer ( . 5) or his authortred delegate. (.b)

REFERENCE SOF' l.4.J.4

(***** CATEGDRY F CUNTINUED ON NE+T F' AGE *****)

e

• Et__D19dDbSp_60p_EL1 ESC 4EUg,f,.,OEg6911bg_PBOGEDL)BES Page 34 ANSWER F.07 (3.00)

1. The systems and instrumentation other than those referred to in the short form pre-startup checksheet have been in continuous operation since the completion of the last comprehensive startup checksheet ( . 5) and the routine systems check has revealed no abnormalities. (.5)

2. A full power or low power pre-startco checksheet has been completed within eight hours prior to the time a short form checksheet is to be used

(.5) or the reactor has been operating at some time within the previous eight hours, and a shutdown checksheet has not been completed within this period. (.5)

3. fJa anomalv with regerd to any systems not covered by the shcrt form checksheet han occurred since complet1on of the 1ast comprehenstve startup

c. t i t c I C e t t (1.0)

PEFEREtJCE EDP 1.4.F.1 t46*** E.ND Of C A T L C.L % i F t44%6)

• 91__ BOD 16IION_G0blB96_6BD_SOEEIY Page 35 W

ANSWER G.01 (1.00)

All the same. (.25) Rem is a unit of biological damage regardless ne the source of radiation. (.75)

REFERENCE 10 CFR 20 ,

Training module 5. 2.1-2 ANSWER G . O .' (2.00)

1. Veri f y radiation bact: ground at staci' monitoi'

2. verify control room readings

3. mark initial needle position on analog displav with the time

4. verify flow rate through monitor to 7 +/- 1 SCFM REFERENCE SEF-4 Immediate action Ettp 5 AN5WER G.03 (2.50) 2 2 D1 r (hl) = D2 x (R2) CO.63 8 F/hr " 1 sqft = D2 r 16 sqft CO.4]

D2 = .5 R/hr CO.11 stav time = total allowed dose / dose rate CO.63

= 1.25 R / .5 R/hr CO 43 CO.3 for limit]

= 2.5 hr CO.13 REFERENCE 10 CFR 20.101 Training module 5. 0. 2-2 t o 0. 2-3 1

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• G. RAD 19110N_GQNI[igL,dND_h6EGlY Page 36 AN5WER G.04 (1.50) mav receive 1.25 REM this quarter nince he has no quarterly enposure

(.5)

Max. Dose = Doso Rate X Time 1.25 Rem = 0.003 Rem /hr X 0 hr/dav A No. of Days No. of Days = 52.1 days (1.0)

REFERENCE 10 CFR 20.101 ANSWER G.05 (1.SO)

(1) He does not enceed 3 rem per quarter ((.5)

(2) Hgs radiation historv to known and recorded on the proper iorm (NRC Form 4) (.5)

(3) The dose received when added to his radiation history dces not eaceed 5(N-10) rem where N v the person's age at his last birthday (.5)

FEFERENCE 10 EFR 20.101 ANSWER G.06 (3.00)

e. 1:50 MREM /400 mhEM = 0.12b hr (DF=1)

b. 1250 MREM /(100 MRAD OF of 10) = 1. 25 h t-

c. 1250 MREM /30u mF:EM = 4.1/ hr

d. 1250 MREM /(400 MREM + 1000 MREM + 300 MREM) = .74 hr FEFERENCE 10 CFR 20.101 Trcining module 5 2.1-2, '.~. 1 .' to . 1-3

(***** CaTEGCRt G CONTItP 'ED ON NEAT FW3E *****'

Ot RnDinTIgs_CggIRQ6_6UQ_S@EEli Page 37 ey ANSWER G.07 (2.00)

a. Radia tion Area: Any accessible area in which a major, portion of the body could receive in one hour a done in excess of 5 mil 11 rems. or in any 5 consecutive days a dose in excess of 100 millirems (1.0).

b. High Radiation Area: Any accessible area in which a major portion of the body could receive in one hour a dose in excess of 100 milltrems (1.0).

REFERENCE 10 CFR 20.202 4

ANSWER G.OS (1.50)

R1 D1442 = R2 D2442 (0.25)

Radiation Area- 5 mrom/hr OR 100 mrem /5 days assuming O hr days => 2.5 mrem /hr most limiting (0.5)

D2642 = 10 (100)/2.5 D2 = 20 f t (0.75)

REFERENCE 10 CFR 20.202 Training module 5, 3.2-2 to 3.2-3 1

(4*64 END OF CATEGORY G s****)

(***446**** END OF EXAMINATION 444444****)