Text

Exam Rept 50-267/OL 89-02 During Wk of 890710.Exam Results: Three of Four Limited Senior Reactor Operator Applicants Passed Exam.Answer Key Encl
	ML20246A706
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/09/1989
From:	Eaton R, Pellet J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	;
Shared Package
ML20246A687	List: ML20246A684; ML20246A706; ML20246A721;
References
	50-267-OL-89-02, 50-267-OL-89-2, NUDOCS 8908230118
	Download: ML20246A706 (65)
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APPENDIX, .

U.S. NUCLEAR REGULATORY COMMISSION REGION IV ,

Operator Licensing Examination Report: 50-267/0L 89-02 Docket No.: 50-267 Operating License No.: DPR-34 Licensee: Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Facility: Fort St..Vrain. Nuclear Generating Station Examinations at: Fort St. Vrain Nuclear Generating Station

' Chief Examiner: ? ? i9 R. B. Eaton, Examiner Date Operator Licensing Branch, NRR

' Approved by: A e % 9 89 JL L. Pellet, Chief Date '

- Operator Licensing Section Division of Peactor Safety Summary NRC Administered Examinations Conducted during Week of July 10, 1989 (Report 50-267/0L 89-02)

NRC administered examinations to four Limited Senior Reactor Operator (LSR0) applicants. Three LSR0s passed all portions of their examinations and have been issued the appropriate license. One LSR0 f ailed the written examination.

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1. Persons Examined LSR0 Total License Examinations: Pass - 3 3 Fail - 1 1

2. Examiner R. B. Eaton, Chief Examiner

3. Examination Report Performance results for individual examinees are not included in this report as it will be.placed in the NRC Public Document Room and these results are not subject to public disclosure,

a. Examination Review' Comment and Resolution In general, editorial comments or changes made during the examination, or subsequent grading reviews are not addressed by this resolution section. This section reflects resolution of substantive comments made by FSV staff.- The only coments addressed in this section are those which were not accepted for incorporation into the examination or answer key. Those comments accepted are incorporated into the mas.ter examination key, which is included in this report. Comments may be paraphrased for brevity. The full text of the comments is attached.

N.05 Reject the question and the answer on the basis that the special senior licensed operator (SSLO) is not responsible for the system lineup or. operation.

Response: Comment is rejected. The facility lesson and system material provide for more than the rudimentary knowledge required to answer this question and it is appropriate that the SSLO have a minimum working knowledge of the few important systems that interface with the fuel handling -

equipment.

Two other comments were submitted by the staff, which were fully incorporated in the written examination answer key.

b. Site Visit Summary (1) At the end of the written examination administration, the facility licensee training staff was provided a copy of.the examination and answer key for the purpose of commenting on the examination content validity. The licensee was informed that written examination grading would not be started until licensee review comments were received in the headquarters office.

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'(2) 'At the conclusion of the site visit, an exit meeting was held with a member of the plant staff. The folicwing items were ,

communicated _to the facility licensee representative as comments, observations, suggestions, or deficiencies:

(a) The applicants exhibited good knowledge of the refueling equipment and its applications. Their familiarity with the instrumentation, supporting systems, and administrative requirements is especially noteworthy.

(b). An area of generic weakness was found in the use of procedures, probably due to the absence of procedures for reference during the operating portion of the examinations.

c. Master Examination and Answer Key

-A master copy of the FSV license examination and answer key are attached. The facility licensee comments, which have been accepted, are incorporated into the answer key,

d. Facility Examination Review Comments The facility licensee comments regarding the written examinations are attached. Those comments not incorporated into the answer key have been addressed in the resolution section of this report.

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U. S. NUCLEAR-REGULATORY-COMMISSION .

SENIOR REACTOR OPERATOR LICENSE EXAMINATION ,y REGION 4 j FACILITY: FT. ST. Vrain )

i REACTOR TYPE: HTGR-GA [

-DATE ADMINISTERED: .89/07/10 CANDIDATE:

INSTRUCTIONS'TO CANDIDATE:

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 et least 70% in each category.- Examination papers will befpicked'up six (6) hours after the examination starts.

% OF LCATEGORY .% OF CANDIDATE'S CATEGORY VALUE TOTAL ' SCORE VALUE CATEGORY 12.00 16.90 ___________ ________ M. REACTOR'AND FUEL CHARACTERISTICS 17.00 23.94 ___________ ________

N. EQUIPMENT, INSTRUMENTATION AND.

DESIGN DESCRIPTION 13.00 18.31 ___________ ________ 0. ' PROCEDURES AND LIMITATIONS 15.00 21.13 ___________ ________ P. EMERGENCY SYSTEMS AND SAFETY DEVICES 14.00 19.72 ___________ ________ Q. HEALTH PHYSICS AND PADIATION PROTECTION

~71.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor rceived aid.

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Ms; REs0 TOR AND FUEL CHARACTERISTICS-4 w._.-'___.________________________

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GUESTION M.01 (1.00) ;

Circle the one answer that correctly list +, the three stages of'an ' induced' i I

nuclear reaction'.

A. Reactants,: Products, Scattering B. Compound Noeleus, Products, Scattering C. Setttering, Reactants, Compound Nucleus, D. Reactants, Compound Nucleus, Products l

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! QUESTION M.02 (2.00) -l 1

l Select the letter.in column B that best describes the item in column A and >

place.it in the space provided before the number.

COLUMN A COLUMN B

1. IONIZATION A. A process by which a gamma interacts with.an orbital

2. EXCITATION electron giving up all'its energy causing ejection of

__ 3. COMPTON SCATTERING- the electron from the stom

. __ 4. PAIR ANNIHILATION B. A process by which a medium energy gamma interacts with

.an orbital electron causing ejection of the electron and a reduced energy gamma that continues on to cause other interactions C. A process by which the removal of one or more orbital: electrons-is caused by electrostatic force interaction between the charged particles and the orbital electron (s)

D. A process by which orbits 1 electron energy state is increased without ejection of the electron from the atom E. A process by which a positron combines with a free electron leading to the emission of two .51 Mev photons

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QUESTION- M.03 - ( 1. 0 0 )'

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There are- five major, fissionable nuclides .in the core of 'which three are ? also

.ifissile.nuclides.-l Circle the answer below which contains the three nuclides

that are both fissionable and' fissile.

.A'. . Uranium 233.,-Uranium 235, Plutonium 239- .

iD. -UraniumN233,-Uranium 235,.-Uranium 238

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C.: : Uranium'235, Uranium'238, . Plutonium 239 i 1

D.- Uranium 235r Plutonium 239,' Thorium 232 7

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JOUESTION- M'. 0 4 : (1100f l

., Cir c1e lthe . answer which correctly corresponds.to the,fcilowing definition.'

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- Atoms :with' th'e same number ' of ' neuttons el but J with - a : dif f erent' number of

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-~ A . Isotope .

B. ' I s o t o n e ... I C.: . Isobar .S :

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"M.;; REACTOR"ANDiFUELJCHARACTERISTICS' Page .~ 8 f

00ESTION H.05. (1.00)

' Circle.the answer.which-applies to fuel roning in the FSV reactor core.

A. ; Fuel zoning simulates an equilibrium core to ensure all regions are at equilibrium.at the'end'of-6-year cycle.'

B. Equilibrium is-achieved by adjusting the fue1' conversion ratio in each

fuel zone using a mixture of Uranium, Plutonium and Thorium, C.. FSV reactor has a fuel conversion ratio of 0 6 which is achieved by Juniform fuel.:oning.

D .- Region 1-fuel coning is different from all other fuel regions to account

.for-the regulating rod.

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...N M.,.REACTORLAND FUELDCHARACTERISTICS' -

P89e 9 1-b j p -1 l GUESTION L ' N .06';. ;(1.00)

< - Circle the answer which best describes the Reserve-Shutdown System (RSD)..

/ .A.- The:RSD is'the alternate reactor shutdown

system.if'the. rods' fail'to

- provide adequate shutdown margin when fully inserted.-

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l- , D.- The'RSD-is comprised of 37 hoppers-which insert automatically;or manually

. in the<following configurations; s'. group of-7 specific regionst-'30-L l, specific regionse or. alli 27 regiotes at 'once, through control.' room l i: discretion.

I L' . C. The RSDLis the main control' poison used in the FSV reactor and is I independent of the' control rod systen..

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The.RSD is independent of the rod contro1~ system, capable of shutting down -!

D. _

the reactor, and initiated through control room discretion in the following configurations; .a group of 7' specific regions, 30 specific regions, or all 37 regions.at once.

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t fD'UESTION - M . 0 7. , (1.00).'

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Circle'the.' statement below which, correctly, describes t.he.Use of graphite'.in L the~FSV reactor.

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A. ' Graphite is the structural material in the fuel compacts and acts as a

moderator.and-reflector for neutrons.

B. .The graphite-in the reactor is-priarily in the' active core.'

'C.' ITheLreflector.is the' layer of graphite-immediately surrounding the core which slows down the neutrons so they can be more readily used.

D. . As-~s moderator' 3raphi.te is ecivally effective as water i.n thermalizing fission-neutrons.

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M, H., ? REACTOR ANDL. FUEL CHARACTERISTICS .Page 11

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i GUESTION( M;08- . (4iO0i ForLthe activities described below on a suberitical reactor, place ~an A in-the s

space provided if.the affect on the core is an increase in reactivityr:a.B if Lthe affect isca-decrease in reactivity or a C if both_ increase ^an'd decrease Japply.

__1.- '

Remove's control rod

.__ 2. . Remove spent f_ vel

.__ 3. Install new fuel' .

__'4.. Remove. reflector

__'5. Vacuum'RSD material from core

__6.- Install la' control rod

__ 7. Install reflector

__ B. . Remove burnable poison

.__ 9. Insert RSD material

__ 10. Install startup source

_ _ ' 11. Install'. burnable poison-a,_-12.' Remove depleted startop source

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EQUIPMENT,2 INSTRUMENTATION AND DESIGN

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-DESCRIPTION l a

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['~DdESTION N.01 (1 00). !

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'Circlelthe' answer'below;which is a function-~.that'is NOT provided by.the .

-fReactor Isolation Valve-(RIV).. l q

A.! Provide a', seal to maintain: helium integrity for the. Fuel Storage.Well.-

o B.- ' Provide a platform for.'the Fuel Handlins' Machine. !

C. Provide-shielding'to plant personnel.

'D.

Provide a means to level.the Auxiliary Transfer Cask, 1

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,(b DESCRIPTION-

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.UESTION.

Q .N.02' ~(3.00) i sIndicat'e the; desired sequence for; connecting t.he below listed electrical and; pneumatic. items of. a;..RIV' by placing their associated number in order.soing c

from'leftito right-in;the spaces provided.

.1'. 'Sealfsource hose

. ;2. RIV f power supply cable .

' 3. : V'acuum: hose t

'4._ bdmbilical. cable oridumper plu.s 5 '. - Backfill hose j

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c.c _ DESCRIPTION.= '

QUESTION N,03 -(1.00l)

~Cdele'the statement-belov which correctly describes.the' seal (s) associated-with the Reactor Isolation Valve-(RIV). ,

A.- There are~3' pneumatic ~ seals.which-maintain-the sir / air or helium / helium.

interface integrity between the RIV and the PCRV?or the Tuel. Storage Wells.

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Ei.1 : There are. interlocks hssociated with the seals to insure that the correct differential pressure and differentia 1: atmosphere are maintained when the;

'FHM or.t'he ATC is installed on the RIV.

Ca;-There is an' inflatable.. seal on the bottom of the RIV to. seal it to.the-structure or equipment and a-mechanical seal (*0' ring);to-seal the. top of the'RIV'to the FHLotLthe ATC.

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D. The inflatable sealJon the top'end bottom of the RIV automatically..

inflates:on loss of.; power to the RIV or ATC.

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N.. E0dIPMENT,I:4STRUMENTATION AND DESIGN Page 15

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GUESTION N.04 (1.00) l Circle the answer below which is NOT en internal RIV interlock.

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A. Dif f sr erit i al Pressure D. Differential Atnosphere C.. Loss of Power l D. RIV to FHM Cask Valve

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N. . : .h00ESTION.'

-N.05 '

'(3.00)

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LSelect the. correct letter . f rom b.* ; items labeled on the simplified system

%q .., disgram ?and, place 'them in the space .provided in 't'ront' of the numbered item

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FUEC HANDLINGJPURGE SYSTEM (SYSTEM 13) l fi

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.l SEE ATTACHMENT N.05 ON THE NEXT PAGE l 1.. 375.PSIG HELIUM PRESSURE REGULATING VALVE

.a_ 2..: 35;PSIG HELIUM PRESSURE REGULATING VALVE

.__ 3. 13 PSIG HELIUM: PRESSURE REGULATING VA'.VE 7 P _4. ' g..PSIG HELIUM PRESSURE REGULATING VALVE

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DESCRIPTION > .<

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i JDOESTION? lN.06 , (2500) !

Place. theile (ter corresp'onding to'the correct' component description in the j

'Spdce':provided in.: front of each numbered ' FHM coniponent, i

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FHM COMPONENT COMPONENT DESCRIPTION !

p?qq;_ji'.1 ARH' DRIVE AZIMUTH SYSTEM ( _ ) A. Used'to position fuel:

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element. monitoring 4e " o .

, system Used.to house and guide? H 39 T2.. . HOIST DRIVE SYSTEM (Z) B..

' c:6 fi the=R>dritve system . , !

Wyp, during-vertical travel Egl3sfEARM DRIVE INDEX SYSTEM (h) C. Used.to monitor fuel ,

%gp' ' - elements

, L i D. Used to align dowels on-

, m :g__J4 1 TELESCOPING MAST' TUBE border elements i E. Used to position the i telescoping tubes I L F. Used to position the=

L index arm angularly I

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' QUESTION. ' N . 07: '(2.00)--

Selectfthe lett'er corresponding-to the correct motive force / power used by the numbered. subassemblies and place it in the space provided-in front-of esen-number *'(choices may'be used more than once or not at all)-

__.1.:2 DRIVE .

A. Pneumatic B. Mechenical-

__ 2. _.; DRIVE-C. Electrical D. Hydeaulic

.__ 3..R DRIVE

__ 4. h DRIVE r- .-

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.. Ho;; EQUIPMENT, INSTRitMENTATION AND DESIGN Page'Ji9-DESCRIPTION-4 it, f I N,08 (1 00)

$.[005STION-v.

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J /.; Circle the choice (s) below which correctly'in'dicates ALL the crane and it";ibolt-down conditions. when the FHM is on the New Fuel: Loading Port.

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W;2C ' CRANE CONDITION BOLT 00W'N CONDITION-i.- ,

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, Z d ' A, Attached'or Unattached Bolted' ,

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.D.- Attached or Unattached. Unbolted l

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ti QUESTION iNiO9c :(1.00)

-Whatiis?'the normal working. pressure for,-the PCRV and internals?- Cirele the g*'l correct answer.

. A.:. TBS 7psis :

. 'B '. - B45psig

.C.: '704psis ,

'D. 688psis-

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i LWkat:.is: the: source of makeup water. for the Reactor- Plant : Cooling Water . System ;l J(System 146)? : Circle' the correct answer listed- below.' -

-: A ., ' F e e r, snd< Condensate- ,

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E;.1 Circulatirrs Water - I

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C iFire-Water. '

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ll.GUESTION' -.N.11 .-

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'.The"LowJTemperature bsorber in the Helium Purification System is-designed-to' -

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. remov'e '.i.he ' f o11owin3 ;;impur ities . - Circle >the' correct answer.-

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.A.; Tritium, CO2, Methaner.LKryPton ,

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1 CO2i Methane , Kr ypton , :l B .4 .

z. Xenon -

Ce , Methine, Krypton,' Xenon, Tritium

-D c .Kr ypto'n t :- Xenon , JTr i tium e .-CO2 i

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30.;EPROCEDURES'AND. LIMITATIONS Page.23-e

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5.90E5TI'ON 0.01 - ( 2. 00) -

- Place a;checkmark'in therspace provided.in' front of the. Technical

Specification LCOs which must be. met prior'to increasing Primary Coolant:

pressure to.100 psiai .

U . __A..'Both safety and rupture discs operable.

7 __B. All primary and secondary closures, operable.

. _ _ C l. ~ Differential outlet and inlet water temperature'<20 degrees--F. '

Hold.down plates'in place.

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__E.'.All penetration' interspace pressures > primary.c'oolant pressure.

._;F i . Penetration primary seal leak rate acceptable.

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L 90UESTION i :0.02 ;( 1. 0 0 F A

j What$ group / department.'is responsibility for: major equipment-movement, planning? :l

. Circle)the correct answer.

A. .

Reacl tor Engineering.

B.. . Reisetor .Mainten.ance

. ' C , ~. . Planning'and SEhe'dulins LD.;' Systems Engineering. 1 i

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0203 '(1.00)

. 10UESTIONJ Who is responsible 1forfrefueling activities snd? spent-fuel and shippin's.:

' Circle the correct ~ answer.. ,

A. Nuclear.' Production.Divisionf(NPD)

% - B. i Nuclear Engineering Division (NED) p !.C.' Nuclear.. Licensing-and Resource Management Division (NLR)

D..JReact'orLEngineerin3-(RE)

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'GUESTION'

. 0.04. - ( 1. 0 0 ) - j r.c !

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..There J are. !fourLclassifications of emergencies at FSV. Indicate-their order of.. ;

iincreasing severity bylplacin3 1 (least severe) to 4'(most severe) in thei ;

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-space provi'deda j

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__-Site Area Emergency -l

__iAlertL 1

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_. ; Gener al: Emer gency.. l

__ Unusual Event. ,

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0.:,: Page 27 a

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QUESTION: 0.05 (1.00) -

,ITo whom does Nuclear Production Administrative Procedure 9-(NPAP-9)e. Radiation ..

Protection Plan, apply? Circle the correct answer.

=A.1 General. Pub 1'ic's: Station Personnels.Non-station Personnel-

.a :

B. Station Personnel, Non-station. Personnel, Visitors. ';

-: \: . .

I C.jNon-station:Personnelt- Visitorsr.; General Public- i e .D.L isit'orst General.Public, Station' Personnel' j

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Page'28

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- DUESTION- 0d6 (1.00)

JFrom.~.the list.below,' circle.the. item.that has the two (2) fuel.handJing j l: ..related systems.; identified in EP-H-2 as most likely sources of potential-Jaakage of' radioactive gas.

~' '

.1 .. l Af. System'13, .. System'14

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rEO.' System 14,. System 15-

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0+ System 13r-System 16:

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0., PRdCEDURES AND LIMITATIONS Page 29'

'GUESTION 0.07' (1.00)

Orion each . entry'r _s minimum of __ authorized individuals shall be present within the Fuel 9torage Building (FSB).. Circle the correct answer fron, the items-' listed.below.-

A. 2 B, 3 C. 4 D.- 5

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r.' i i GUESTION: 10.08, (0.00)

Specification LCO 4.7'.0 Fuel. Storage Facility, Limiting. Conditions for

' Operation -

.During storage of' irradiated fuel;in the Fuel Storage-Facility, the following L"conditibns shall be met:

s .

s a) Both: cooling water coils must be operating and their outlet coolinstwater

-temperatures 1150 degrees F'or less, for any storage well containing ~

" irradiated fuel. .

b ) , :If only one cooling' water.coi'l is operating'on a storage well's irradiated-

fue'1: storage'.is' permissible if the outlet cooling water temperature i's:150 1d eg r e e s .. o r less,<and th'e. ventilation system is capable of supplying a totalof

129000 CFM'to:.the Fuel-Storage Facility.

Lc) .The-fuel storage wells containing irradiated fuel.are maintained at approximately. atmospheric pressure.

S Assume-the. conditions-listed below are met. Place an 'X" in the space Lprovided in front of.the condition (s) if the LCO is met.

.__.1. .a) or b)..or c)

__-2. a)'or'b) and.c)

__+ 3. a) and b) or c) 2_f4..a)-and'b).and c) .

__i5. a)iand'c) 6'. b)'and c)

-(GUESTION DELETED FROM EXAMINATION AFTER ADMINISTRATION) y

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GUESTION. .0.09 (2.00)

The' Operator's console is divided into six~(6); bays. In the< space provided

--in front of'the'four bay descriptions place the letter 'that corresponds to,the

~

i correct bay-number.

_ _ if '. .. Manua.1 Position Control Panel A. 1000 bay B. 2000 bay

_.-2. ; Haster'Conteel Panel -C.- 3000. bay D. 4000. bay ,

.. 3. _ Helium Seal-Source Monitor E. 5000 bay ,

F. 6000 bay I 4. - Automatic Control' Panel !

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J. LGUESTION - 0.10 (1.00);

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.A complete;startup. procedure must be used afterewhichiofLthe fo110 i wing'. .;

.y ' conditions-listed: below? -Circle.theJcorrect' answer..

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each' shutdown, all.-repairs

y. [ B .~ vall.repairsi all modifications y

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r. 8 b .. , ,

d D.- .each shutdown',Lall modifications- a q

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. :GUESTION. 0 11. (1.00)- ,

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During.defueling;.+. operations -it. becomes necessary to: at;t er the sequence.-

The- :j lYo110winsLaction Aust'be taken. 1

'A.. Authorization'-J.is required from'NPD

~

i B .- An NCR'is^ initiated.and approved by. gas Msterial Review. Board (MRB) p; .C.. -A Procedure-Deviation Report is; required.

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10. : 'NED prepares and submits;a' Change Notice.(CN) for NPD .!

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q LOUESTION ~ -

0.12- -<1.00)

E-

'Use;of~the clamp bypass sw' itch. allows the operator:to (circle the answer.Nhich '

fcorrectly completes this statement).

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-d :A. cor(tinue' operat'i on' if the f ault is understood and found acceptable.

Eh ys'ift h from/ automatic to manual without'a long procedure to follow.-

'C o . ' verify the associated problems without shutting'down.

D* reverse the action'which.1 caused the' clamp. -

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g CPk; ENERGEt4CY(SYSTEMS AND SAFETY DEVICES,: Page_35" i ., ,.;

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- ~-QUESTION : P . 01: - ('1.00)

Circle (the statement :below :which is required under Specification: LCO 4 5.1-LReactor 'Duilding,. Liniiting-1 Condition f or Operation, to. handle irradiated fuel within the Reactor-Building.

< ;A. ' Personnel access to theLbuilding is controlled.

g

B.: The reactor. average 1 helium ses-inlet' temperature is-165 degrees.F'.or less.'- -

C. ;All; primary,and; secondary penetration closures and. hold-down plates are in-

< p1' ace and operable pe? Specification LCO 4.2.9.

{..

D -. - The' reactor'is maintained in a.-reactor shutdown or~refuelingsshutdown

condition and-theireactivity of the core is monitored continuously-by at' a -- -least two neutron flux monitors capable of continuously indicating the

neutron flux"' level within the core.

' Nu

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j; P.~] EMERGENCY'. SYSTEMS AND SAFETY DEVICES Fage'36. ,

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GUESTION. .P.02- (1.00) .i

?

l cThelicircle' Lthe correct : answer listed below) is responsible for obtaining,the- j

~

, Jdata and-performing the shutdown. reactivity caleviations.for anticipated

-l reactivity ~' manipulations'to verify: adequate shutdown margin is: maintained.

A . >-: _. : Operations-Department n

B. Nuclear. Engineering Division ,

C.i Reactor Engineering Department. 4 0... Nuclear Production Division j

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36

+ _

5

GUESTION' P.03; (2 00)

, 1

.: Select the appropriate letterj.from the Limit column and place it in the; space j

.provided in-front'.of:the' alarm received if that liiittis exceeded.' '

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. ALARM: LIMIT

'1 J . _ _ u l . ; M o t i o n. L i m i t f- f o r'- R a d i a l A. + or - 20 lbs.

Head: T r an s l at i'on. B. 450 lbs. H

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C. R or.0 not in Z,R.r0

. " ;_; 2. Tube Fail' interlock zone-D. . 6* ,

"/__~; 3,: Weight L Limit . E .' S e p a r a t i o n ' a b o v e ' t h e '- N separation region,

.l l __;4.l Incorrect Machine Position. F.- Analog. and digital readings disagree l b

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<>:With. respect thelZr-R, and 0 interlocks, place theicorrect letter.(s) i n .~ t h e

.JInterl.ock Limitatio'ns' column in the space provided.in front of the numberedi

.FHMLPosition column.'-(Thel 1etters may:be used more than once or not at all.)

. E; FHM POSITION INTERLOCK LIMITATION'

-9.

,___.1. REACTOR "

A. No.Z' motion'below 173.9'~.with cask valve closed ~

.___.2. FUEL. STORAGE WELL B. R must be less than 25.~0' when 2.is-above 282 3"

___.3.' .

LOADING PORT C. R.and 0 zerced between.173.9' and

,.. 476.4'

'D. R and 0 nivst be zeroed when I is -

between 173.9'.and'282 3* ~

E. Cask valve cannot be closed with Z below 173.9' F. Cask valve must be opened prior:to opening the RIV

0. O must be rotated toL+60 degrees.to enable Z movement below 476.4*

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(GUETION P.05 "(1.00)

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E0fithe four. interlocks listed'belowi circle the. answer!that is:an interlock associated'sith!L(l') ~ the grapple. and-(2) cari NOT'be bypursed.

D _' A;; . DodeliPin Ens'agement' B .1 Zeto Weight

t. . Load Port' Position D Y. ~ P r o b e EU p .- n z

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The F eN_ ,~riah;,f.'.
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(completeithis? sentence.by circling the-correct' answer below).,
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( f
.y GUESTION Q.02 (1~.00)
Circle the item.below which presents the greatest ha

:ard to a radiation worker A if' accidentally ingested.
.w s; 'A.fAlpha
. :s B. Beta O'S C. Gamme >
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Place the correct Quality Factor in the space provided in front of each item
. . listed below'.
__'A. Alpha
__ B. Beta
__ C. Gamma.., a.
__ D. !!e u t r o rs l's'-
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Wa , 0.05 ;(1 00)-
l> p;m; 7 Sq ,Mc. .~An.,fexposure to' ionizing. radiation'of BremJin.the last quarter is within the
.fdderali-liniits-if received!(circle the correct, answer).
' 2 A'.- r Accidentally
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A. ~one shift
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' [ QUESTION ?G.07.
-(3.00)
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Pl'aceJan "X' in the. space provided'in front of.each person / position-listedzwho i
'a, Radiation.' Work 1 Permit'you-are. requesting dur.ing your-
!is' required to' sign xshif t.c- -
__;A.. HP' supervisor'for your' shift
__

B. 5hift Supervi'sor for~your shift
. _ C.'1Yourself-w
_ _..; D . Security Supervisor for your shift
_ _- E . - Anyone'whofuses'the. permit
_f F..~SSLO-foryour ~ shift
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.h. IB _
Q. .. HEdLTH PHYSICS AND' RADI ATION PROTECTION: 'Page 51-h
OUESTIONt G.08 (3.00)
In the space provided in front of the lettered itenis place a '1 or 2 or both 1 and 2'as they apply to that item.
____ A. RO-2 1. Ion Chamber
____ B. Nuclear Instrumentation 2. Proportional Counter
____'C. R0-5 i
____.D. FNR-4
____.E. :* Gas Filled
____ F. Low sensitivity, high range j ,,
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'Cifele the answer-below'which>would most;likely. prevent /minimite the spread'of' 1 -
' CONTAMINATION in;an area that is already contaminat'ed.
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'Ai Ensur. e -..the., st ea '- 2 s well ventil at ed . .
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'D'.j Assume all materials in area are contaminated.' ] ;
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