ML20235S216

Exam Rept 50-186/OL-89-01 on 890118-19.Exam Results:Reactor Operator Candidate Passed Exam

ML20235S216
Person / Time
Site:	University of Missouri-Columbia
Issue date:	02/21/1989
From:	Hare E, Jordan M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20235S215	List: ML20235S213 ML20235S216
References
50-186-OL-89-01, 50-186-OL-89-1, NUDOCS 8903070008
Download: ML20235S216 (100)

Text

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i U.S. NUCLEAR REGULATORY COMMISSION REGION III j l

Report No. 50-186/0L-89-01 I Docket No. 50-186 License No. R-103 Licensee: University of Missouri Research Park Columbia, Mo 65201 Facility Name: University of Missouri at Columbia Research Reactor Examination' Administered At: University of Missouri at Columbia Research Reactor Examination Conducted: January 18-19, 1989 Chief Examiner: Elizabeth A. Hare Oro @l)

Dat'e 1 Approved By: M. J. Jordan, ? Z 2/

Date Examination Summary Examination administered on January 18-19, 1989 (Report No. 50-186/0L-89-01).

Examination was administered to one reactor operator candidate.

Results: The candidate passed.

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.1 REPORT DETAILS

1. Examiner Elizabeth A. Hare

2. Exit Meeting On January 19, 1988 at the conclusion of the examination, a meeting was held to discuss generic findings made during the course of the exami.tati on. The following personnel attended the meeting:

Facility Representative W. Mayer, Operating Engineer NRC Representative Elizabeth A. Hare The following observations were discussed:

a. General condition of the facility was clean, except for the trackway for the thennal column which contained numerous cigarette butts.

The licensee took immediate corrective action by cleaning up the area.

b. The examiner felt REP-1, " Failure to Scram or Rod Run-In," immediate action step 1. Scram the reactor, was incomplete and should be elaborated upon. The examiner recommended listing the alternative ways to scram the reactor, and place them in order of ease and certainty.

c. Examiner noticed a discrepancy between the Secondary Cooling System P & ID found in the Training Manual and the Hazard Summary Report (HSR). The HSR contained an updated diagram. The licensee will look into this problem.

3. Examination Review Question A.08b FACILITY COMMENT:

The Facility comment is directed to the answer to question b. The answer j given, that the buildup of Pu-239 and Pu-241, causes beta-fraction to decrease due to different beta-fractions, may be true for low enriched cores, but is not true for highly enriched cores such as MURR (93.5%

enriched).

For a typical new fuel element (B0L) at MURR, the isotope distribution of fissile material is 772.43 grams U-235 and 56.81 grams U-238. When this fuel is retired (EOL), the isotopic distribution is 585.36 grams U-235, 56.81 grams U-238, 29.69 grams U-236, and less than .2 grams total Pu.  !

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2 For this reason, there is negligible fissions from Pu at the end of core life and the beta-fractions for MURR highly enriched fuel remains virtually constant over core life. We recommend that the answer "no change in the beta-fraction over core life for MURR fuel" be accepted as an answer.

REFERENCE ORIGIN CODE OUTPUT for past spent fuel shipment (0RNL-4628)--(attached)

NRC Response: Agree with comment. The answer key will be changed to "no change in the beta-fraction over core life for MURR fuel.

Question C.03 FACILITY COMMENT:

This is a valid question based on material supplied to the examiner.

Part one of the answer may not be provided by the operator candidate because our training program does not stress this mode of operation.

This mode of operation has not been used in over fifteen years. The candidate's inability to provide the proper answer regarding natural convection cooling is more a reflection of a weakness in our training, than a weakness in the candidate's knowledge. We recommend that the point vulue for this part of the answer be reduced or eliminated since it would penalize the candidate for what is a weakness in our training program.

NRC Response: Comment noted. It is recommended that the licensee's training material be updated to reflect actual operation at MURR. It is not made clear whether this mode of operation can still be used under certain conditions. The answer key will remain unchanged.

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U. S. NUCLEAR RE00LATORY COMMISSION 1 l

, REACTOR OPERATOR L'ICENSE_ EXAMINATION REGION 3-FACILITY: MDiYt_Qf _diannurl _______

REACTOR TYPE: IESI_____________________

i DATE ADMINISTERED: QS20141R_________________

IN118URIl0NS_IQ_G88Q1081El

' -Vas' separate paper for-the answers. Write answers on one side only.

Staple question sheet on top of the a n s w e'r sheets. Points for each quastion are indicated in parentheses after the question. The passing

<.grado' requires at least 70% in each' category. Examination papers will bo picked up six (6) hours after the examination starts.

% OF CATEGORY  % OF CANDIDATE'S CATEGORY

__V8LUE_ _IDIaL ___SQQBE___ _V8LUE__ ______________C6IEQQBl_____________

________ A. PRINCIPLES OF REACTOR OPERATION J112tZE__ _12thi ___________

_15tDD__ _lizR2 ___________ ________ B. FEATURES OF' FACILITY DESIGN

,_latDD__ _12tRD ___________

________ C. . GENERAL,0PERATING CHARACTERISTICS

_1stEQ__ _1st22 ___________ ________ D. INSTRUMENTS AND CONTROLS

_1stDQ__ _1222Q ___________ ________ E. SAFETY AND EMERGENCY SYSTEMS

_15tDD__ _lataa ___________ ________ F. STANDARD AND EMERGENCY OPERATING PROCEDURES

_1sthD__ _idtag

___________ ________ G. RADIATION CONTROL AND SAFETY

_1DDtZ__ _.._________ ________% TOTALS FINAL GRADE A11 work done on this examination is my own. I have neither given

'nor received aid.

Candidate's Signature L______________ _ __

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. s NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS l

i turing the administration of this examination the following rules apply:

b. Chosting on the examination means an automatic denial of your application end could result in more severe penalties.

N. Rootroom trips are to be limited and only one candidate at a time may locve. You must avoid all contacts with anyone outside the examination rocm to avoid even the appearance or possibility of cheating.

D. Uso black ink or dark pencil only to facilitate legible reproductions.

O. Print your name in the blank provided on the cover sheet of the oxsmination.

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

B. Uso only the paper provided for answers.

P. Print your name in the upper right-hand corner of the first page of each cection of the answer sheet.

O. Consecutively number each answer sheet, write "End of Category __" as Appropriate, start each category on a new page, write only on one side of the paper, and write "L9st Page" on the last answer sheet. l

0. Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

12. Uso abbreviations only if they are commonly used in facility literature.

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Portial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the examiner only.

17. 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 assistance in completing the examination. This must be done after the examination has boon completed.

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.c I8. Whaniyou' complete your examination, you shall:

~o. Assemble your examination as follows:

(1) Exam questions.on top.

(2) . Exam aids - figures, tables, etc.

(3) AnswerLpages inokuding figures which are.partlof 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 questions.

d. Leave the examination area, as defined by the examiner, If after

leaving, you.are found-in this area while the examination is still in progress, your license may be denied or revoked.

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9, et__EBINCIELE1_QE_BE8CIQB_QEEBAIIQN Page 4

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-A.01-

-QUESTION (1.50)

L. Matching - Indicate for each item in Column A (a thru c).the item in Column B'(1 thru 4) that is associated with it. -(1.5)

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' Column A ~ Column B a.. Most fast fissions occur 1. . U235 in this n.aterial 2. U-238

3. Boron

b. Most thermal' fissions 4. Water occur in this material

c. Highest absorption cross section for thermal neutron l

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

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'ei__EBINGIELE1_QE_BE8010B_QEEB611DN QUESTION 'A.02 (1.00)

Fill.'in the blanks with1 INCREASES, DECREASES, or REMAINS CONSTANT. (1.0)

Tho equilibrium xenon concentration ____(1)____ with increasing power level while_the equilibruim samarium concentration ____(2)____ with increasing pcwar level.

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. QUESTION 'A.03- '(3.00)

~ Xonon is the major fission product poison in your reactor.

c. ' '

i-  : How is--it produced? (Include pertinent half-life.) - ( 1. 0 ) .

b.- How'is it removed? (Include pertinent half-life.3 (1.0):

c. Why does xenon reactiv'ity peak after a trip from high power?

(1.0)

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QUESTION A.04 (1.25) tWhat'effect'does e-moderator temperature increase have on control rod' worth? (0.5) Explain your answer C.75).

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A.05 .(2.003'

( 1. 0 ) ,-

c.-  ; Define reactor period.

6.. . Explain'the: term prompt critical. (1. 0 ) -

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8t__EBINGIELES_QE_BE8GIQB_DEEB811DN- Page 9 QUESTION A.06 (1.00)

Rosctor power-is 100-watts and increasing on a 30 second period.. How long will it take for the reactor power to reach 10 kilowatts? (Neglect heating cffects) Show your' work. (1.0) q 4

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g /. .h-Page<10-181__EBINCIELEf_QE_BE8CIQB_QEEBeI1ON QUESTION A.07 (2.00)

'o. . Explain'what-the difference is between k-infinite and k-effective.

(1.0)-

'b. K-effective of a reactor is given as 1.0795 delta k/k.

What k-excess does the reactor have?- (0,5).

-c.. What reactivity is associated with this k-effective? (0.5) 1 i

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1 Page 11 l.et__EBINGIELER_QE_BESGIQB_QEEB8IIQN fQUESTION A.08. (2.00).

c. Explain what.is; meant by the term." delayed neutron frsetton."

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~ b. Does the value of the delayed neutron fraction change over-core Itfe?

Explain.. (1.0)-

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(***** END OF CATEGORY A *****)

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I um Page 13 Et__EE8IUBEi_DE_E8CILIIX_ DESIGN QUESTION B.01 ~C3.00)

What.three features in the reactor' cooling system are designated to protect

.tha core f rom a loss. of coolant accident? (3.0)

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4 Pege.14 Ri__EE8IMBES_DE_E6CILIIX_ DESIGN

' QUESTION B.02 (3.50)

> Indicate the. component which corresponds to each letter designation'-(A through 6) on the attached-cross-sectional. view of the reactor core. (3. 5).

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Page 15-A __EE8IUBER_DE_E8CILIII_ DESIGN

. QUESTION' B.03- '(2.50).

.Concorning the_. pressurizer system:'

0. Briefly' describe'the automatic pressure andl level control of.the pressurizer. (1.0) .

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b. What' scram functions are initiated from the pressurizer system?.

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1 Page 16 Et__EE8IUBES_QE_E8CILIII_ DESIGN QUESTION B.04 (2.00)

Tho water, steam, gas and air pipes are brought in through a 4.6 foot deep cctor-filled trap. Answer the following questions with regards to the wetor trap.

a. What areas of the plant does the water trap seal? (1.0)

b. What happens in the event pressure exceeds 2.0 psi? (1.0) h m n W. < #44 71uomb p

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'E,.__EE8IMBES_QE_E8CILIIX_ DESIGN Poge'17

,, QUESTION B.05' '(1.00)-

' Explain the response of the backup iso 1'ation doors to the following l

.oonditions- .l

o. Failure of-normal power supply (0.5) .i b.- Loss of compressed air supply (0.5) i l

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Page 18 Et__EE8IUBE1_QE_E8CILIIX_DE11AN

' QUESTION B.06 (2.00)

Fosility Emergency Procedure, FEP-2 lists five events which result f rom a Rocctor Isolation alarm. List four of these. (2.0) r

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-lRt__EE8IUBE1_QE_E8CILIIY_DE11GN Page 19 l

QUESTION B.07 -(1.00)

.Spcoors'are set between the pressure vessel and reflector.= What are the Ltwo reasons for having the spacers installed? (1.0) q I

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C.01-MQUESTION ( 1. 0 0 ) .

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-Stato the two reasons'for maintaining water chemistry control in'the l p'riocry coolant' system. (1.0)

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'Page 22 lCt__GENEB6L_DEEBBIING_Cd686CIEB11I101 QUESTION C.02 (3.00)

Tho reactor,shall be considered secure whenever it contains insufficient fual in:theIreactor core to establish criticality with all control rods renoved. State three of the five conditions that- will also meet the rosctor secured criteria? (3.0) l l

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, i P c.g e 23 lGr__GENEB8L_QEEB8IING_GH888CIEB11IIGS l1

.. QUESTION .C.03 (2.00)

Dscoribe'three methods of normal reactor loop cooling system. operation.

Include any dif f erences in maj or equipment used and any applicable system

' flow rates and maximum allowable power levels for each method. (2.0) o

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Page 24-

'Gi__DENEBeL_DEEB6IIND_QB8869IEB11IIQ1 QUESTION C.04' (2.00)

Givo the normal-operating range for each of the following parameters (include units). ( 2. 0 )-

c. Pressiur ize r Pressure

b'.. Pool' Outlet Temperature (Hot Leg)

Ho. Reactor Inlet Coolant Temperature

d. Pool Level i

i Page 25 lCt__9ENEB6L_DEEB8IIN9_GB888GIEB111101 ~

! QUESTION C.05' -(1.00)

Whet:two' conditions, when satisfied, will bypass the rod withdrawal prohibit? (1.0) l

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Page 26-Gi__GENEB8L_DEEB8IINQ_CB888GIEBISIIGS-

!OUESTION C.06 (2.00)

c. Describe the criteria used in establishing-the flowrate for the Pool

. Loop Coolant System. (1.0) y b. Why'must the Pool Loop Cooling System remain in operation for a minimum of five minutes after a normal reactor shutdown. -(0.5)

c. What is the-purpose of th Pool Holdup Tank T504? (0.5)

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.Gi _GENEB6L_QEEB6IING_Gif888CIEB11IIGS i

! QUESTION C.07- (3.00)

What ere the four major hazards involved with beamport experiments?

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(***** END OF CATEGORY C *****)

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Page 29 Di__INSIBWHENI1_6HQ_G9NIBQL1

-QUESTION' D. 01' (3.00)-

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Stcto thc reasons for,the'following-Rod-In' Protection Logic for:-

1.- Low' Pool Level .(1.0) 2.- Vent;Tenk Low Level- (1.0).

f 3 '. . Antisiphon Line High. Level (1.0)_

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Page 30 i: QUESTION D.02 .(1.00).

.Why is the. bridge' ARMS placed in the upscale position prior to moving.a .

control blade offset mechanism? ( 1. 0 ) .

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'Dt__INSIBudENIS_8ND_DDNIBDLS.

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. QUESTION D.03 (3.00)

Indicate what type of nucleer detector is utilized by each of the following nuoloar instrumentation channels, and describe how-the effect of gamma rays-10 prevented from causing an erroncous indication of neutron flux.in each

%ype.

e- Channel 1 Source Range Monitor (1.0)

b. Channels 2 and 3 Intermediate Range Monitors (1.0)

c. Channels 5 and 6 Power Range Monitors (1.03- j l

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\ QUESTION 0.04 (2.00).

Dcocribe-four: conditions.that must be met prior,to automatic' operation of

=

.the+ regulating. rod. -(2.0)

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Pege 33 Dt__INSIBudENIS_8ND_QQUIBQLS QUESTION D.05 (1.00)

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

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'Di__INSIBudENI1_880_GQNIBQL1

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..UESTION Q D .' 0'6 (1'00)

Concerning the nuclear-instrument range channels:

'c. -What does the Period Automatic Control Interlock Trip prevent? '(0.5)

'b.

How is.the Period Scram: Trip reset? C0.5) l

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

.: s D4._lINRIBut!ENI1_880_GQNIBQL1 Page..35

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.I l QUESTION 0.07 ,(2.00)

'. Indicate the primary purpose of each of the following activity monitors and

.dcocribe its. respective sample location in relation to: major. system ocaponents within the applicable system:

a. Fission Product-Monitor (1.0) l - b '. -Secondary L.oop Monitor .' ( 1. 0 )

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! QUESTION- D.08 (1.50)

Mctch the appropriate response condition (1 through 3) with the correct bcck light color (a through d). (1.5) 1.- Screm s.- Red q 2.- . Rod run-in b. Yellow-3.- Alarm c. White

d. Blue

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

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Page 38

Ei__18EEII_8HQ_EUEBGENQ1_111IEUA

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-QUESTION' E.01 (2.00)

D00eribe.and Explain how the safety system scram logic works. ( 2. 0) .

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.3 Pege 39 3a.__18EEIY_aND_EMEBSENGI_111IEd1 '

i QUESTION- E.02 .(2.00)

Wh;t'cre the four major loads that th6 emergency generator supplies? ( 2. 0 ) - l l

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Pege.40 Et__feEEIX_8ND_EMEBGENGX_SYSIEd1 QUESTION. E.03' ( 1.' 5 0 )

Which'of the following conditions will result in1an automatic rod run-in?

(1.53 (1)- High Power

~(2) Low Pressurizer Pressure (3)' Short Period' (4) Rod Not in Contact with Magnet (5) Anti-Siphon System Pressure High (6) Thermal Column Door Open

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Page 41 lei __S8EEII_6ND_EMEBEENC1_SISIEb1 QUESTION ~ E.04 (1.00)

Which of the following components can be supplied with air f' rom:the-

' Enorgency Backup Air Compressor?- .(1.0)

( 1') , Pool Loop ~ Isolation Valve 509

' (2) ' Reactor Loop Isolation Valve 507A (3) Containment Building Exhaust Valve 16A (4)- Emergency Generator (5) Freight Door 101 Gasket l'

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Page 42

!Ei__18EEII_8NQ_EUEBEENC1_111IEUR QUESTION E.05 (2.003-Whct is the basis for having a scram associated with differential pressure coroco the reflector region? Ccnsider both high and low delta P. (2.0)'

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EA__S6EEII_8HD_EdEBGENQ1_111IEd1 Page 43

' QUESTION E.06 (1.50)

c. Describe two conditions or_ signals which will cause automatic start of the emergency generator. (1.0)

b. Explain why the emergency generator continues to run for five minutes after site power has been restored. (0.5)

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~ Ez__18EEIY_8HD_EMEBGENCY_LYSIEd1 Page 44

. QUESTION E.07 (2.00)

o. Describe how a Reactor Loop Low Pressure Scram initiated by signals from pressure transmitters PT9444A or PT944B must be reset. .C.75)

b. Explain why this' type of lockout was installed. (.75)

c. When can this type of scram be bypassed? (0. 5 ).

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LQUESTION E.08- (2.00),

13 Which'of the following conditions.will result in a' reactor'screm?

( 2.0)

(1) Source Rar.ge Monitor Channel 1 Inoperative x (2) Low Pool Level-(3) Pool Low Hi Temperature .

(4). High Off-ges-Activity (5) IRM Channel 2 Inoperative

'(6) Core Low Differential Pressure (7) Low Pool Flow

(***** END OF CATEGORY E *****)

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p. . ::

-Ei__SI6ND8BD_6ND_EdEBGENGXiDEEB8IINE_EBQCEQ2BES' Page 47 QU'ESTION F.01 (1.50).

. Match the tag colors (1:-thru 4) with the appropriate designation (a thru c).

(1.5) 1

'c. ' Danger-to personnel 1. Green

b.. Danger to equipment 2. Yellow 3.-

c.. . Supplemental information concerning Red an operating procedure 4. White 1

l.

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

? ^', .. .

a 4

Page 48 Ei__1I ANQ 880_8NQ_Et!EBG ENCY_QE E BeIING_EB Q G E QUB E1

. QUESTION F.02 (1.50)

Maintenance'was performed on the Nuclear Instrumentation detector. A recponse check is required to be performed prior to commencing a reactor

- Otcrtup.

c.. What two types of scurces can be used to perform the response check? (1.0)

~b. Where-is the successful response check noted. (0.5) 1

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

l..

y Page 49 (Ea__SIANDeBD_8ND_EdEEDENGX_QEEB8IINS_EBQGEDUBES QUESTION. F.03 (1.00)

'Anawor'the'following questions with regards to REP-20,'"High Activity Lovols in the Primary Cooling System."

c. The'second subsequent action is a precautionary reduction of flow.

What is the reason for this action? (0.5)

b. What should be/done to determine the source of radioactivityprior to an operator. entering an area containing primary coolant? (0.5) l

)

l l

i

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

E. L

c. .y.

Page 50.

Ei__II8NQ 880_8H D _ E tlE B E E NG X _ Q E E B 8IIN G _ E B Q G E Q U B E R

.~

! QUESTION' F'04 . -(2.00)

During a reactor.startup, you as'the reactor operator detect a stuck drive-

.cochenism. . What'are the'four immediate actions? -

(2.0)

L i

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

_-______________-__---__-____----Q

e .

(, '

Page'51 e EiL_SI8ND8BD_8ND_EdEBGENGX_DEEB8IING_EBDCEDUBES  !

3

,; QUESTION F.05 (3.00)

Dc cribe the three conditions that must be satisfied before the--Reactor

=Short-form Pre-critical Checksheet con be used. (3.0) 1 1

it i

1 i

(***** CATEGORY F CONTINUED ON NEXT PAGE *****)  :

l .f- ,

6

- Ei__SI6NQ8BD_eND_Et1EBEENQX_QEEB611bu_EEQQEQWBgg Page 52 QUESTION F.06 (1.00) c.

Who has the operating authority over all experiments performed within the reactor containment or which may effect reactor operation? (0.5)

.b. The insertion and removal of experiments in the center test hole position will be done with the reactor in what condition? (0.5)

I

~

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

+

Page 53 Et__SIeNDeBD_eND_EdEBGENCliDEEB8IIND_ESQGEDUBES' l-QUESTION F.07 (2.00)

,When starting the secondary cooling system, what limitations are placed on

-the pumpanwhen at 10 Mw. operations and Why? (2.0) 9 l

i

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

, ): '

Page 54 Et__SI6NDeBQ_6HQ_EdEBGENCY_QEEB6IING_EBQQEDVBES-l-

l IQdESTION F.08 (1.00)

' FILL IN THE BLANK with eegards to SOP II.1, " Routine Reactor Operation":-

l-c.- .Vithdrew'the four control blades in gang, stopping'to take a set of -

otartup nuclear data at ________ inch increments. (0.5)

b. When the blades have reached a position within ________ ir.ches of the estimated critical position, discontinue pulling in gang and take a set' of'staitup nuclear' data.- (0.5)

H i

I l

l l

l

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

.j c

.A Page.55 Et__SI8NQ8BD_8HD_EUEBGENGY_DEEB811NG_E80GEDMBES

{ QUESTION F.09 (1.00)

Per-SOP V, " Pool Cooling System",-what two methods of. lowering pool- level

'cen be used?  :(1.0)

'I t;

l i

l l

l l

l-(***** CATEGORY F CONTINUED ON NEXT PAGE *****)

r ,

e Page 56

. Et__1I8NQ8BD_8ND_EMEBGENGY_QEEB8IING_EBQGEDVBES QUESTION F.10 (1.00).

Who can perform a hot startup? (Include any limitations pieced on-that Lporcon)- (1.0) 1 i

i I

l i

l- i l

i l

l l

l i

I

(***** END OF CATEGORY F *****)

7-, .. .

pc g.

$ 1',' { a v;mi

,91 _88DIeIIDN CONIBQLieND 16EEIX.

Page.57-L il > 's 6

J

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

l:- - c,c ...

Page 58-i91__B6DI6IION_CONIBQL 6ND_18EEIX-1 1

QOESTION G.01 (1.50)

Stato the three methods used t'o remove radioactive waste in the form of dry cotive weste.from-the liquid waste retention system. .(1.5) l l

l l'

l

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

4 Page 59

[fi__B6018IION_GQNIBQL_8HD_18EEIX

{ QUESTION G.02 (2.00) s . .- Wh'at are the quarterly.. dose limits for en individual in a restricted area? I*

' b. What'is the dose' limit for.an individual under the. age of 187 (0.5) 1

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

(

l X

St__BeDI8IIDN_GDNIBDL_8ND_18EEIX- Page 60 1

li LQUESTION 'G.03.. .(2.50)

Define.or explain the following:

'o.. Dose: .CO.5)

b: . 1 Contamination (0.5)

<c. Red (0.5)

Dead Time (Os5)

..d.. (0.5)

W o .- - Half'Value Thickness

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

)

Page 61 A __B6016IIQN_QQNIBQL_8ND_18EEIX QUESTION G.04 (1.00)

Determine the exposure rate at a distance of two feet from a point source (1,0) containing 5 curies of cobalt 60.

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

a

.yh. -:^

v . <:

3 Page 62 Ai__B8DI8IION_GQNIBQL6ND_18EEIX QUEST' ION. .G.05 (1.00)

I' What is meant by.the~ term ALARA7 (1.0),

L.

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

9' 1 f I

Page 63-

' fri__B8DI8IIQN_GQNIBQL_8NQ_18EEIX.

QUESTION' G'.06 (1.00)

'If the' radiological half-life of Cesium-137 is 30.2 years and the

' biological. half-life is 70 days, what is the effective hal'f-life?

-(1.0)

31 i

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

R

, 1 Page 64- f AA__B8018IION_CONIBQL_6ND_18EEIY ~ 1 QUESTION . G .' 0 7 '(2.00)

M0tch type of radiation (1 thru 4) with the-proper penetrating power.(a-

~

thru d) (2.0)

1. Gamma a. Stopped by thin sheet.of paper

'2. Bets b. Stopped by thin sheet of metal 3.- Alpha c. Best shielded by' light material

4. . Neutron d. Best shielded by dense material l

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

'M iGr__B6D16Il0N_QQNIBQL_6HD_18EEII- Page 65

-QUESTION _ G.08 (1.00)

Explain why iodine-131 is the' limiting isotope in many accident analyses.~

(1.0)

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

F; >.

1  ; 4 --

Page 66-ini_iB8DieIION_GDNIBQL_8HD_18EEIX (QUESTION-G.09 (1.00)

Lio,t: three people, by' title, who must s ign and 'date ' the radiation work (1.0)-

parait.

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

c

.c E c _B6018I19N_GQNIBQL_8HQ_18EEIX- Page 67

~QUE'STION'

' G.10 (1.50),

,Liot three-types of personal monitoring devices. (1.5) t 1

(***** END OF CA1E60RY G *****)

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

m. '

Pcg2 1 of : 5

- DOIG_ESEEI

.BE8CIQB_IBEDBY_EQBduLOS:

p .p et /T P = P 10  ;

I E th P = ---------10 -------------- sbr = 26.06/T 3.12 x 10 fissions /sec ,

1 2 1 eff ,

-(B L th P " ~~ * ~~~~~~

p ,

y 1 + v th' 2 2 1 + (B L }

th K- 1 l P =e

-(B Lf2) A =.----- ,l f K' final

-[N3[1 eff 3 / lI- s AP = In -------

p=e g initial i

EbI---p 71 T =

C =C (1-Keff2) 1 (1-Keffi) 2 Ap  ;

i 1 C 1* J

_fie*1__

,. ___ . v - --

.1-K- C initial ,

l l -5 1 Af 1 op 2

6L 2 + AL th 2

a = - -- + ..-- - B (--f - -----)

f at p at at at off ~0 0 K =EP pP th fn P =P ---------

1 0O eff off El i

l l

1 l

l l

l i

Pcga.2.of.S'

- DOIO_SUEEI

'0- ,

I, - IBEBdQQYNed1CE_OND_ELUIQ_dEC60 NICE EQBduLOS:

lO = A Ah ,

2 w LAT:

> g._______________________-

-1 in R2 /R 1 .In R3 /R2

- + -------- +

0=UA (AT )* .

K K K.

2- 3 G=mc p' (AT) 4 0 = cc & A R Q- Q (h y , __Lg__=hout)real y . _l0. __out =

Q in (h

in -hg g) ideal W- PV PV22 actual 1 1

. _________ ____ . ____ q W T T supplied 1 2-4

'E = pAV pAV 3 g g

=pAv 222 3

& = KA J AP p- 5nc " Q E

= AT ( i n ') - AT (out)

---

G = -f th-AT 9 m 8.8x10 AT (in)  !

i in (-------->

1 AT (out)  !

1 l

L 2 kAAT Gr .

T -T = --. 0 = -----

CI D* Ax '.-

.4k A AT total Q = gy--- gp-- 3y a b n

___ + ___ + , , , + ___

K K K a b n ,

i i

l

- Page 3 of 5 DOIO_SBEEI p

CENIBIEUGOL_Eude_ LOWS:

N-g sg md g Hg m[

g

=

P

__3

_ _ . _ _ ____ = __

(N ) H (N P N

2 "2 2 2 2 2 BOD 10Il0N_GUQ_CHEd1SIBX_EQBdRLOS:

-R/hr = 6CE/d I =1 0 e CV g g =C 22

'G = Dilutten_ Bate I= 1 0 Ib 10 O*

Volume

~

A=A e A = AN O

GQUVEBS1RNS:

1 gm/cm = 62.4 lbm/ft Density of water (20 C) = 62.4 lbm/ft 1 gal = 8.345 lbm 1lft = 7.t,8 gal Avogadro's Number = 6.023 x 10 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 i

~

grams j e = 2.72 1 AMU = 1.66 x 10 u = 3.14159 Mass of Neutron = 1.008665 AMU 1 KW = 738 ft-lbf/sec Mass of Proton = 1.007277 AMU 1 KW = 3413 Btu /hr Mass of Electron = 0.000549 AMU 1 HP = 550 ft-lbf/sec One atmosphere = 14.7 psia = 29.92 in. Hg 1 HP = .746 KW *F = 9/5 *C + 32 1 HP = 2545 Btu /hr 'C = 5/9 (*F - 32) 1 Btu = 778 ft-lbf *R = *F + 460

-16 'K = *C + 273 1 MEV = 1.54 x 10 Btu

~2I h = 4.13 x 10 M-sec 1 W = 3.12 x 10 fissions /sec g = 32.2 lbm-ft/lbf-sec c = 931 MEV/ AMU 0

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

-8 Btu /hr ft 2 R 4 a = 0.1714 x 10

r Pega 4 of 5

• ' DOIe_SUEEI-ECVE80GE_INE8dGL_CONDUCI1Y11Y_1Kl .

Obtettal E

~O.025

, Cork .

L Fiber Insulating Board _ O.028 Mrple or Oak Wood . 0.096 L Cuilding Brick O.4 Window Glass O.45 Cancrete 0.79-1%' Carbon Steel 25.00 1% Chrome Steel 35.00 Aluminum 118.00 Capper. 223.00 Silver 235.00

~ Wster" (20 psi a, 200 degrees F) 0.392 Steam (1000 psia, 550 degrees F) 0.046 Uranium Dioxide 1.15 H211um 0.135 Zircaloy 10.0 l'

d1SCELLONEQUS_1NEQ8dOIlON:

E = mc KE = 1/2 mv PE = mgh V

f =VO + at' Geometric Object Area' Volume

.Tri angl e A= 1/2 bh /////////////////

Square A =-S* /////////////////

Rectangle A=LxW /////////////////

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

Rectangul ar. Solid A = 2(LxW + LxH + WxH) V=LxWxH (2 nrz)h + 2(wr2) 2 Right* Circular Cylinder A= V = wr h Sphere A = 4 nr 2 V = 4/3 (nr2)

///////////////////////////// V*S Cube

Pcge 5 of 5 D8Ie_SUEEI dlSCELLONEQUS_INEQBd8I1ON_icanttouedi:

10 CFR 20 Appendix B Table I Table II Gamma Energy Col I Col II Col I Col II MEV per Air Water Air Water Disintegration uc/ml uc/ml uc/ml uc/mi Material Half-Life

-6 ~0 1.84 h 1.3 Sub 2x10 ----- 4x10 ------

Ar-41

~# ~3 ~0 ~D 5.27 y 2.5 S 3x10 1x10 1x10 5x10 Co-60.

~ ~D ~10 ~#

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

~U ~# ------

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

~#' ~u 3x10

~0 1x10

~4 2.52 h O.59 S 9x10 4x10 Ni-65

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

~ ~11 ~#

---

S 1x10 1x10~ 3x10 3x10 Sr-90 29 y

~D 1x10 ~#- ------

Xa- 135 9.09 h O.25 Sub 4x10 -----

-9 9x10 -5 -10 -6

' which Any single radionuclides with Tdoes not. decay by 1

alpha 3x10 or/2 > 2 hr 1x10 3x10 spontaneous fission 2 Average flux to deliver Neutron Energy (MEV) Neutrons per cm 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 /> 6 670 thermal 970x10 6 400x10 280 (neutrons) 0.02 6 ----------

• 43x10 30 0.5 24x10 6 '

37 c,2 x ,,e 10 Linear Absorption Coefficients p (cm~I)

Water Concrete Iron Le:ad Energy (MEV) 0.090 0.21 0.63 1.7 0.5 0.067 0.15 0.44 0.77 1.0 0.057 0.13 0.40 0.57 1.5 0.048 0.11 0.33 0.51 2.0 0.49 2.5 0.042 0.097 0.31 0.038 0.088 0.30 0.47 3.0

Page.68 8t__EBINCIELE2_DE_BE8GISB_QEEB8IIQN

.t ANSWER A.01 (1'.50) c.- 2 p . b .- 1

o. 3 s

(0.5 pts'ench = 1.5)

REFERENCE

}Recctor Operations, p. 1.5-3 ANSWER A.02 (1.00)

(1) Increases (0.5)

(2)' Remains Constant (0.5)

~ REFERENCE NUS Reactor Operations 10.3 and 10.6 ANSWER A.03 (3.00)

c. (1) Directly from fission. (.25)

(2) From beta decay of fission products iodine 135 and te11urium135. (0.375) Tellurium-135 decays to iodine-135 (20 seconds half-life) which then decays to xenon 135 (6.7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> half-life). (0.375)

b. (1) Burnout by neutron nbsorption. (.333)

(2)' Beta decay to cesium 135 (0.333) with a 9.2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> half-life.

'(0.333) i

c. Iodine has a shorter half life than xenon, so initially after a trip, xenon will build up because the only removal mechanism remaining is xenon decay. (1.0)

REFERENCE NUS Reactor Operations, 10.2-1

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

_ - . _____-_____-_____-___________-__j

Page 69 "81__EBINQ1ELER_QE_BE80IQB_QEEB8I1ON l ANSWER A.04 (1.25)

Control rod worth increases. . (0.5) As a moderation is decreased and.the prebcbility of leakage into a control rod increases, the effectiveness of

.tha control rods increase. (0.75)

' REFERENCE Rocotor Operations; 8.3.2 ANSWER 'A.05 .(2.00)

c. The time required f or. the neutron density (or flux) to change by a-factor e.- (1.0) b.- When a reactor'is critical on prompt neutrons alone (i.e., a reactor became prompt. critical when the reactivity is equal to the fraction of delay neutrons. (1.0)

REFERENCE Rocctor Operations, 6.2-1 ANSWER A.06' (1.00)

P= Po*exp (t/T) 10,000 = 100*exp (t/30) in 100 = t/30 t = 30*4.6 = 138 seconds l

= 2.3 minutes (1.0) .

REFERENCE-Rocotor Operations, p. 6.3-1 l

l l

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

k

.v g Page 70 i:6t__EBINQ1ELEH_QE_BE8CIQB_QEEB6IIQN ANSWER A.07 -(2.00)

c. K-infinite is the multiplication constant for a theoretical reactor with zero leakage. K-effective takes into account neutrons lost due-to slow and fast leakage (k-eff = k-inf

• slow and fast non-leakage probability.) (1.0)

b. k-excess = k-effective-1.= 1.0795-1 u 0.0795 delta k (0.5)

c. Reactivity'= (k-effective-1)/k-effective = (1.0795-1)/1.0795 =

0.0736 delta k/k (0.5)

REFERENCE-l- NUS Corp., Reactor Operations, p. 1.3-2, 2.1-1, and 2.1-2 ANSWER A.08 (2.00)

c. The: fraction of all neutrons in a given generation which are emitted from.the-decay of fission fragments at a significant time after.the actual fission event. .(1.0) .

4o chug W Siu bxAx- 0Mm one

b. -Ves - ( 0 . 2 5 -) , as core exposure incrhses, the e m D 4,s- f c pg build-up of ru2. end e M(lC ORD f u- 2 41, +eus e: bete *r-: tien t; decrees due to ineir uiiferent Bet: f r:ct4on. (4 ,754 (1.0) (Exact wording not required)

A

.. REFERENCE Ranctor Operations, p. 52-1, 5.3-2 l

1 t

l

(***** END OF CATEGORY A *****) I

- _ ______-__________a

L

't Page 71 1 at__EE6IUBE1_DE_E6CILIIX_ DESIGN f

ANSWER B.01 (3.00) l n.. The reactor vessel is located in a water filled pool, and provisions are made for entry of pool water into the vessel to the extent necessary to make up boiling losses (from decay heat) under conditions of no coolant circulation. System breaks (valve 5500/0) inside the pool would, of course, allow free admittance of pool water to the primary system.

b. ' The antisiphon system connects to exit line on the invert loop which is designed to prevent siphoning of the coolant in the primary system in the event of a pipe break below the core level outside the pool.

c. Automatically actuated isolation valves 507 A/B on the inlet and outlet lines (1.0 each = 3.0)

REFERENCE MURR Training Manual, p I-8 ANSWER B.02 (3.50)

A. Control Blade B. Small Graphite Reflector Elements C. Irradiation Elements D. Beamport E. Fuel Elements F. Beryllium Reflector G. Large Graphite Reflector Elements (7 at 0.5 each = 3.5)

REFERENCE MURR Training Manual p I-2

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

t

4 Page.72

'St__EEeIUBEE_QE_EeQILIIX_ DESIGN LANSWER B.03 (2.50).

o. Constant pressure is maintained by automatically feeding'in or bleeding out nitrogen gas (0.5). Water level is automatically maintained by pumping in or draining out water (0.5)

b. hi pressurizer pressure lo pressurizer pressure lo pressurizer level (3 at 0.5 each = 1.5)

REFERENCE

-MURR Training Manual, p I-46 to I-48 ANSWERi B.04 '(2.00)

c. Forms a seal between the containment building (0.5) ~and the adj acent laboratory structure (0.5)

b. The water is elevated out of the water seal partially flooding the floor in the adj acent room. (1.0)

~ REFERENCE MURR HSR p 3.2 ANSWER B.05 (1.00)

s. Doors will close (and remain closed until power is restored) (0.5)

Doors will be closed by: gravity (0.5) b.

. REFERENCE MURR.HSR 3-7 I

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

l

Page 73 Rt__EE8IMBES_QE_E801LIIX_ DESIGN ANSWER B.06 (2.00)

a. The reactor scrams

b. The containment ventilation system isolation doors close

c. The containment exhaust isolation valves close

d. The' containment horns sound

o. The flashing red light exterior to the personnel air lock is on (any 4 at 0.5 each - 2.0)

$. n udeopr c (4Ma,6% y c,\gje g g k d 5 REFERENCE MURR FEP-2 ANSWER' B.07 (1.00)

1. Assure adequate slot width is maintained (0.5)

Reduce the possibility of rod binding (0,5) 2.

REFERENCE MURR Training Manual I-6

(***** END OF CATEGORY B *****)

l c

Page'74 )

' C A__QENEB8L_QEEB811NQ_GB888CIEB11I1Q1 -

ANSWER' C.01 .(1.00).

To cinimize'the corrosion rate (0.5)

To minimize induced' activity (0.5)

REFERENCE MURR SOP /II-4 1 ANSWER C.02 (3.00)

c. All shim rods are fully inserted

b. One of.the following conditions exist:

1.' The "Mester 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 operatortis present in the control room and the dummy load control rod test connectors are inst lied ~

c. No work is in progress involving transferring fuel in or out of the core

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

o. The reactor pressure vessel cover is secured in position and'no work is in progress.on the pressure vessel or its supports (cny three at 1.0 each = 3.0)

REFERENCE MURR Tech Spec 1.20 ANSWER C.03 (2.00) l

1. Natural convection to pool with vessel head removed.and flanged port

-open C.25) - Limited to 100 kw C . 25 3'

2. Reactor loop pressurized with only one pump and one heat exchanger in use (.25) - 1850 (+/- 50) spm flowrate (.25) - 5 Mw (.25)

Reactor Loop pressurized with two pumps and two heat exchangers in use 3.

(.25) - 3700 C+/- 50) spm flowrote (.25) - 10 Mw C.25)

/

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

t k

Page 75 Gi__GENEB8L_DEEB8IIND_CB8B8CIEBISIIG1 4

i REFERENCE MURR HSR'n 5-1 ANSWER 10.04 (2.00)

a. 67 +/- 3 psig

b. 105 degrees F +/- 5 degrees F

c. 120 degrees F +/- 5 degrees F

~d. 29'-7" +/- 3" REFERENCE SOP /I-14

-ANSWER C.05 (1.00)

1. Master switch in " test" position (0.5) 2 .1 Rod magnets are de-energized (0.5)

REFERENCE MURR HSR p 9-21 ANSWER C.06 (2.00)

a. Flowrates were adjusted according to the composition of the special reflector elements in the reflector irradiation area such that the(1.0) pressure drop across the reflector region is kept. constant.

b. To remove core decay heat from the reflector and experimental (0.5) facility.

c. To allow oxygen and nitrogen activity to decay before coolant water is returned to the pool. (0.5)

REFERENCE MURR Training Material p I-38-39

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

L C Page 76 Ga__fENEB8L_DEEB8IINS_GH6BaGIEBISIIGS ANSWER .C.07 (3.00)

1. ' Changes _in reactor reactivity due to beamport activities (such'as draining or flooding a beamport)

2. Exposure of personnel to radiation (as a result of movement of shielding or inadequate' shielding) .

3. Release of radioactive gases (such as Ar41) which are produced'in'the beamport

4. Production of explosive or toxic materials in the beamport

.(4 at 0.75 each = 3.0)

REFERENCE MURR' SOP VIII.4.1.A

(***** END OF CATEGORY C *****)

'{0

.Page 77

!Qi__INSIEUBENIS_eND_GQNIBQLS l ANSWER .D.01 (3.00)

1. Provides~ assurance that the radiation level from direct core radiation above the pool will.not exceed 2.5 Mr/hr: (1.0)

.2. Prevents reactor operation with,e'ventLtank level which could result in the' introduction of air to the primary coolant' system ,

(1.03-

13. Provides assurance that'the introduction of air to the invert loop is 4 sufficiently rapid to prevent siphoning action-following a rupture of theLprimary coolant piping' (1.0)

REFERENCE MURR. Training Manual p II 65-66 LANSWER D.02 (1.00).

To prevent a building isolation alarm while the blade-is being handled out

of water. (1'.0)

. REFERENCE.

MURR'SO'P II.3.2.A ANSWER > D.03 (3.00)

s. Fission Chamber (0.5) - Pulse Height Discriminator (0.5) b.: Compensated Ion Chamber (0.5) - Gamma ray induced currents are automatically subtracted from the total current-readings (0.5) c.- Uncompensated Ion Chamber (0.5) - Neutron flux is of sufficient intensity that gamma is insignificant (0.5)

REFERENCE i

MURR Training Manus 1 p II4, II-12

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Page 78 lDt__INSIBudENIS_6ND_99 NIB 9LS ,

ANSWER. D.04 L2.00)

1. The period as indicated by both IRM-2 and IRM-3 must indicate not-less than 35 seconds 2,' .The WRM selector switch must be in the 5 kilowatt-red scale position or above-

3. .The power trace pointer (black) on the WRM recorder must be reading greater than the auto control prohibits setpoint (red)

4. The regulating blade position must be greater than 60% withdrawn such that the 60% annunciator alarm is energized (4 at 0.5 each = 2.0)

REFERENCE MURR Training Manual p II-79 ANSWER- D.05 -(1.00)

Will cause water to bypass the core resulting in low differential pressure (0.5). Differential pressure switch 929 signal will cause trip unit to reech flow scram setpoint (0.5).

REFERENCE MURR Training Manual p'I-26 ANSWER D.06 (1.00)

c. Prevents the regulating control rod from being operated in the automatic mode. (0.5) b.- Reset'using the reset switch (0.5)

REFERENCE MURR Training Manual p II-30-32

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I-Page 79 Dt__IN11BudENI1_6ND_GDNIBQL1 i

ANSWER' D.07 (2.00)

c. To indicate possible fuel failure (0.5) - Monitors effluent from the reactor on the discharge of heat exchangers 503 A and B (0.5) b.- To detect leaks into the secondary system from the pool or primary (0.5) - Located on the return line from the heat exchanger ( 0. 5 )-

REFERENCE MURR' Training Manual p II-46, II_49

' ANSWER D.08 (1.50)

1. a

-2. d

3. c REFERENCE MURR Training Manuel~II-67 l

l

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

) - - -- - . _ - - _ _ - - _ - _ _ _ - - _ _ _ -

2 Page 80

[Et__18EEIX_8NDEMEBAENCX_111IENS

' ANSWER E.01 (2.00)

Tho cafety. system utilizes 1 of N logic (0.5) with each input trip signal' fod in parallel to each solid state logic unit. Either logic. unit will trip a pair of amplifiers supplying current to the scram magnets whenever one of the scram. inputs signals is interrupted (1.5)

~ REFERENCE MURR Training Manual I-11 ANSWER E.02 (2.00) ,

1. emergency lighting system

2. reactor exhaust system

'3. -reactor instrumentation

4. air lock doors (4 et 0.5 each - 2.0)

REFERENCE MURR-Tech Spec 4.5 ANSWER E.03 .(1.50)

(1), (3), (4)

(3 required - 0.5 pts each - Will do proportional grading for each incorrect answer up to the value of the question)

REFERENCE MURR: SOP /I-15-18 ANSWER E.04 (1.00)

(3) and (5)

(2,roquired - 0.5 each - Will do proportional grading for each incorrect cnawor up to the value of the question)

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g  ;-

1.- x h 4 b .' ' ., .

l Ei;_18EEIX_8NQ_EdE BGE NGI_111IEMS : Page 81.

LREFERENCE' MURR; Training Manual p IVS

'AN'SWER E.05' (2.00)

.Hiidolta P -possible core blockage (.75)

.Lecdolta P -Dindicates reduced. flow (.75)

Doth cerve as1e' backup to pool. coolant Iow flow. scram (0.5)

REFERENCE

'LMURR Training Manual, p:II-63, 11-70 and Tech Spec 3.3 p.4 ANSWER E.06 (1.50)!

c. . Loss of site electrical power.at substation'"B"'(0.5) , '

(0. 5 3' W Signal f rom seven day ' clock plant exerciser (A 'Or WM C ALC ,-.

ib. To~essume the' load should any additional power. interruptions occur. 1 (0.5)

L REFERENCE' '

.MURR TrainingiManual p I1110-12 ANSWER E.07 (2.00) lo. Mester Control switch (1S1) must be turned to " test".and thenLback to "on". (.75)'

b .- With the prweent antisiphon system the core stays pressurized and the

! 944s can remake, causing cycling of the pumps and valves if not for the circuit lockout. (.75)

c. Can'be bypassed in 50 kw mode. (0.5)

-REFERENCE MURR Training Manuel p-I-34, I-75

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i

. W: '

1 r +: j e ,

Page 82 j

! Et__18EEIX_eWQ:_EMEBSENC X_112IEMS .l

'i 2 ANSWER- E.08 (2.00)

(2),-(5), (6), (7).

(4 required - 0.5 pts 'esch - Will do proportional grading-for each incorrect answer up to the'value of the question)

REFERENCE MURR SOP /I 15-18

(***** END OF CATEGORY E *****)

E p i

~Page'83

( El_l1I8ND 8BD_8ND_EtlEBEENGX_QEE B8IING_EBQ G E DUBES I

' ANSWER' F.01' '(1.50)

'3' 0..

b. '2

c. 4 (3 0 0.5 pts each = 1.53' LREFERENCE- ,

MURR SOP /I-13a

' ANSWER' 'F.02 (1.50)

c. . Gamma (0.5) or neutron (0.5)., or us O.CCeM @ l f b '. [ Control room logbook. '(0.5) f~

' REFERENCE MURR SOP /III-1 ($b) #' W ANSWER F.03 (1.00)

c. The reduced flow is to minimize plate erosion. (0.5) b'. Area should be monitored by a health physics (or adequate protective measures should be~taken before entering). (0.5)

REFERENCE MURR REP-20

. ANSWER F.04 (2.00)

1. Scram the reactor (0.5)

'2. Note' approximate stuck position (0.5).

3. Pimee master switch in test to prevent mechanisms from driving in (0.5).

(0,5)

?4.. Verify the reactor is shutting down by nuclear instrumentation.

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

Page 84 Et__SI6HDaBD_80D_EdEBGENCY_QEEBoIING_EBQQEDVBES REFERENCE i MURR REP-8 ANSWER F.05 (3.00)

1. The systems and instrumentation other than those referred to in the short form pre-startup checksheet have been on continuous operation since the completion of the last comprehensive startup checksheet (0.5) and the routine systems check sheet has revealed no abnormalities (0.5).

2. A full power or low power pre-startup checksheet has been completed within eight hours prior to the time a short form checksheet is to be used (0.5) or the reactor has been operating at has some time within the not been completed previous eight hours and a shutdown checksheet within this period (0.5).

3. No anomaly with regard to any systems not covered by the short form checksheet has occurred since completion of the last comprehensive startup checksheet (1.0).

REFERENCE MURR SOP /I-5 ANSWER F.06 (1.00)

a. Reactor Manager (0.5)

b. Shutdown (0,5)

REFERENCE MURR SOP /I-10 ANSWER F.07 (2.00)

Two pumps cannot be started at the same time because the basin level will be drawn down faster than the makeup water can be supplied, which will After one pump is result in the actuation of a low sump level trip (1.0).

started, it is necessary to wait at least 10 minutes before starting the second pump (1.0).

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

y O'

Page 85

'Et__118NQ880_8HD_EMEBGENQY_QEEB8IING_EBQQEQUBES REFERENCE-MURR SOP /VI3

ANSWER F.08 (1.00)

c . 5. inches i

b. .2' inches (2 ot 0.5 = 1.0)

REFERENCE MURR SOP /II-1' LANSWER F.09 (1.00)

-1. By use of. skimmer system (0.5)

2. By'use of pool pumps (0.5)

' REFERENCE MURR SOP /V4 ANSWER F.10 (1.00)

1. SRO (0.5)

-2. R0 C.25) under direct supervision of anSROj.25)

REFERENCE MURR SOP /II-3

(***** END OF CATEGORY F *****)

L. _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _

e 1

-O

.-f ISt__B8DI8IIQN_GQNIBQL_8ND_18EEIX; Page 86

-ANSWER G.01 (1.50)

1. . Sludge'S'ettlement

. 2 .. Cuno Filters

3. . . Chemical Precipitant Treatment REFERENCE 4 MURR SOP /VII44 ANSWER G.02 (2.00)

c. 1. Whole body.1.25 rem

2. Hands and feet 18.75 rem

3. Skin 7.5 rem (0.5. pts each)

b. 10% of above limits.

(0.5 pts each)

REFERENCE 10 CFR 20.101,-104 ANSWER 'G.03 (2.50) c .~ .

Dose - The quantity of radiation absorbed per unit mass by the body or by any portion of the body. (0.5)

b. Contamination - The deposition of radioactive material in any place where it is not desired, particularly if its presence is harmful to personnel. (0.5)

o. Red - A measure of the ionization produced in a specific material by any type of ionizing radiation.

d.. Dead Time - The time during which a second pulse cannot be detected.

(0.5)

o. Half Value Layer - A term used to represent shield. A half value layer of a material, HVL, reduces the intensity of incident radiation by a factor of 2 (or reduce radiation to one half of their original value). (0.5)

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

o ~ .

L-E Page.87 fSt__B6D16IION_QQNIBQL_6NQ_18EEIX

] s i

REFERENCE NUS; Corp.,. Radiation Protection, p. 1.5-1, 2.1-2, 3.1 2, 3.3-7, 5.4-4 ANSWER G.04- (1.00)

'R/hr.=:6 CE/d2 .(0.25)

R/hr = 6(5)(2.5)/(2)2

= 18.75 R/hr. (0.75)

REFERENCE NUS Red Protection 3.2 ANSWER G.05- (1.00)

All reasonable steps will be taken to keep the dose to plant' workers as low co ' 10 reasonably achievable. (1.0)

REFERENCE NUS Rad' Procedure, p. 22-2 ANSWER G.06 (1.00)

Toff = TB x TR TB + TR (0.25)

Toff = 30.2 years x 70 days 30.2 years + 70 days m' 11023 days x 70 days 11023' days + 70 days

= 771610 days 11093 days

= 69.56 days or .19 years +/- 5% (0.75)

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

e s

Page 88 St _B8DI8IION_CQNIBQL_8NQ 18EEIX REFERENCE NUS Radiation Protection, p. 1.5-5 ANSWER G.07 (2.00)

1. d

2. b

3. a

4. C 7

(4 0 0.5 pts each = 2.0)

REFERENCE Basic Nuclear Concepts, p. 7.4.2 ANSWER G.08 (1.00)

I-131 concentrates in the thyroid and can produce severe damage. It is the most hazardous fission product excluding Pu; therefore, it is the most limiting factor. (1.0)

REFERENCE NUS Radiation Protection ANSWER G.09 (1 00)

1. Job Supervisor (0.33)

2. Health Physics (0.33)

3. Shift Supervisor (0.34)

REFERENCE MURR SOP /I-12

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

a' Page 89 ft__B8DI8IION_QQNIBQL_6ND_SaEEII

\

l l

l ANSWER: G.10 (1.50)

1. Film' badge

2. TLD l

3. Pocket ion chamber

4. Finger Ring (Any 3 6 0.5 pts each = 1.5)

REFERENCE NUS. Radiation Protection Unit 6

(***** END OF CATEGORY .G *****)

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

77_. _

1

'lJ '

E -TEST CROSS REFERENCE Page. 1.

LQUESIl0N. _Y8LUE- BEEEBENCE_

A'.01 1.50- 9000059.

A.02- 1.00 '9000060' A.03' 3.00- 9000061

.A.04 1.25 9000062 A.05 2.00 9000063-A.06 1.00 '9000064 A.07 2.00 9000065 E ~A.08 2.00- 9000066 13.75 B.01 3.00 9000067 B.02 3.50 9000068

.B.03' 2.50- 9000069 18 . 0 4 2.00 9000070' B.05 1.00 9000071.

~

B.06- 2.00 9000072 B.07 1.00 9000073 15.00

.C.01 1.00 9000074 C.02 3.00 9000075 C.03 :2.00 9000076 C.04 ,

2.00- 9000077

'C.05 1.00 9000078

' C. 06- 2.00 9000079 C.07' 3.00 9000080 14.00' D.01 3.00 9000081

-D.02 1.00 9000082 D.03- 3.00- 9000083 D.04 2.00 9000084 0.05 1.00 9000085

.D.06 1.00 9000086 D.07 2.00 9000087 D.08 1.50 9000088 14.50 LE.01 2.00 9000089 E.02 2.00 9000090 E.03- 1.50 9000091 E.04 1.00 9000092 E.05 2.00 9000093 E.06 1.50 9000094 E.07 2.00 9000095 E.08 2.00 9000096 14.00

.F.01 1.50 9000097 F.02 1.50 9000098

s .

• L:I J

! , . TEST CROSS REFERENCE' Page'.2 m g-42WERIl0N _Y6LUE* BEEEBENCE_-

L ' F.03 1.00 9000099

[' F.04 2.00' .9000100-

= F.05' 3.00 9000101 F.06- 1.00 9000102 F.07' 2.00 9000103.

'E.08' 1.00 :9000104 F.09 .1.00- 9000105 F.10 1.00 9000106 15.00-

?

6.01- 1.50 8000107 6.02 2.00: 9000108 9000109' 6.03 2.50 -

, - 6.04 .1.00 9000110-6.05' 1'00

. 9000111:

G.06 '1.00 9000112-G.07: 2.00- 9000113 6.08- 1.00 .9000114 G.09 1.001 9000115 '

G.10 1.50 9000116-14.50 100.7 b.. '

11