ML20207R971

Exam Rept 50-186/OL-87-01 on 870224-26.Exam Results:Two Upgrade Operator Candidates & One Operator Candidate Passed

ML20207R971
Person / Time
Site:	University of Missouri-Columbia
Issue date:	03/13/1987
From:	Burdick T, Hare S, Ridgway K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20207R961	List: ML20207R960 ML20207R971
References
50-186-OL-87-01, 50-186-OL-87-1, NUDOCS 8703180372
Download: ML20207R971 (73)

Text

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U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-186/0L-87-01 Docket No. 50-186 License No. R-103 Licensee: University of Missouri Research Park Columbia, M0 65201 Facility Name: University of Missouri at Columbia Research Reactor Exanination Administered At: University of Missouri at Columbia Research Reactor Examination Conducted: February 24-26, 1987 Inspector:

ItllIltl 3/,7 /s 7 K. R. Rik'wayva9 Date' WW f 3\sW7 Date Approved By: T. M. Burdick -/f(

Date Examination Summary Examination on February 24-26, 1987 (Report No. 50-186/0L-87-01)

Examinations were administered to two upgrade senior operator candidates and one operator candidate.

Results: All candidates passed.

8703180372 870313 PDR ADOCK 05000186 V P DR ._

REPORT DETAILS

1. Examiners

• K. R. Ridgway E. A. Hare

• Chief Examiner

2. Examination Review Meeting An examination review meeting is no longer conducted. Specific facility comments concerning written examination questions, followed by the NRC response, are enumerated in the following paragraphs.

a. Two comments were made concerning the reactor operator written examination.

Question A.04 Facility Comment: Since the University of Missouri Research Reactor uses highly enriched fuel (93% U-235), we do not attempt to quantify the fuel temperature coefficient of reactivity for our reactor. We could expect the operator candidate to understand the theory behind the fuel temperature coefficient of reactivity, but we would not expect him to understand, in depth, the factors that would cause the coefficient to vary, since it is not directly applicable to our reactor.

The only real concern here is the high weighting factor placed upon this question. I believe the candidate will be conversant with the concept of the Doppler effect in fuel, but I doubt if he will have much depth in this area of theory.

NRC Response: Agree. This question has been removed from this examination.

Question / Answer E.02 The terminology " PERIOD AUTOMATIC CONTROL" is not typically used.

This is illustrative that the attempts we have made to revise our Training Manual have fallen short. Much of the terminology in the Training Manual was taken from Technical Manuals and do not correspond to operational terminology.

This is still a valid question, one that the candidate should be able to figure out, however, I wouldn't be surprised if the answer given involves period shutdowns (RRI and SCRAM).

NRC Response: Agree. The question and answer have been reworded to " Automatic Control" period interlock. Full credit was given for the candidates answer.

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b. One comment was made concerning the senior operators written examination.

Question H.10 (b)

Since we don't produce steam, we don't teach use of steam table.

I would expect one senior (ex-Navy) to do well, and the other might surprise me.

NRC Response: Agree. This question will not be placed in the NRC question bank, however, since both candidates answers were correct, this examination will not be changed,

c. Several corrections and clarifications were made to the senior operators examination as follows:

Question / Answer I.10 Four Emergency Procedures were changed to five, and Security Procedures added to the answer.

Question J.05 The question was reworded by adding " upper (max)" to clarify what limits were desired.

Question K.03 The question was reworded by adding " SOP" to clarify which setpoints were desired.

Answer I.02 a Pool cooling water was added as a source of N-16.

Answer I.02 b Ventilation of beam ports and thermal column, dilution of A-41 in the pneumatic system were added to precautions taken to reduce A-41 effects. Shielding was added to precautions taken to reduce Na-24 effects.

d. Other corrections made to the operator examination are as follows:

Answer / Reference C.02b 30 second period used up to 1.0 MW greater than 1.0 MW use 100 second period. The reference was changed to SOP /II-1.1.P.

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Question / Answer / Reference C0.4 SOP was added to the question to clarify what setpoints. Answer to Part F was changed to "< 10%." Reference was changed to S0P I Table IV.

The above resolutions and changes either did not affect the applicants' answers or were taken into account when assigning point value to the applicants answers.

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3. Exit Meeting ,

At the conclusion of the startup portion of the plant walk-through examination an exit meeting was held. The following personnel' attended this exit meeting:

Facility Representatives:

D. Alger, Associate Director W. A. Meyer, Acting Reactor Manager NRC Representative: '

K. R. Ridgway, Chief Operator Licensing Examiner The following observations were discussed:

a. One candidate and several other operators were observed to be wearing their film badges facing toward their body thus, obfuscating  ;,

any beta radiation contribution. ,j

b. One candidate smoked while in the emergency generator room which As was recently posted as a no smoking area. '

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MASTER CCtPJ

, _. U. S. NLICLEAR REGULATORY COMMISSION l ,

REAClOR OPERATOR LICENSE EXAMINATION FACILITY: _UNIVERSily_DE_MISSOUBl__

REAC10R lYPE: _ -TE_S _T_._ _ _ _ _.- _ _ _ _ _ .._ _ _ _ _ _ _

DATE ADMINISTERED: _ 82 / 9 2 / 23_ _ _ _ _ _ _ _ _ _ _,_ _ _ ,_ _

EXAMINER: _RIDGW6Y, K.

CANDIDATE: _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ , _ _ _ _ , _ _ _ , ,

i INSIEUCIJOU3_lO_C6991D61El Lis e separate paper for the answers. Write answers on one side only.

Staple question sheet on top of the answer sheets. Points for each questi on are indicated in parentheses af'ter the question. the passing grade requires at least 70% in each category. E::ami na ti on papers will be pici:ed up si: (6) hottrs after the examination starts.

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% OF cal;EGDJY  % OF CANDIDAIE'S CATEGORY

__ksbtK. .10lGL __ _ _ % D B L __ _, _V 6 6 U E _ _ _ _ _ _ _ , _, . __ _ _,, __ _ _ C G I E G O R Y _ _ _ _ ,, _ ,,,_ ,, _, _ _ , .

_12t99 _ .1E'.11 _ ____.___ _ _ _ _ _ _ _ _ _ . . . A. PRINCIPLEG OF REAClOR OPERAT1DN

.10t9K _101.3B _ _ _ _ _ . . . _ _____..._._U. FEATURES OF FACIllTY DEEIGN

_1N.40 _ _16159 ___________ _.______._C. GE.NE,'AL OPERAl 1NG CNARACTERIS'lICS

_1lh.OQ__ _Idz}k , , , . _ _ _ _ _ , _ _ _

_ _ _ _ _ , _ _ _ D. INS 1RUMEm S AND CONTROLS

_1S1S9_. lb.@Z _ _ _ _ _ _ _ _ _ _______._E. SAFETY AND EMERGENCi SYSlENS

_1d x99_ __ _1b.M _ . . _ . . . . _ _ _ _ _ ___.______ F. Sl ANDARD AND El1ERSENCY OPERATINb FRUCEDURES

_ 1 3 1. W _ _ ..l 'i. 2 Z _ . _ _ _ _ . _ _ _ _ ________

G. RADI AT loN Lum not Aub SAFEli

_22aM9_ . . _ _ _ _ _ _ _ _ _ . _ . _ ___ _

% lotale Final bradc All worl. dont ore thi s exausination is n.y own. I have neithE. civen nor recel vc-d ald.

I t.% nd i d a t c 's Sianature

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R- NRCLRULES AND GUIDELINES'FOR LICENSE EXAMINATIONS.

gDuring the-administration.of this e,: amination the following rules apply:

1. Cheating on the examination mean,s an_ automatic denial of your application and could. result in more severe-penalties.

2. Restroom trips are'to be7 1imited and only one candidate et a time may leave. You mush avoid'all' contacts with anyone outside the examination-room to avoid even'{he hppearance or possibility of cheating.

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13. Use black ink or dark pencil'ggly to facilitate legible reproductions.

j4. Print your name in the blank provided on the cover sheet of the examination.g

5. Fill'in the date_on the cover. sheet of the examination- (if necosnary).

6. Use only the paper provided for answers.

7'. Print your name'in the upper right-hand corner of the first page of-each

.section of the answer sheet.

B.- Consecutively number each answer sheet, write "End of Cateoory __" as cppropriate, start each category on a gew page, write gely 90 gge gide

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of the paper, and write "Last Page" on the last answer sheet.

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

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10. Skip at least thtee lines between each answer.

11. Separate answer sheet's from pad and place einished answer sheets face Ldown'on your desk oritable.

12. Use abbreviations.only if they are-commonly used in facility litetetute.

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

s. 14. Show all.calculat' ions, methods, or assumptions used to obtain an answer to mathematical prcblems whether indicated in the question or not.

['m: - _

4 15.~ f Part i al credit may be given. Therefore, ANSWP L PARTS OF I bi;

. NL$i1GN AND DO NOT LEAVE ANY ANSWER BLAuk.

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16. Ii'barts of the examination are not clear 4 i. stent, ask ques tions at the (n:,ami.,ner; only.

, '17..You must sion;the statement on the cover sheet that indicates that the c work is your J own and you have not received or been given assistance in f compl eting the examinat on. This must be done after the examination has been compl,eted.

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-.. 1% I.When you! complete ~your examination, you shall:

a. Assemble your~ examination.as follows:

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. (1 )_ Exam questions ~on-top.

(2)- ' Exam l aids' -

' figures,~ tables, etc.

(3) ' Answer pagesiincluding figures which are part of~the' answer.

., Turn in y'our-copy ofz the examination and.all pages used to answer

'b.

the' examination questions.

.c. Iurn 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 stills in. progress, your license may be denied or revoked.

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, f6; _ PRINQIPLES_QF_REAQTQRigPERAIIQN. PAGE 2-T

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.. QUESTION [A.01 (3.00)~.

u Briefly -explain the dif f erence between:

- ;a. Fast and' prompt. neutrons- ( 1. 0) ~

b. : Sl ow -and delayed neutrons (1.0)

c. Activity and' reactivity (1.0)

-QUESTION 'A.02-(1.00)

~A reactor has'a-count rate of 45 when it has a Keff of O.965, whatf2s the

'Keff:of this reactor when it has a count rate of 90? -il . 0)

OUESTION. A.03 (1.50)

Explain'how source-neutrons are generated at the MURR.

QUESTION- A.04 (2.50)

a. What is nucleate boiling? (1.0)

b. .

What is meant by the term "DNBR"?-(1.0)

c. What is the DNBR limitation for the MURR7 (0.5)

DUESTION ~A.05 (1.00)

What is the decay heat and how is.it produced? (1.0)

QUEST 1014 (4.06 (3.00)

'Epplain the. production and removal mechanisms for Xenon-135 and Samarium-147. (3.O)

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(*++** END OF LAIEGORY A *****)

- B __EE61UBES_GE_E8CILITY_DESIGij PAG'E 3 5

OUESTION B.01 (3.00)

What three features are designated in the reactor cooling system to protect the core from a loss of coolant accident?

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OUESlION B.02 (2.00)

Pressuriner pressure is not required below 50 Kw if certain conditions are met. What ar e these conditions? (2.0)

DUESTION E.03 (2.00)

State the four automatic plant respontes to the initiation of the r eactor isolation system.

QUESTION D.04 (3.00)

a. What is the purpose of the Antisiphon syctem? . ( 1. 0 )

b. What two conditions must be met to perf orm its f unction? (2.0)

DUESTION B.05 (2.50)

a. Describe how the Reactor Loop Vent Syctem Liquid Level Controllers LC925A and LC925B operate in conjunction with the venting of gases from in pool primary piping. Be sure to include ALL automatic actions associated with signals from these controllers. (1.b)

b. Deccribe the fIowpath for the exhaust 1ine from the vent t an F-including major components and final m:haust point location. (1.0)

DUES 11DN D.06 (2.DO)

List five (5) of the cir (6) conditious t. ! . a t must be satisiied ter r e w. t or containment integrity to exist.

(+++++ END Ui' CATfWURY B +++H)

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>Gz__QgNEB96_QPEBBIINQ_GH9899IEB191195 PAGE. J4 r

EQUESTION' C.01 (2:00).

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<Give the normal operating range for each of the following parameters 2(include uni ts) . :. - ,

a.:

Pressurizer Pressure

-b'c . Pool: Outlet Temperature (Hot Leg)

c. Reactor In1et Coolant' Temperature

d. Pool-Level' OUESTION C.02: ( 3. 00).

rIn regards to a reactor startup:

a. . At what: point during a-startup do you stop gang pulls'and start withdrawing single control rods? (1.0) b .; During a reactor.startup, different periods.are used.

.What are the periods and when is each used? (1.0)

.c. =What are two (2) of the four (4) conditions which must be met prior to. going into automatic reactor control? - ( 1. 0 )

4 ' QUEST 1 ON' C.03 (1.00)

What two conditions, when satisfied, will bypass the rod withdrawal prchibit? (1.O)

.OUESTION C.04. (2.00)

For ' the f ollowing condi tionsi, give the SOP setpoints and the auto action (scram or-run-in) for each. If the condition causes both actions-give both setpoints,

a. Short period

b. . ..Hi gh - Power

c. Hi Pressuriner Pressure

. d. Bui) ding Air P1enum Hi Ac t i vi ty.

e. Reactor Bridge

, f. , Reg Blade OUES TION C.05 (2.00)

'a. Why doec the procedure for shutdows: of the pr imary cysstem r equi re

that i t remain in operation after the reactor has been shut down?

. ( 1. 0)

.. t) . Explain why the system is only required to be run 15 minutes after a reactor shutdown. (1.0)

(++*** CATEGORY C CON I I NUE D ON t!E X i PAGE *****)

G. -GhiEBAL_gPEBATING_GHABAgTgBISTigg j PAGE- 5 QUESTION C.06 (1.00)

What problems are associated with radiation damage in the beryllium reflector and what causes it?

DUESTION C.07 (2.50)

Indicate whether each of the f ollowing reactivity coef ficients are positive or negative for the indicated locations.

a. Voi d Coef fi cient of the Flux Trap (0.5)

b. Void Coefficient of the Core (0.5)

c. Temperatur e Coef ficietet of the Core (0. 5 ;

d. Temperature Coefficient of the Pool (0.5)

e. Temperature Coefficient of the Flux Trap (0.5)

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

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DI__INEIBut!EUIS_8HD_CQUIBOLE- - PAGE 6' 4

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.OUESTION DiO1 ( 1'. 50 ) '.

{What.is.the difference between an uncompensated and a compensated lon-

chamber?-

_;OUEST1UN- D.02 (3.00)

-State the reasons 5 f ore the f ol1owing Rod- Run-In Protection Logic for:

' 1.'  : Low Pool. Level -

2i Vent' Tank Low. Level "

3. <.Antisiphon Line High Level i

QUESTION 'D.03 ~ (2.SO)

. List 5 of the 6 conditions which will discontinue automatic operation of

-the regulating rod. .

DUES 1IUN' D.04 ( 1. 00)-

iExplain how the automatic shim control circui t reposi tions the ,snim

-rods. . Include the various conditions which will cause rod' movement' l -.' and subsequent stopping-by this circuit. (1.0) s

'OUEST1ON D.05 (2.00)

The four reactor shim rods are attached to the rod drive mechanisms by DC *

. electromagnets.

Explain how the magnet current is controlled and what happens during a scrans.

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. QUESTION D.06 (2.50) be4 cre contr ol rods can=be pulled to start the reactor, six interlocks must be satistied. What, are five (S) of these si : conditions? (2 b) 4

- (****+ CATEGORY D COH!'INUED Uij NEXI PiEE * * * * ,4 )

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D;__INgIBUDENIS_6ND_CgNIBg65 PAGE 7 QUESTION D.07 (1.50)

Fi11 in blanks in the annunciator sequence table below. Use the fol1owlsig illumination choices: Ot'f, On Dim, On Bright, Flashing.

Condition 111 unii nat i on Audible Siqua)

Norinal (1) _ _ _ _ _ _ _ _ _ _ Of+

Alarn. Input (2) ________ On Alarm Input Acknowledged (3) _ _ _ _ _ _ _ . _ _ Off Return to Normal (4) .________ Off Reset (5) _____ ___ Off

. Test (6) _________ Dn

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• 4 :* ENI) U!- C A 4 titWi ? i b +++-**;

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Ez__SBEEly_6ND_EUE6GEUCy_SYSTEdg . PAGE 6 D

QUESTION E.01 (3.00)

The 16A and 168 valves are both containment building isolation valven.

Although similar they have a different method of valve closure.

a. Enplain the different methods of valve closure. (1.5)

6. During a loss of facility power (including the emergency generator),

will closure of the 16B valve be assured? Explain. (1.5)

OUEST ION E.02 (3.00)

a. Explain how a trip of the Automatic Control Period interlock circuit will affect rod control. (1.5)

b. If the Automatic Control Period interlock circuit were to trip, how can it be reset? (1.5)

OUESTION E.03 (2.00)

What is the basis for having a scram associated with differential pressure across the reflector region? Consider both high and low delta P. (2.0)

DUESTION E.04 (2.00)

The reactor is operating at b Megawatts with a core inlet pressure of 65 psia. For some unexplained reason pressure slowly begins to increase. Describe all actions (including alarms) that will be taken by the pressurizer and safety systems to control or impede this pressure increase. (Include setpoints.) (2.0/

OUESTION E.OS (1.00)

Which of the followirig components can be tupplied with air f r ou the Enier gency Backup Air Compressor? (1.O)

(1) Pool Loop Isolation Valve 509 (2) Reactor Loop Isolation Valve SO7A (3) Containment Building Enhaust 1 solation Valve 16A (4) Emergency Generator (S) Freight Door 101 Gast:et

(***** C A T E G O R Y' E CONilNUED LiN NE)1 PAGE ++*+*)

E.__SOEEly_9ND_EMEBGENCy_SYSIEd@ PAG 5 9 QUESTION E.06 (2.00)

What are the four major loads that the emergency generator supplies?

(2.O)

. QUESTION E.07 (1.50)

State the two locationn where the Facility Evacuation alarm can be manual 1y actuated.

(+*++* Elli) OF t.AlEGORY E +++*+)

Ed __ ElGU D6B D_ GbID_.EM E S Q E U G Y_O E E E G11H g_E B Og E gyB h b PAGE 10 QUESTION F.01 (2.00)

a. List the five Facility Emergency classifications. (1.25)

6. List three action levels for emergency classes. (0.75)

OUESTION F.02 (1.00)

State whether the following are TRUE or FALSE.

a. The Shift Supervisor will have operating authority over all experiments performed within the reactor containment or which may offect reactor operations.

b. The insertion and removal of ex per i snent s in the center test hole ponition wi11 be done with the reactor shutdown.

QUESTION F.03 (1.00)

During normal operations, the reactor operator notices that pool flow has dropped to 350 gpm in one loop operation. What would be the immediate actions as the operator? .

QUESTION F.04 (3.00)

Why would an operator be concerned if valves 546 A/B open during reactor-operation?

OllESTION F.OS (3.00)

For a facility evacuation, what are:

a. Four dutien of the duty oper ator- priot to leaving the conteol r cone?

(2.0)

, b. lhe t.wo dutiet of the asci ttant dut y operat or 14 he is in the containment bu i l d i n g'? (1.0)

OUESl1ON F.06 (2.00) -

When starting the secondar y cooling system, what Jimitations are plesced on the pumpu wiien at 10 Mw operations and why?

(+**** CATEGDPi F CONTINUED UN NEXl P4bE *****)

i Ez__SI6MD6BD_690_EUEBgEUQy_QEEBOIIUQ_E899EQUBES PAGE 11 QUESTION F.07 (2.00)

State four of the five immediate actions to be taken by the reactor operator upon receipt of a bomb threat or other overt threat.

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(****+ ErlD Of~ CA~lEGUky F- ++**+)

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^ OUESTION~:G.01 7(1.50) 4 State .the three methods used to remove radioactive. waste from the liquid

waste. retention system'in the form of. dry active' waste.

'OUESTION G.02 ~ ~(2.00)

Does the bialogical-effect of'100 REM depend on:

whether it is a neutron or a gamma dose? ' Explain. (2.0)

OUESTIGN G.03 (3.00)

According to'10 CFR 20, an individual in a restricted area may be allowed - to receive . a whole body dose of radi ation ,

greater than the 1.25 REMS per quarter when three conditions-are met. What are these conditions? Assume non-emeroency conditions. (3.0)

QUESTION G.04 (2.50)

Define.or explain the f ollowings -

a. Dose (0.5)

b. ' Contamination ' (0. 5)

c. Rad (0.5)

d. Dead Time = (0.5)

e. Half Value Layer (Half thickness)- (0,5)

DUESTION G.05 (1.00)

List three, by titIe, who must sign and date the radiation work - per mi t ? (1.

QUESTION G.06 (2.00)

One of the immediate action steps of the Si te Area Emergency pr ocedure 2 s ta cend an operator to west tower with a radiation. monitor.* What four setions muct this individual take?

(***** CATEGORY G CONTINUED ON NEX1 PAGE. +**++)

9t__BSDIGI190_c9 NIB 96_6Np_S8EEIY PAGE 13 QUESTIOr4 G.07 (2.50)

a. If the doce rate f rom- a radiation sour ce is 100 mrem /hr at 1 meter, what is the dose rate at 25 cm? Show work. (1.5)

b. How long could you be 25 cm from above source before exceeding your quarterly dose limit. (Ignore point source effect) (1.0) s

(**+** EtJD 04 L(ili:D OFC, b + + + * + . '

(****++**** on Erib UF t- Mil l i ke i A UI 4 ++***+**++*****)

j D s%IATIINIS , . t ,. : ,- ,

REACTOR THEORY RAll!ATION ' -

Fl.UtDS/ THERM 0/IIEAT TRANSFEB -

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P,e"I' = P,10 N = N,e = AlpsV = AapaVa i

y A = AN Q = AtV1 = AaVa l

t =8'+

p DAp ort = 10D -m g g*,-Wu = I*10 g l ,=

• g . . , ,TS,= ..,3 2.E , = E,,g + A E,,,,,4

= , y . .. . . . .. . . . .

R/hr e d feet = d2 "A I N =I~

• k=1 Point source 8e cpeg 1 - km Ind a - Iada a ya l

g 5*I~

Ind = lada - line R/hr x time - R source

• (

reduced for - turbine. SC pump, aossle.

"P** erifice. condenser e plPee RE

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• Rad a QF = Ren j u cys, flow a (dp Tis ,gg = gslo , grad L V8 ** a 6

• AI'deppler

• 8 mod

• 8 void Tb,g, + TisRad ** I*** * ***

• eet D 23 c head lose e Ap

+p.+8.+8Pu g 3 + P*

• P ambient F = pA = k'2E c  !

'Seron " rod 8 fuel + Apap hase

• api phase a E

, poisons) k = f(quality & Fressure) y,,,g,,, ,,,,g ,gg , ,

k, = kg + sk (speed)3e pressure MTH (speed)'s power 4k=k-1 Q = kAg? = hA&T = UAAT SW =

y =b N * %AT log b=a N * *A I i 16v y Q = cot I l E " 3.1 x IOne los x" = c log x att = m.c.,AT l l

log y"- = log x - log y AU = en s AT V

I e Its 1 l

. = ..

los my - log a + log y H=U+PV AS = S i Defect = Coeff x A. Parameter T

, pV = nRT l nh Tt

= r.m Ta CV + CaVa = C (V + Va)

6t__EB10G1ELEW_QE_BEOG10B_QEEB01100 PAbE 14 r,..

g ANSWERS -- UNIVERSITY OF MISSOURI -87/02/24-RIDGWAY, K. 1 I l t- .

l ANSWER A.01 (3.00)

a. Fast neutrons refer to those at high energy levels. ( 0. 5 ) ,

Prompt neutrons rufer to those released at the time

{

of fission. ( 0. b) i j.

b. Slow neutrono are neutrors at low energy levels. (0.5) l Delayed neutrons are those which appear at sonie timo '

after the finuion event due to fission product decey. (0.31

c. Activity refers to the rate of radioactive decay. (0,5)

Reactivity expresses the deviation of a reactor from the critical condition. (0. b)

(Will accept deviations f roin exact wording. )

l REFERENCE NUS Corp., Basic Nuclear Concepts ANSWER A.02 (1.00)

CPS 2 = 1-Keffi (0.5)

CPS 1 = 1-keff2 90 = 1-0.965 45 = 1-Keff2 i Koff2 = 1-0.35/2

= .9825 (0.5)

REFERENCE NUS Corp., Basic Nuclear Concepts ANSWER A.03 (1.50)

Activated ctructural material emi ts a high-ener gy gamma. (0.5) 1he gamma strikes a beryllium atom in the reflector (O.S), r esul ting is, the disinteur ation of the berylliune atom i rito two alpha pcrticleb and a neutrun (0.S).

REFERLNCE NUS Cor p . , Reactor Uperation l .

18t__EBING1ELEE_QE_BE8QIQB_QEEBBIlON- PAGE 15' ANSWERS -- UNIVERSITY.OF MISSOURI --87 / 02/24-RI DGWAY , K.

4 ANSWER-~ A.04 (2.50) ,

a.' Momentary formation of small. bubbles on the heat. transfer surface which are quici:ly swept into the subcooled liquid and condensed.

b. (heat. flux required to cause DND.)/(local heat flux)

c. Minimum of 1.2

' REFERENCE Ha:erda Summary 5-52 Nucluar Engineering Handboolc, p 9-76  :

. Tech Spec 2.1 ANSWER A.05 (1.00)

Decay heat is~the heat produced from the part of the fission eneroy released at none time after the fission event.

(0.5) By radioactive decay of the fission products. (0.5)

• REFERENCE NUS Corp.,. Reactor Operation

' ANSWER A.06 (3.00)

, a.. Xe is a daughter of "1" which is a daughter of le (a fission product). Xu also is a direct fission product. It can be removed by decay to cosium or "burnup" by absorbing a thermal neutron. (1.S)

b. Sin is a daughter of promethium (formed by fiusion and alno a daughter of neudymium). It can be removed by "burnup", but Sm is stable.

(1.5)

RE.FERENC.E NUS Corp., Reactor Oper a t i on s, 4

4 1

E t

I t

Ez__EE619 BEE _QE_ EGG 161IX_QE@l@N PAGE 16-

-87/02/24-RIDGWAY,.

ANSWERS -- UNIVERSITY OF MISSOURI. K.

ANSWER. B .' 01 (3.00) l 1. The' reactor vessel-is' located in a water filled pool, and provisions are made for entry-af' pool water into the. vessel to the extent necessary to make up boiling losses 1+ rom (decay heat) under conditions of.no coolant. circulation. System breaks (valve 550C/D)

~

inside-the pool would, of course, allow' free admittance ofLpool2 water

-to the primary system.

2. !Thefantisiphon system connects to exit line on the' invert loop which

'in 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.

3. Automatically actuated isolation valves 507A/B on.the-inlet and outlet lines.

(3 9 1.0 each)

. REFERENCE MURR Training Manual, p. I-8.

ANSWER B.02 (2.00)

If natural convection flange and pressure vessel cover are-removed.(1.0) or in operation with the reactor subcritical by a margin of at least 0.015 delta K. (1.0)

REFERENCE

'MURR Training Manual, p. 1-46 and 47

' ANSWER D.03 (2.00)

1. 'Close normally open containment building penetrations,.

2. Sound an alarm in the containment building.

.3.- Ener gi::e a rotating red beacon outside the airlock.

4.- Scram the reactor.

(4 0 .5 each)

REFERENCE MURR 1 raining Hanual , p. 11-54

.^ .

Ez__EE61MRE@_DE_E6Q16111_DE@l@N PAGE 17 LANSWERS -- UNIVERSITY OF MISSDURI -87/02/24-RIDGWAY, K.

~ ANSWER B.04 (3.00)

a. To provide 'suf ficient - ai r (under pressure) to. break a siphon of the primary coolant system in the event of'a.

pipe rupture.

b. (1) The system must be maintained at-a pressure greater than 27'psig.

- (2) The water level ~above the antisiphon. valves must be less than 6 inches.

REFERENCE SDP IV.3

' ANSWER B.05 (2.50)

a. LC925A vents the tank through vent valve 552A on low l evel in the vent tank. (0.5)

If water level continues to recede LC925B operates a parallel vent

' valve b528 (0.5) and initiates a rod-run-in (0.5).

b. Exhaust line diverges to parallel paths each containing a strainer, check valve, and solenoid valve (0.25). Exhaust line converges

.and passes through pressure regulator (0.25) and charcoal filter (0.25).and then to the pool sweep (0.25).

-REFERENCE MURR Training Manual, p. I-31.

ANSWER B.06 (2.50)

1. The. truck entry door closed and cealed.

.2. The utility seal trench filled with water to the depth required to maintain a minimum water seal of 4.25 feet.

3. All containment building ventilation system automatically-closing doors and automati call y-closi ng val ves ar e operable or placed in thc.

closed position.

4. The reactor niec han i c al equipment room exhaust system, including the particulate end halogen filters, in operable.

'5. The perconnel air 1ocL door oper ablc.

6. The most recent building leak test was satisfactory.  ;

(D G .60 each = 2.b) '

REFERENCE

'l ec hni c al Specification 1.15

t-

Gz__QENEB86_QPgBOI1N@_QHOBBGIEBl@llGS PAGE 181 ANSWERS -- UNIVERSITY OF MISSOURI -87/02/24-RIDGWAY,'K.-

4 ANSWER: ~C.01 (2.00).

e. -67 +/ .3 psig b.- 105 degrees F +/ S degrees F L c.c 120' degrees F +/- 5 degrees F

d. 29'-7" +/- 3"-

REFERENCE SOP /Ia14 ANSWER C.02 (3.00) a.' When the blades have reached a position within 2_ inches of the estimated critical position, discontinue pulling in gang.(1.0)

b. 30 second period used up to 1.0 MW - greater than 1.0 MW use 100 second period. (1.0)

c. Only.two (2) of four (4) required.

1. The period as indicated by both IRM-2 and IRM-3 must-indicate

~

not less than-35 sec.

_2. The WRM selector switch'must be in the 5 Kw red, scale pocition or above.

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

-4. The reg b1ade position must be greater than 60% withdrawn, such that 60% annunicator alarm is energized.

'(2 @ 0.5 each = 1.0)

REFERENCE

,50P/Il-1-1.I and P

ANSWER C.03 (1.00)

a. Master switch in " test" position (0.5)

b. Rod magnets are de-energized (0.5)

REFERENCE MURR HSR'9.S

,d

~

=G__iggNE866_OBE86 TING __QHORAQTEBISTICS- -PAGE ~19-

'.'ANSWERS - UNIVERSITY [Mr . MISSOURI' -87/02/24-RIDGWAY, K.

' ANSWER -C.04 (2.00) s.a 8 sec, scram; 10 sec, run-in (0.5)

-b. . 120%, scram; 115%, run-in .(0.S) c.- 78 psig, scram-(.25)

'd. 1.0'mr/hr scram-(.25) e._ 50 mr/hr,1 scram, (.25)

f. Reg Blade < 10% or bottomed, run-in (.25)

REFERENCE SOP /I Table IV ANSWER C.05 (2.00)

a. Operation of system after reactor shutdown required to remove decay heat.-

b.. Although decay heat will last much longer than 15 minutes, the power is low enough after 15 minutes. (So that it can be removed by other means - conduction, convection, and so on without overheating components.)

REFERENCE

' SOP _IV-2

~

ANSWER ~ C.06' (1.00)

Swelling of material produces internal stresses (0.5) in areas where'there in a rapid variation of flux level. (0,5)

REFERENCE MURR Training Manual, p. 1-17 6

ANSWER C.07 (2.50)

n. posi ti ve (0.b)

b. negative (0.5)

c. negative (0.5)

~

d. positive -(0.5)

e. positive (0.5)

REFERENCE MURR Hazards Summary Report, p. 4-14.

SOP /VIII-7.

c. ggNE866_QEEB611NQ_GU686GIEBISllgS PAGE 20 ANSWERS -- UNIVERSITY OF MISSOURI -87/02/24-RIDGWAY, K.

9

-Critical Parameters List 6

e

~ ~ ,

JQc__IN@lBWMENIE_@ND_CDNIBOLE 'PAGE' 21

ANSWERS - . UNIVERSITY OF MISSOURI- -87/02/24-RIDGWAY, K.

' ANSWER' D.01 ' ( 1. 50) .

An uncompensated ionization chamber detects gamma rays as well as neutrons. A compensated. ionization chamber is constructed so that~ gamma:

ray; induced currents are automatically subtracted f rom total current reading; thus'the resulting net current represent only neutron

' interaction..

. REFERENCE t t1URR Training Manual , 11-7.

ANSWER' D.02 '(3.00)

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

2. Prevents reactor operation with a vent tank level which could

-result in the introduction of air to the primary coolant system.

3. ' Provides assurance that.the introduction of air to the invert

. loop is sufficiently rapid to prevent siphoning action following a rupture of the primary coolant' piping.

REFERENCE MURR Training Manual, p. 11 65-66 ANSWER D.03 (2.50)

1. Regulating rod less than 10%

2. . Switch 1SS' to in or out position

3. Channel 4 (black) pointer less than red pointer

4. Loss of voltage to magnet (2K2O or 2K21)

5. Rod run-in (1LB or 1K9)

-6. Manual push button (Switch S12)

REFERENCE MURR Training Manual, p. 11-80 ANSWEli D.04 (1.00)

- Shim rods will automat i cal l y insert when the r equlat ing rod reaches the 20% withdrawn position. (0,5) Iha insertion will be a sufficient amount to drive the regulating rod to its 60% withdrawn position at which point the signal is terminated. (0.5) l.

i

.  ;. Ib.__JUEIBlit!ENIE 8ND_ CON 1BQLS PAGE 22

'. ANSWERS'--. UNIVERSITY OF MISSOURI -87/02/24-RIDGWAY, K.

REFERENCE LMURR Training Manual, p. II-81. _,

ANSWER D.05 (2.00)

M :gnet current 'is controlled by, the trip actuator amplifiers. .Two trip cctuator. amplifiers operate in paral 1el, each control 1ing current to two ongnets. -( 1. 0) The magnets are-de-energized by the trip actuator empliers in response to.a saignal from the scram logic circuit. ' ( 1. 0 ) (The-trip actuator-amp 1ifiera reset when the " Scram Reset" button ie. depressed with no incoming trip signals.)

REFERENCE MURR Training Manual,'p. 11-60

' ANSWER D.06 (2.50)

Startup interlocks

a. Master switch in the "On" position

b. " Rod Run-In" switch reset

c. No nuclear instrument anomalies

d. Shim rods bottomed and in contact with magnets e

e. Startup channul more than 1 count per second

f. Thermal column door c1osed (5 of 6 required - 0.5 pts.)

REFERENCE MURR Ha;rard Summary Report, p. 9-20 ANSWER D.07 (1.50)

Condition 111 omi nati on Audible Sigoal Normal (1) Off Ofi Alarm Input (2) F l at:h i ng Un Alarm input Acknowindged (3) On Pright Oft Return to Nor mal (4) On Dim Ofi

>Reuut (5) Uff

• Off Test (6) Flashing On (6 0 .25 each = 1.5) i i

4

D___10eIBUUEUIE_009_G9 BIB 96@ PAGE 23 ANSWERS -- UNIVERSITY OF MISSOURI -87/02/24-RIDGWAY, K.

REFERENCE HRS p. 9-19

\

O w ._-_ - - - - - - - -

T Ez__SOEEIY_GUD_EUEBWhUGX_EX@lhdS PAGE 24 ANSWERS -- UNIVERSITY OF MISSOURI -87/02/24-RIDGWAY, K.

ANSWER E.01 (3.00)

c. The 16A valve requires spring to close. (0.75) The 168 valve air to close.(0.75)

b. During a loss of power, the air to the open side of the valve is vented while air- is supplied to the close side. (0.5) Ihe air supply comes f rom a single stage air compretisor which has a ten gallon accumulator. (0.5) The accumulator assures air supply in available.

(0.5)

REFEREIJCE MURR Training Manual, p. 1-87 ANSWER E.02 (3.00)

a. A trip of the Automatic Control Period interlock circuit will prevent the regulating control rod from being operated in the automatic mode.

b. The system will automati call y res,et uhen the period becomes greater than the trip point of 35 seconds.

REFERENCE ,

MURR Training Manual, 11-32 Af1SWER E.03 (2.00)

Hi del ta P - possibl e cor e bl ockage. (0.7S)

Lo delta P - indicaten reduced flow (0.75).

both sorve as backup to pool coolant l ow f l ow sc r on- (O. S)

REFERENCE t1URR Training tlanual, 11-63. 11-70 T/S 3.3, pg. 4 ANSWEH E.04 (2.vo)

Wheri prennurl:er pr ect,ur e ex ceeds, lub7. of 70 pt,i. va)ve bCD wil1 opon to bleed oft nitrogen gas to the oftgas system. (0.5) If pruauuro exceeds 110% of 70 psi, pr essur i z er h14h press ure al arm veill, sound t ri the control room. (o,5) A reactor scram occurs at 1157. of 70 pui. ( 0. '. )

At ctill a higher pressure the encess prest,ure will be vented theough safety relief valve 537 to the offyas system. (O.S)

L_

. - . + , g.

.e

. Ei.__E9EEIL6ND_EdgBQgNQX_@XQIEd@ 'PAGE 25 1..

ANSWERS -- UNIVERSITY.0F MISSOURI -87/02/24-RIDGWAY, K. .

9

. . . i, :

1 REFERENCE

'.HURR Training Manual, p. 1-47.. f

$l'i

%i if7ij->

ANSWER E.05 (1.00) . ,,,g- "a (3)-and (5)

(2. required - 0.5 ptt.. each - Will subtract.O.5 pts, for each incorrect x 4'i answer givon up to value of question.) ,. g !

w ,, ,.

REFERENCE

MURR Training Manual, p. IV-5.

c r],

? f 2

ANSWER' E.06 (2.00) J .

J' O.

b.

emergency lighting system . (0. 5) reactor exhaust system (0.5) y

[ ..

l -c. reactor instrumentation (0.5) '

P '

d. air lock doorn- (0.5) , ,,

x, REFERENCE ^ $~ 7t-

MURR Technical Specification 4.5 '

I le~

- ANSWER E.07 I (1.50) l 1. the reactor control room "

2. the lobby control center l (2 0 .75 each) l /' ;r l REFERENCE I '.

FEP-1 p.1 f ,.

l l I t e:

/)

i

. .r 8

.+

e l

l?

l ,

l I

y j;

" w ", .. ..s. .

Ep.__.EIGNDOED eND_ EMERGE.NQy_QPEh613.HQ_tRQQEpyRES PAGE -26

. e:&

/l$NSWERS -E UNIVERSITY OF' HISSOURI -87/02/24-RIDGWAY, K.

[fl(&

?

4 .g y ANSWER I 01 (2.00)

'~

%p o. Faci 1ity Evacuation (0.25)

,, Reactor Isolation '(0.25)

$.. Fire >'O.25) if/I Pfedi cari! -(0.25)

'52curityj (0.25)

b. Unuuual. livent - (O. 25)

Al er t . '/f q. 25)

)7.

g .

Site Aruk Emergency (O.25)

R'EFERENCE FEPb ,

, SEP-1,' p. 1.

e -

g+

[,o[ i'

~

t/ . ANSWt? F.' 02 (1.00) y

. V) b.

> False

b. True '

4 REFERENCE SDP I ,+ 1' 0 '

N , <' '

. { \

[i- cf ANCWER F . Ot". (1.00)

' ,r :

1. -Scram It m roactor

~

2. - Shut dtderi the pool system, leaving the primary and secondary on line REFERENCE i<i.,;

-, REP-14-1 l ;I .

1'

% ' ANSWER F.04 (3.00)

J .,

"/ j If 546 A/It opens during operation, a flou path for the primary coolatst.

i.bypanning the core in ostablished (about 30 - 33% of original core l fIow). ( 1. O) .

1 hic reduced fIow wi11 not 1ead to core damage as 1ong as l

normal temperraturo, power, and pronnure are maintainud. (1.0) This' reduced' flow ratu, however, decreases our saf ety margin fr om the saf ety

, ,_ limit urvus by about 60%. (1.0)

L

.\

t."

! {/

. r. .

y ..

O f .p *' N

.M ' . % h {

e

, Et__SIONueBD_9ND_EDEBQENQY_QEEB611NQ_EBQQEQQBES PAGE 27

. .i=

ANSWERS -p UNIVERSITY OF MISSDURI -87/02/24-RIDGWAY, K.

3 REFERENCE-REP-19-1 1

1 ANSWER - F. 05 , (3.00)

c. 1. Veri f y that the r ukctor han scrammed as indicated by the:

i nst r ument a t i on .

1. 2. Verify that all shim ~ rods have bottomed 'as indicated : by .

console lights. . .

3. Verify that the containment has sealed as indicated by the ventilation dnor and the exhaust valve lights.

4. - Insure all personnel are cleared from 5th, 4th, 3rd, and 2nd levels of the containment building and exit via personnel airlock doors.

5. If the assistant duty operator.is not known to be in containment, the duty operator shall also insure that all personnel are cleared from the beam port floor.

(4 of 5 required - 0.5 pts. each)

b. The assistant duty oper ator shall ascertain that all personnel are cleared from.tbe beam port-floor area (0.5) and exit via personnel

'. airlock door. ( 0. 5) e

, REFERENCE FEP-1, pp 2,3  ?

ANSWER ~ F.,06 (2.00) i 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~

result in the actuation of a low sump level trip. (1.0)'After one pump is etarted,.it is necessary to wait at least 10 minutes before starting the second pump. (1.0)

REFERENCE SOP /VI-3

-ANSWER '

F.07 (2.00)

L 1. Immediately. shutdown the reactor. '

2.- Notify the shift Eupervisor 3 .' Insure all doors are secured.

4. Noti f y the Uni versi ty police.

5. Facility evacuation or partial evacuation.

(4 of 5 (o v.5 each)

%w,-i- - , - y-- - - - --y --- 7y.- pr-9--- ---

E,_;_EleNQeBD_eNQ_E ME B@ENGLQBE861 [NG_E80C EQUBg@ PAGE 28'

ANSWERS.-- UNIVERSITY'OF' MISSOURI -87/02/24-RIDGWhY, K.-

. o .-

' REFERENCE REP'22-1 e

LQt__8001011QN_CQNIBQL_8NQ_SOEEIY PAGE- 29' ANSWERS -- UNIVERSITY OF M4SSOURI. -87/02/24-RIDGWAY, K.

W ANSWER G.01 (1.50) r-

1. - ' Sludge. settlement

2. Cuno' filters

3. = Chemical Precipitant Treatment--

(3 O~.50 uach)

REFERENCE SOP /VII-44 ANSWER G.02~ (2.00)

No. The unit REM already considers the different effects. REM i n a .

biological unit thus different radiations causing the same dose in REM-should have the same effect.

REFERENCE NUS Corp., Radiation Protection.

ANSWER G.03 (3.00)

a. He does not exceed 3 REM per quarter. (1.0)

b. His radiation history is known and recorded on NRC Form 4. (1.0)

c. The dose rate received- when added to his radiation history .does not exceed 5(N-18) . (1.0)

REFERENCE 10 CFR 20.101 O

sGs__B89101100_G9H1896_6UD_Wethl1 2 PAGE 30 AN5WERS -- UNIVERSITY OF NISSOURI' -87/02/24-RIDGW4Y, K.

0-5:

. ANSWER: G.04 (2.50) z fa. Dose - The quantity of radiation absorbed per unit mass by the _ body or by any portion of - the body. - (0.5)

b. . Contami nation -_ The deposi ti on of radioactive material

~ in any place where it is not desired, particularly if its presence is' harmful-to personnel. (0.5)

c. Rad --A measure of the dose of any ionizing radiation to body tissues in terms of_the energy _ absorbed per unit mass of the. tissue. 100 ergs /g tissue. (0.5)

~d. . Dead Time - The time-when a detector operating in the Geiger-Mueller region of the curve is insensi ti ve to' incoming radiation due to the process causing the anode to be engulfed by positive ions. (0.5) e.-.HalfLValue Layer - A term used to represent _ shielding.

A half.value layer.of a material, HVL, reduces the:

i..censity of incident radiation b'y a factor ~of 2.

Also called. half thickness. (0.5)

' REFERENCE

NUS Corp. , Radiation Protection 4

ANSWER G.05' ( 1 . 0 0 )'

- a. ' Job supervisor (.34)

b. Health Physics (.33) c.1 Shift Supervisor (.33)

REFERENCE F MURR SOP I.4.7 ANSWER -G.06 (2.00)

+

Any four of the followina (0.5 each):

1. Verify the_ background radiation at the stack monitor.

2. Verify-control room readings.

3.-Mark initial needle posi tion on analog display with time for future analysis if control racin di spl ay becomes inaccessible.

4. Verify that'the flow rate through the monitor i s tietween 6 and 8 S[iM.

l 5. Have stack filters analyzed for nuclides. -

. REFERENCE SEP - 4, i mniediate action step 5 t- ya4 t+-, --

Er a- ee f -*+es -r me-q-u-=- -gT+gs ---qr ee -w er m - >g -

+m-y-e p$ > w e w -? w F 7 = de f5-TT- T7

G s._ B O D .1 8 I 1 9 N _.G Q N I B O L___,0 N Q _,5 0 E g l y pAsk 32.

Aa ~ ANSWERS'-- UNIVERSITY'OF MISSOURI -07/02/24-RIDGWAY,.K.

c. ,

of ,

. ANSWER: G. 07 (2.50)

.c.. . 11d12~=L12d22~

'(100' mrem /hr) (1 m)2'= 12-(.25 m)2 1600 mrem /hr u I2' .

(1.5)

.. 1250 mrem /1600 mrem /hr = .78.hes.

-b'- .

3000 mrem /1600 mrem /hr = 1.875 bes. (1.0)-

(Either-answer accepted)-

' REFERENCE-HUS Corp.~ Radiation ~ Protection, p. 3.2-1

.10:CFR 20 f

.),

I, .

e 9

4 e

4 I

i J

e i

, M/Ab l tK LUt'I U. S. NUCLEAR REGULATORY COMMISSION

'o SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _yNIVERSITy_QE_ MIS @OUBl__ '

REACTOR TYPE: _ TEST _____________,,______

DATE ADMINISTERED: _BZf92/2d________________

EXAMINER: _RIDGWAY1_II:._____________

CANDIDATE: _________________________

INSIBygligNS_lO_GONDID91El Use separate paper for the answers. Write answers on one side only.

Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours after the examination starts.

7. OF CATEGORY  % OF CANDIDATE'S CATEGORY

__YBLUE_ _I910L ___SggBE___ _yGLUE__ ______________CBIEGOBy_____________

_12t50__ _12tDQ ___________ ________ H. REACTOR THEORY

_29t99__ _2919Q ___________ ________

I. RADIOACTIVE MATERIALS HANDLIN3 DISPOSAL AND HAZARDS

_22t99__ _22t99 ___________ ________ J. SPECIFIC OPERATING CHARACTERISTICS

_1Et99__ _le r gg ___________ ________ K. FUEL HANDLING AND CORE PARAMETERS

_29tE9__ _29159 ___________ ________ L. ADMINISTRATIVE PROCEDURES.

CONDITIONS AND LIMITATIONS 100.00  % Totala Final Grade All work done on this exami nation is my own. I have neither given nor received aid.

Candidate's Signature

e NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2. Restroom trips are to be l'imited and only_one candidate at a time may leave. You must avoid all contacts with anyone outside the examination-room to avoid even the appearance or possi bility of cheating.

3. Use black ink ~or dark pencil gdly to facilitate legible reproductions.

4. Print your name in the blank provided on the cover sheet of the examination.

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

1

6. Use only the paper provided for answers.

7. Print your name in the upper right-hand corner of the first page of gech section of the answer sheet.

8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write gnly gn gne sidg of the paper, and write "Last Page" on the last answer sheet.

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

10. Skip at least thrgg lines between each answer.

11. Separate answer sheets f rom pad and pl ace f inished answer sheets face down on your desk or table.

12. Use abbreviations only if they are commonly used in facility 11 t etetute.

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. Partial credit may be given. Therefore, ANSWER ALL PARIS OF Tilt OUESTION AND DO NOT LEAVE ANY ANSUER HLANK.

16. If parts of the enamination are not clear es to intent, ask oues*.lenu of the haganet only.

17. You must sign the statement on tnc cover m er:t that i ndic at es +hst the work is your own and you have not recei ved or been given ase,istance in cc.mpl eti ng the ex ami nat i en. ihis nue! De done after the examinati on has been completed.

t 18.-When you complete your examination, you shall:

a. Assemble your. examination as follows:

(1) E::am questions on top.

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

(3) Answer pages including figures which are part ci t he answer ,

b. Turn in your copy of the examination and all peces usec: to an st* r the examination quest ions.

c. Turn in all scrap paper and the balance of the paper t. h a t you did not use for answering the questions.

d. Leave the examination area, an defined by the exan.iner. If after leaving, you are found in this area while the examination is still in progress, your license may be deni ed or revoked.

e

m -.

H __BE991Q6_luggBy> PAGE lL 4

QUESTION H.01 (2.00)

a. List the two major negative reativi?.y coef ficients which (1.0) can halt'the rapid power escalation following a positive step reactivity insertion.

b. What.are their values? (1.0)

QUESTION H.02 (2.00)

Explain or define the following terms.

a. Shutdown margin.- (1.0)

6. Beff (1.0)

DUESTION H.03 (1.00)

What is decay heat and how is it produced? (1.0)

DUESTION H.04 (1.00)

A reactor has a count rate of 45 when it has a Keff of 0.965. what 'is the Kef f of this reactor when it has a count rate of 907' Show your work.

QUESTION H.05 (3.00)

Briefly explain the differences between (3.0)

a. Fast and Prompt neutrons.

b. Slow and Delayed neutrons,

c. -Activity and Reactivity, i

OUESTION H.06 (1.00)

What effect does a moderator temperature increase have on control rod worth? (1.0) Explain your answer.

QUESTION H.07 (2.00)

What four parameters are used to determi ne the reactor safety l i mi t curve?'

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

~B___BEGGIQB_IBE98Y PAGE 2

. w.

DUESTION H.08 (1.50)

Explain.how source neutrons are' generated at the MURR.-

OUESTION .H.09 (2.00)

.a.- Explain what the difference is between k-infinite and ..

-R-ef f ecti ve. . - ( 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-$ffective?- (0. 5) .

.' QUESTION H.10 ( 1 '. 00 )

a. What' pressure in psig corresponds to 65 psia? (0.5) b.

~

What is.the saturation temperature corresponding to'65 psi'a? (0. 5) -

QUESTION H.11 (3.00)

Xenon is the major fission product poison in your reactor,

a. How is it produced? (Include pertinent half-life.) (1.0) b.- How is it removed? (Include pertinent half-life.) (1.0)

c. Why does xenon reactivity peak after a trip from high power? (1.0)

(***** END OF CATEGORY H ***++-)

-li__B09199GIIME_dGlgBlGb@_U6NQLING_pl@EQ@@6_@ND_M6188QS. PAGE 4' r

DUESTION 1.01 (2.00)

List four (4) major possible hazards. involved with beamport .( 2. 0) experiments.

. OUESTION I.02' '(4. 00)

Radioactive isotopes that are common from the operation of a research-reactor are N-16, A-41, H-3 and Na-24.

a. .For each of the above, give the source, where.it would be found, and the half-life. (0.2 each, total 2.4)

b. What, if any, precautions are taken to reduce the effect of these isotopes at MURR? (0.4 each, total 1.6)

OUESTION I.03 (1.00)

Explain why iodine-131 is the limiting isotope in many (1.0) accident analysis.

QUESTION .I.04 (2.00)

.Does the biological effect of a 100 REM depend on whether it is a neutron or a gamma dose? Explain. (2.0)

OUESTION I.05 (3.00)

According to 10 CFR 20, an individual in a restricted area

.may be allowed to receive a whole body dose of radiation greater than the 1.25 REMS per quarter when three conditions are met. What are these conditions? Assume non-emergency conditions. (3.0)~

OUESTION 1.06 (2.50)

Define or explain the following:

a. Dose (0.5) -

b. Contamination (0.5)

c. Rad (0.5)

d. Dead Time (0.5)

e. Half Value Layer (Half thickness) (0.5)

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

li__B89196CIlyE_dGIEBIGLB_U8UQLINg_Q1gEQS6LiGNQ_U8Z6BDS PAGE- *

..D QUESTION I.07 (1.00)

-What practice is carried out in your facility to reduce radioactivity released to the sewer?

QUESTION I.OB (1.00)

Li st three, by title, who must sign,and date the radiation work permit? ~(1.

QUESTION I.09 (2.00)

One.of the immediate action steps of the Site Area Emergency procedure is to send an operator to west tower with a radiation monitor. What four actions must this individual take?

QUESTION I.10 (1.50)

List three of the five Facility Emergency Procedures.

r a

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

e- . -.

.~ _

,,y<e.

JI__SEERIEIG_REEB8IING_gd8B8GIEBl@Ilgg PAGE 6 QUESTION J.01 (3.00)

a. What is the purpose of the Antisiphon System? (1.0) b.~ What two conditions must be met to perform its function? (2.0) j.

QUESTION J.02 (2.00)

Control Blade-Operation

a. Why.are you required to keep the shim rod difference (1.0) within.one inch, above 100 kw? Explain,

b. The shim blades shall be capable of insertion to.the (.5) 20 percent withdrawn position in ----- . (time)

c. How often shall the drop time of each of the four (.5) reactor shim blades be measured?

OUESTION J.03 (3.00)

a. What is the function of the pressurizer system? (0.5)

6. Driefly describe.the automatic operation of the pressurizer. (1.0)

c. What scram f unctions are initiated f rom ' the pressurizer system?

(1.5)

-QUESTION J.04 (2.00)

Reactor Fuel

a. The average fuel burnup shall not exceed ------- MWD per (0.5) element of uranium-aluminum alloy type fuel or -------

MWD per element of UA1x intermetallic fuel. (0.5)

b. Why do we limit the fuel burnup? (1.0)

DUESTION J.05 (3.00)

. What are the upper (max) limits for the following parameters during steady state operation? (0.5 each) Explain the reasons for the limit.

(1.0 each)

a. Primary coolant pressure

b. Pool temperature

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

i

.- _- .. n - _ ,_ ,

4t__SEEQ1Elg_QEgg@IlNG_gd@B@gIEgl5I195 PAGE 7

-s OUESTION J.06 '(2.00)

.What are the four major loads that the emergency generator supplies? (2.0)

OUESTION J.07 (1.00)

What two conditions.when satisfied will bypass the rod withdrawal prohibit? (1.0)

QUESTION J.08 (3.00)

The reactor shall be considered secure whenever it contains insufficient fuel in the reactor core to establish criticality.with all' control rods removed.

Name three of the five conditions that will also' meet the reactor secured criteria? (3.0)

QUESTION J.09' .(1.00)

-True or False.

The control blades'cannot be operated in gang control except during hot

-startup approach to critical following a scram. Explain your answer.

(2. 00) -

. QUESTION 'J.1O

' Facility Emergency Procedure. FEP-2 lists five events which result f rom a Reactor Isolation alarm. List four of these. (0.5 each)

(*+**+~ END OF CATEGORY J *****)

e Ks__gyg6_HONg(ING_@Ng_ggBE PARAMETERS PAGE E-4-

QUESTION K.01 - (3. 00) a.. List three of the four means of determining that a fuel element rupture has leaked into the primary coolant. (1.5)

b. ' Describe how a leaking or ruptured fuel element can be identified. (Include HP monitoring requirements) ( 1. 5) -

OUESTION K.02 (2.00)

a. What precautions must be followed when loading fuel into (1.0) the core to assure that the fuel is properly seated?

b. How can a positive latch of fuel element be achieved (1.0) with the fuel element tool?

OUESTION K.03 (3.00)

State _the SOP setpoint for the following scrams: (0.5 each)

a. ' Period.

b. Primary coolant flow.

c. Reactor inlct temperature.

d.- Reactor outlet temperature.

e. Pool coolant flow.

f. Pool level.

QUESTION K.04- (2.00)

List the two requirements in your technical specifications which apply to fuel storage-at the MURR. (2.0)

OLIESTION K.05 (2.00)

Why are all beamport evolutions such as drai ning, fi13ing, or evacuating the port carried out by reactor operations personnel?

QUESTION K.06 (1.00)

What people by job title are required to be present during fuel handling? (1.0)

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

'g. Fyg(_HONQLINQ_8NQ_GQBE_B68@MgIEB@ PAGE- 9 QUESTION K.07 (1.00)

~

-Why is.the SRM scaler'and chart recorder turned on and the fission chamber. inserted _to the 1000 counts per second position prior to moving' fuel in or out of the reactor?

QUESTION K.'OB .(1.50)

True or False.

a._ Containment integrity is required when unirradiated fuel is being handled. (0.5)

b. Fuel, new-or irradiated, shall only be handled one element at a time. (0.5)

c. Fuel elements should be moved with the small end forward to reduce the possible area of contact. (0.5)

OUESTION- K.09 (2.50)

a. Why are additional limitations placed on-a samples to be irradiated in the flux trap? (1.0)

b. List-three of the seven limitations placed on flux trap samples by SDP VIII.2.3. (1.5)

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

. Li__0Dd1NigIB8Ilyg_Eggggggggg2_ggNQlligNS_@NQ_LidlI@llgNg PAGE IC

-s

b QUESTION L.01 (3.50)

-a. List three tags and explain their meanings. (1.5)

6. Who by title must fill out and attach the tags and the (0.5) tag log?

c. Who by title must approve tags before they are removed? (0.5)

d. When the tags are removed what information is recorded (1.0) in the log.

QUESTION L.02 (3.50)

a. Why do we set the safety limits and the limiting (2.0) safety system settings?

b. List the values of.the safety limits in the Mode I and (1.5)

'II operations.

Primary Coolant Flow Reactor Inlet Water Temperature Primary Coolant Pressuriner Pressure QUESTION L.03 (2.50)

List five conditions that must be satisfied for reactor -(2. 5) containment integrity.to exist.

• OUESTION L.04 ( .50) 2 True or False.

Operations affecting changes.in core reactivity, other than normal steady i.e., refueling, startup, etc. will be directly state power control, supervised by a senior operator. True or False.

DUESTION L.05 (1.00)

Who can authorire reactor startup following a scram where the ceuse has not been determined but all systems are found to be normal.

QUESTION L.06 (1.50)

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

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

bi__0Dd1NISIEBIlyEiEBQGEQUBES2_ggNQ111gNS_GNQ_LidlIBIlgUS- PAGE 11 4

.: i-i:

QUESTION L.07 (1.50)-

.What is'the minimum' staffing requirements during reactor operations?

~

- QUESTION L.08 (1.00)

The cause for any difference greater than _______ percent between the primary and secondary calorimetric calculations should be determined.

(1.0)

QUESTION L.09 (2.00)

List the three emergency classes for your facility in order of severity, least severe first.

QUESTION .L.10 (2.00)

a. A volunteer may be authorized to receive up to _______ Rem to save a life (0.5) and up to ______ Rem to save vital equipment. (0.5)

b. List two of the three personnel selection considerations for emergency exposure volunteers. (1.0)

QUESTION . L .' 1 1 (1.50)

Reactor Emergency Procedure, REP-13, Loss of Secondary Flow. states five immediate operator actions. List three of these.

'l l

(***** END OF CATEGORV L +****)

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

t.t!IIATilg . .

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Hz__BgACIDB_IMEQBL PAGE 12 s.,

ANSWERS -- UNIVERSITY OF MISSOURI -87/02/24-RIDGWAY, K.

= ANSWER H.01 (2.00)

a. Void coefficient- (0,5) and temperature coefficient (0.5)

6. -2.39 x 100-33 delta k/ percent void. (0.5)

-7.0 x 10[-53 delta k/ degrees Fahrenheit (0.5)

REFERENCE Technical Specifications 3.1, Critical Parameters Sheet ANSWER H.02 (2.00)

a. S/D margin = 1-Keff or A measure of the reactivity which must be added to a shutdown reactor to make it just critical. (1.0)

b. Beff is the effective decay constant for delayed neutron precursors. or Beff = 0.693 / T 1/2. Where T -1/2 is the effective half-life of all the delayed neutron (1.0) precursors.

REFERENCE NUS Corp., Basic Nuclear Concepts ANSWER H.03 (1.00)

Decay heat is the heat produced from that part of the fission energy released at some time after the fission event (0.5) By radioactive decay of the fission products.

(0,5)

REFERENCE' NUS Corp., Reactor Operations ANSWER H.04 (1.00)

CPS 2 = 1-Keff1 , (0.5)

CPS 1 1-Keff2 90 = 1-0.965 ,

45 1-Keff2 Keff2-= 1- 0.35/2 = 0.9825 (0.5)

dz__8EOCIOR THEQRY' PAGE. 10 ANSWERS - UNIVERSITY OF MISSOURI -87/02/24-RIDGWAY, K.

+

. r.

REFERENCE NUS Corp., Basic Nuclear Concepts ANSWER H.05. (3.00)

a. Fast neutrons refer to those at high energy levels. (0.5)

Prompt neutrons refer to those released at the time of fission. (0.5)

b. Slow neutrons are neutrons at low energy levels. (0.5)

Delayed neutrons are those which appear at some time after the fission event-due to fission product decay. (0.5)

c. Activity refers to the rate.of radioactive decay (0.5);

. Reactivity expresses the deviation of a reactor from the critical condition. (0.5)

REFERENCE NUS Corp., Basic Nuclear Concepts ANSWER -H.06 (1.00).

Control rod worth increases.(0.25) As moderation is decreased and the probability of leakage into a control rod increases, the effectiveness of the control rods increase. (0.75)

REFERENCE NUS Corp., Basic Nuclear Concepts

_ ANSWER H.07 (2.00)

1. Pressuriner pressure

2. Core flow rate

3. Core power

4. _ Inlet water temperature (0.5 each)

REFERENCE TS Figure 2.2 O

Hz__BEGGIQB_IBEQBY PAGE ~ 14!

LANSWERS --fuNIVERSITY OF MISSOURI -87/02/24-RIDGWAY,-K.

e ANSWER H.08 (1.50)

Activated structural material emits a high-energy gamma. (0.5)

The gamma strikes a beryllium atom in the reflector (0.5), resulting in-

- the ' disintegration of - the beryllium atom into two alpha parti cles and a -

neutron (0.5).

REFERENCE Hazards Summary 13-229 ANSWER H.09 (2.00)

a. .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 = 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 NUS Corp., Basic Nuclear Concepts ANSWER H.10 (1.00)

a. 50 psig - (0. 5 )

b. 297 degrees F (0.5)

REFERENCE Steam Tables e

e

I~ , U___BEOGIQB_IBEQBY PAGE 1*

. ANSWERS -- UNIVERSITY OF MISSOURI -87/02/24-RIDGWAY, K. -.

TC- l

.N

• F ANSWER H.11 (3.00) ,

\

! r

a. (1)- Directly .f rom fission. (.25) 3, (2) From beta decay of fission products iodine-135 and' ,

3 te11urium-135. (0.375). Tellurium-135 decays to iodine-135 (20 seconds half-life) which then decays to f 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) e#m

(

b '. (1) Burnout by neutron absorption.(.333) i (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)

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

REFERENCE '

NUS Reactor Operations, Module 3, Unit 10 -

"v

". x

/

t

)

e

m ._. . .

,Is__B89198CIINE_M8IEBl@(@_H8NQLINQ_QlSEQS@(_8ND_H8Z8BDS PAGE 16 c ANSWERS -- UNIVERSITYf0F MISSOURI -87/02/24-RIDGWAY, K.'

s.

.]- V 3 '

'{"{(l ANSWEY. .>I.01 (2. 00 ) -

1. ChanDes in reactor reactivity due to beamport activities such as draining or flooding a beamport.

2. Exposure of personnel to radiation as a result of

'" movements of shielding or inadequate shielding.

3. Release of radioactive gases such as Ar-41 which are ptoduced in the beamport.

4. A} production of explosive or toxic materials in the bepmpo'rt,.s in U REFERENCE SOP /VIII-19.

yj :

, ANSWER I.02 (4.00) w

a. Q-16 En,lp3 N-16; Primary and pool-coolant water; 7 seconds (0.2 each:

A-40 + n --- A-41; Air space near reactor and primary water with' dissolved air; 1.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> (0.2 each)

H-2;+ n ,c H-3; Primary coolant water and air above

pool; 12 years. (0.2 each) cll'Na-23 + n --- Na-24; impurities in coolant; 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> (0.2 each) b.$ N-16 = Hold-up tanks in primary coolant (0.2) and demineralizer. (0.2)

., A-41 =1 Ventilation or beam-ports and T-column-(0.2): ventilation and u and dilution of_A-41 in the pneumatic system. (0.2)

H-3 =. Vents at top of-pool. (0.4)

Na-24 = Demineralizer system (0.2) and shielding (0.2)

I

'EEFERENCE z NUS Corp., Basic Nuclear Concepts S

-, ,z : , -ANSWER I.03 (1.00)

IodYse-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.

REFERENCE g4LS Corp., Radiation Protection -

t O k

\

,,.- ,\')

A. . _ _

4 Iz__B8DlD8GI1ME_MOIEB1865_HONDLING_DIEEDS86_8ND_UBIBBDS PAGE 17 ANSWERS -- UNIVERSITY OF MICSOURI -87/02/24-RIDGWAY, K.

ANSWER I.04 (2.00)

No.- The unit REM already considers the different effects. (1.0)

REM is a biological unit thus different radiations causing the same dose in REM should have the same effect. (1.0)

REFERENCE NUS Corp.,-Radiation Protection ANSWER I.05 (3.00)

a. He does not exceed 3 REM per quarter. (1.0)

6. His radiation history is known and recorded on NRC Form 4. (1.0)

c. .The' dose rate received when added to his radiation history does not exceed 5(N-18). (1.0)

REFERENCE 10 CFR 20.101 ANSWER I.06 (2.50)

a. 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)

c. Rad - A measure of the dose of any ionizing radiation to body tissues in terms of the energy absorbed per unit mass of the tissue.- 100 ergs /g tissue. (0.5)

d. Dead Time - The time when a detector operating in the Geiger-Mueller region of the curve is insensitive to incoming radiation due to the process causing the anode to be engulf ed by posi tive ions. (0.5)

'e. Half Value Layer - A term used to represent shielding.

A half value layer of a material, HVL, reduces the intensity of incident radiation by a factor of 2.

- Also called half thickness. (0.5)

' REFERENCE -

NUS Corp., Radiation Protection

g 1z__B8DIDeG11YE_M01EB10LE_B6MDLING_DIEEGE0k AND_B@l@BQg PAGE 18

;< ' ANSWERS '-- UNIVERSITY OF , MISSOURI -87/02/24-RIDGWAY, K.

' ANSWER I.07' (1.00)

Liquid wastes ar e retained as long as possible to maximize radioactive r decay. L( 1. 0)

REFERENCE- l SOP.VII.B.~3 ANSWER I.08 (1.00)

a. Job supervisor (.34)

b. Health Physics (.33)

c. Shift Supervisor (.33)

REFERENCE MURR SOP I.4.7 ANSWER I.09 (2.00)

Any four of the following (0.5 each):

1. Verify the background radiation at the stack monitor.

2. Verify control room readings. ,

3. Mark initial needle position on analog display with time f or future analysis if control room display becomes inaccessible.

4. Verify that the flow rate through the monitor.is between 6 and 8 SCFM.

5. Have stack filters analyzed for nuclides.

-REFERENCE SEP 4, immediate' action step 5 ANSWER 1.10 (1.50)

1. Facility Evacuation Procedure

2. Radiation Isolation Procedure

3. Fire Procedure

4. Security Procedure

5. Medical Emergency Procedure L. (Any three, 0.5 each) -

REFERENCE FEP Table of Contents L

it__EEEGIEIG_QEERATINQ_QHABAQTEBigTICE PAGE ic-31

..- l ANSWERS -- UNIVERSITY 1DF MISSOURI -87/02/24-RIDGWAY,-K.

4

~ ANSWER .J.01 (3.00)

a. To provide sufficient air (under pressure) to break a-siphon of the primary coolant system in1the event of a pipe rupture. (1.0)

b. (1)- The systemLmust-be maintained at a pressure greater; than 27 psig. (1.0)

- ( 2)' The water level.above the antisiphon valves'must be

-less than 6 inches. (1.0)

REFERENCE-SDP IV.3 ANSWER J.02 ' ( 2. 00 ) '

a.- It can provide a restriction on the-maximum neutron flux tilting that can' occur in the core to insure the validity of _ the power peaking f actors. - ( 1. 0 ) -

b.~ Less than 0.7 seconds. (0.5)

- c .- Every 3 months. (0.5)

REFERENCE Technical Specifications-3.2 and 5.3

- ANSWER. J~03

. (3.00)

a. Maintains a constant reactor coolant-inlet pressure. (0.5)

b. Constant pressure is maintained by automatically feeding in or-bleeding out nitrogen gas. (0. 5) ' Pressuriner-water level is automatically maintained by pumping.in or draining out water. (0.5)

c. 1. ,High pressuriner pressure (0.5)

2. Low pressuriner pressure (0.5)

3. Low pressuriner level (0.5)

REFERENCE Training Manual o

'az__SEEGIEIG_DEEB@l1N@_GB@BBGlEBISIlGS PAGE 20-m ' ANSWERS -- UNIVERSITY OF MISSOURI -87/02/24-RIDGWAY, K.

ANSWER oJ.04 (2.00)

La.. 70; 150 .(0.5 each)

b. The fuel burnup limits restrict the peak atom percent burnup to' values correlated to result in legs than a 10~ percent swelling of the fuel plates. -(1.0)

REFERENCE Technical' Specifications 3.8-ANSWER J.05 (3.00)

a. 110 psig-(maximum) (0.5)

To assure that the system design pressure of 125-psig is not exceeded. (1.0)

b. 120 degrees Fahrenheit (maximum) (0.5)

To assure the adequate cooling of pool components during all modes'of operation. (1.0)

REFERENCE MURR Technical Specification 3.4 ANSWER J.06 (2.00) l-

a. emergency lighting system (0.5) l

b. reactor exhaust system (0.5) [.

~

c. reactor instrumentation (0.5)

d. air lock doors (0.5) i REFERENCE MURR Technical Specification 4.5 L- ANSWER J.07. (1.00)

L i

a. Master switch in " test" posi tion (0.5)

6. Rod magnets are de-energized (0.5)

REFERENCE MURR HSR 9.5 l-f l

l- .

l

.~

Jz__EEEGIEIG_DEEBBIING-CHARAQTERIEIIGEL PAGE '21 ANSWERS -- UNIVERSITY OF1 MISSOURI -87/02/24-RIDGWAY,: K.

1

[ ANSWER J.08 (3.00)

>a.

All shim rods-are fully 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. (1.0)

2. A licensed operator is present in the Control Room and the dummy load control rod test connectors.are installed. (1.0)

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.

e. The reactor pressure vessel cover is secured in position and no work is in progress on the pressure vessel or its supports.

Any three at 1.0 each.

REFERENCE MURR Technical Specification 1.20 ANSWER J.09 (1.00)

False. (0.4) (Gang control can be used while critical for reducing power (0.2) Shutting down the reactor (0.2), or as part of the automatic.

shimmi ng operation. (0.2)

REFERENCE SDP I.4.3.D and E.

ANSWER J.10 (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.

e. .The flashing red light exterior to the personnel air lock i.s on.

(Any (4) four)

REFERENCE FEP-2

m

<Kt__EQEL_H6NQLINQ_@ND_CQRE PARAMETERE PAGE 2;

., ANSWERS -- UNIVERSITY;OF MISSOURI -87/02/24-RIDGWAY, K.

' ANSWER- K.01 (3.00)

a. 1. -Checking fission product monitor.

2. Observing off gas recorder.

3. Sampling and analyzing primary water.-

4. Conducting radiation surveys in areas containing primary coolant.

(Any three, 0.5 each) I'

b. 1. Have the HP personnel move the portable gaseous and particulate monitors to the reactor bridge for continous monitoring. HP personnel will be present. (0.5)

2. Move four elements from the core to the "X" basket and the "Y" basket separately. (0.5)

3. Draw a grab sample from above each element and give to lab group for analysis.

REFERENCE-REP-20 ANSWER K.02 (2.00)

a. Never lift the air-operated fuel handling tool off the element; allow it to float off. (1.0)

b. Positive latch is achieved only when the. red plunger on the air-handling tool is fully retracted and flush with the cylinder. (1.0)

REFERENCE i SDP 11-2.1  !

i i,

ANSWER K.03 (3.00)

a. 8 seconds. (0.5)

b. 1725 gpm. (0.5) ,

c. 150 F. (0.5) j

d. 170 F. (0.5)

e. 490 gpm. (0.5)

f. 23 feet. (0.5)

REFERENCE -

SOP I, Table IV i

I

'Ez__EMEL_d6dELING ANQ_QORE_PABAMETE8@' PAGE- 23"

-:o-4 ' ANSWERS -- UNIVERSITY OF MISSOURI -87/02/24-RIDGWAYf K.

ANSWER' K.04 (2.00)'

a. -It shall be~ stored in geometry such that the-calculated Keff.is less than O.8 under all conditions of moderation. (1.0) b.. Irradiated ~ fuel elements shall be stored in an

, array which will permit sufficient natural convection cooling such that the fuel element

. temperature will not exceed design: values., (1.0)

REFERENCE MURR Technical Specifications 3.8 ANSWER K.05 (2.00)

NRC regulations require that any apparatus and mechanisms other than reactor-controls which may effect the reactivity or power level-(1.0) shall be manipulated only with the knowledge and consent of a licensed operator. (1.0)

REFERENCE SOP VIII.4.1.B.

ANSWER- K.06 (1.00)

a. Senior Reactor Operator (0.5)

b. Reactor Operator or trainee (0.5)

REFERENCE MURR SOP II.2.1."H" ANSWER K.07 (1.00)

Ensure that core reactivity is continuously monitored t o prevent inadvertent criticality.

REFERENCE SOP II.2.2.F -

g ..,, f <Ki_iEWEL_HONDLING_OND COBE_EB89MEIESS PAGE 24

o. ANSWERS - ' UNIVERSITY'OF MISSOURI -87/02/24-RIDGWAY, K ..

C.

ANSWER K.08 (1.50)

a. False. ( 0. 5) -

b. True. (0.5)

c. False. ~. ( 0. 5)

REFERENCE S D P - I I . 2~. 1 ANSWER K.09' (2.50)

a. Because the flux trap has a positive temperature'(0.5) and void coefficient-of reactivity. (0.5) b.- All flux trap samples will be seal-welded (0.5), leak checked (0. 5) .

and have a negative buoyancy (0.5). The flux trap holder will be loaded or removed only with the reactor shutdown (0.5). .The flux trap holder will be securely locked in place. (0.5) Verification of proper latching by an operator other than the one inserting the flux trap. (0.5)

'(Any three for 0.5 each)

REFERENCE SOP VIII.2.3.

_ Lt__0Dd1NISIB8IIVE_EBQgggg6gg2_GQNQlIlQNS_8NQ_LIN1I@IlgNS 'PAGE~ 22 10- ANSWERS -- UNIVERSITY OF MISSOURI. -87/02/24-RIDGWAY, K.

b.

ANSWER. L.01 (3.50)

a. . Red - Danger.to personnel (0.5)

Yellow Danger to equipment (0.5)

White - Supplemental information concerning operating procedure. (0.5)

6. A licensed operator (0.5)

c. Shift supervisor (0.5)

-d. . When the tags are removed, the date of removal ( 0. 5 ) - and the initials of the individual clearing the tags (0.5) shall bec

. entered on the. tag log.

REFERENCE SOP /I.4.10 ANSWER L.02 (3.50)

a. The safety limits shall prevent damage to the fuel element cladding.-(1.0) The LSSS shall prevent the safety.

limits from being exceeded under the most severe anticipated transient. (1.0)

b. Flow rate 1625 per loop (0.5)

Temperature 155 degrees Fahrenheit (maximum) (0.5)

Pressure 75 psia (minimum) (0.5)

REFERENCE Technical Specifications 2.1 ANSWER L.03 (2.50)

1. The truck entry door closed and sealed. -

2. The utility seal trench filled with water to the depth required to maintain a minimum water seal of 4.25 feet.

3. All containment building ventilation system automatically-closing doors and automatically-closing valves are operable or placed in the closed position.

4. The reactor mechanical equipment room exhaust system, including the particulate and halogen filters, is operable.

5. The personnel airlock door operable. -

6. The most recent building leak test was satisfactory.

(0.5 each - any five for full credit.)

Lz__6Dd1Ni@IB@TIVE_EBQGEQUBES2_GQNQlligNS_@NQ_LidlI@llQNg. PAGE- 26 1F -ANSWERS -- UNIVERSITY OF MISSOURI -87/02/24-RIDGWAYv_K.

c-

^ REFERENCE

-Technical Specification 1.15 ANSWER L.04- ( .50)

True.

' REFERENCE' SDP I.4.2.E.

ANSWER L.05 (1.00)

Reactor Manager (.7) or his authorized delegate (.3).

REFERENCE SOP I.4.3.A.

ANSWER L.06 (1.50)

a. Systems and instruments on the Startup Checksheet but not on the short form have been in continuous normal operation since completing-the last Startup Checksheet. (0.5)

b. A Startup Checklist has been completed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or the reactor has operated some time within the previous 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and a-Shutdown Checksheet has not been completed. (0.5)

c. No anomaly of any systems not covered by the short form has occurred since the completion of the last comprehensive Startup Checklist.

(0.5)

REFERENCE SDP I.4.3.F.1

. ANSWER L.07 (1.50)

Two licensed operators (.50) nne of which is a senior operator (.50) with one licensed operator in the control room (.50).

REFERENCE -

SOP I.4.2.C 4-

r --

"Li__BDd1NISIBBIINE_PBQGEQUBES3_GQNQlI1QU@iSNQ_ Lid 1I811gN@ PAGE .2

.c.-

1 ANSWERS.-- UNIVERSITY OF MISSOURI ' -87/02/24-RIDGWAY, K.

.- O :

ANSWER' 'L.08 . ( 1. 00) .

5 Percent '(1.0)

REFERENCE SOP-I.4.4.H ANSWER L.09 -(2.00)

Unusual Event (0.5) , Alert (0.5). and Site Area Emergency (0. 5) -

Add-(0.5) if in this order.

REFERENCE SEP-01 ANSWER L.10 (2.00)

a. 100 Rem (0.5) 25 Rem (0.5)

b. 1. Volunteer over 45 years. (0.5)

2. Volunteer is familiar with the radiological consequences of the emergencyfexposures. ( 0. 5)-

3. Women of child bearing age shall not take part. (0.5)

(Any two)

REFERENCE SEP-4 and 11 ANSWER L.11 (1.50)

1. Send the Assistant Duty Operator to the cooling tower to assess the flow reduction problem.

2. Switch secondary pumps to determine whether the action corrects the deteriorating flow conditions.

3. Notify the shift supervisor.

4. Monitor the position of S-1 and reactor temperature.

5. IF primary / pool temperature cannot be managed, the reactor shall be shut down, leaving primary and pool systems in operation.

(Any three. 0.5 each) -

REFERENCE REP-13 1

m

TEST: CROSS REFERENCE PAGE 1.

-I QUESTION VALUE REFERENCE

- H .'01 '2.00 RRKOOOO322 H.02 2.00 RRKOOOO325 H.03 1.00 RRKOOOO327 H.04 1.00 RRKOOOO328-H.05 3.00 RRKOOOO329

~H.06 1.00 LRRKOOOO330 H.07- 2.00 RRKOOOO331 H.08 1.50 RRKOOOO332 H.09 2.00 RRKOOOO333 H.10 1.00- RRKOOOO334 H.11 .3.00 RRKOOOO335

-19.50.

I.01 2.00 RRKOOOO323 1.02 4.00 _RRKOOOO324 I.03- 1.00 RRKOOOO326 1.04 2.00 RRKOOOO336 I.05 3.00 RRKOOOO337 I.06 2.50 RRKOOOO338 I.07 1.00 RRKOOOO339 I.08 1.00 RRKOOOO340 I.09 2.00 RRKOOOO341 I.10 1.50 RRKOOOO342 20.00 J.01- 3.00 RRKOOOO313

'J.02 2.00 'RRKOOOO314 J.03 3.00 :RRKOOOO315 J.04 2.00 RRKOOOO316 J.05 3.00 RRKOOOO343 J.06 2.00 RRKOOOO344 J.07 1.00 RRKOOOO345 J.08 3.00 RRKOOOO346 J.09 1.00 RRKOOOO347 J.10 2.00 RRKOOOO348 22.00 K.01 3.00 RRKOOOO317 K.02 2.00 RRKOOOO318 K.03 3.00 RRKOOOO349 K.04 2.00 RRKOOOO350 K.OG 2.00 RRKOOOO351 K.06 1.00 RRKOOOO352 K.07 1.00 RRKOOOO353 -

K.OU 1.50 RRKOOOO354 K.09 2.50 RRKOOOO355 18.00 L.01- 3.50 RRKOOOO319 L

-y_

_ TEST. CROSS REFERENCE PAGE 2 l .-QUESTION- VALUE REFERE'NCE-L RL.02 3.50- .RRKOOOO320'

L.03 2.50 'RRKOOOO321 L.04 .50 -RRKOOOO356

-L.05- .1.001 RRKOOOO357.

L.06 '1.50 _RRKOOOO358-

. L. 07 - .1.50 RRKOOOO359 L.08 1.00 RRKOOOO360

- L.09 2.00 RRKOOOO361 L-1O' 2.00 .RRKOOOO362

~L '

'1.50 RRKOOOO363 20.50

--~~-_

- - - ~ ~ -

100.00 O

L