IR 05000134/1987001

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Exam Rept 50-134/87-01OL on 870511-12.Exam Results:Of Two Reactor Operator Candidates,One Passed Both Written & Operating Exams & One Passed Operating Exam,But Failed Two Out of Seven Written Exam Sections
ML20215M386
Person / Time
Site: 05000134
Issue date: 06/17/1987
From: Coe D, Collins S, Keller R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20215M361 List:
References
50-134-87-01OL, 50-134-87-1OL, NUDOCS 8706260379
Download: ML20215M386 (46)
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U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT

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EXAMINATION REPORT N (OL) ]

FACILITY DOCKET N ;

i FACILITY LICENSE N R-61 l LICENSEE: Worcester Polytechnic Instit.ute Worcester, Massachusetts 01609 l I

I FACILITY: WPI Nuclear Reactor Facility I i

I EXAMINATION DATES: May 11-12, 1987 CHIEF EXAMINER: [ v '^r 4 m #T Dou~glas H. Coe, Chi'ef Examiner '

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Date

l REVIEWED BY: b_ _ _ hjh d[M/["7

,_ Robert M. Kefler,Shief i D5te 1 Projects Section 1C ]

APPROVED BY: M N /T)$

Samuel J. :ollins, Deputy Director 6fl7fp Date ,

Division of Reactor Projects SUMMARY: Written and operating examinations were administered to two reactor operator (RO) candidates. One candidate passed both the written and operating examinations and was issued a license. The other candidate passed the opera-ting examination but failed two out of seven written examination sections and was not issued a licens h[ OCK V

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REPORT DETAILS TYPE OF EXAMINATIONS: Replacement EXAMINATION RESULTS:

1 RO l l Pass / Fail l l l 1 l l l Written l 1/1 l l l l 1 I I 10perating l 2/0 l l l _I 1 l l l j l0verall l 1/1 -l  ;

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l l I CHIEF EXAMINER AT SITE: D. H. Coe 1 Summary of generic or deficiencies noted on oral examinations:

This information is being provided to document areas of minor weakness in '

the licensee's training program which should aid the. licensee in upgrading i license and requalification training program Candidates had dif ficulty explaining the ef fect. of subcritical mul- ;

tiplication on neutron flu i

' Candidates could not describe the origin of delayed neutron Candidates were not aware that de-energizing an electrical fire is i usually the fastest way to extinguish the fir ! Candidates were unable to describe how.the safety channels were cali- i brated, Summary of generic strengths or deficiencies noted from grading of written examinations:  !

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This information is being provided to document areas of' minor weakness in

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the licensee's training program to aid the licensee in upgrading license

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and requalification training program i

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l Candidates were unable to predict the reactivity effect of fully loading

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j the core matrix with fuel with respect to maintaining subcritical condi- '

tion j 4 Personnel Present at Exit Interview:

i NRC Personnel D. Coe', Chief Examiner-Facility Personnel T. Newton, Facility Director 5. Summary of NRC Comments made at exit interview:

i No preliminary results were given. Several facility comments on the writ-ten examination were discussed and the facility was requested to submit substantive comments in writing within five days to be considered during exam gradin . CHANGES MADE TO WRITTEN EXAMINATION DURING' EXAMINATION REVIEW:

Question N Change Reason

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B.0 Change "10 to the (-10)" Correct typo to "10 to the (-5)"

D.0 Add "and scaler" Add additional cor-rect answer per SAR pg. 24 E.02 Deleted Question asked for

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scram functions j which :nay be by- ;

passed, but. there ;

are none. . Question - l should have asked

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for the safety functions which may be bypassed per ,

Tech Spec Table : .;

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Question N Change Reason !

E.06 Add " Place a high level Allows another source near the area monitor" means of manually i setting off the alar G.01 Delete "Na /Na231n water" Na 23 is not sig- ,

nificant in the WPI pool, i

G.04 Will consider R0 precautions Question not clear l as well es entrant precautions as to which is i for full credi desired, j d

G.06 Change beta gamma range to Corrects numbers to 1

"< 1 mR/hr to > 50 R/hr" recently changed Tech Spec J l

Attachment: Written Examination and Answer Key (RO) '

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E1__EEEEO9h_9EE891199_Ed909EIE01@IlCS PAGE 23

[ ANSWERS -- WORCESTER POLY. INSTITUTE -87/05/11-TURNER, I i

ANSWER C.01 (2.00) I l

t a) In the ouestion context," shadow" means to interpose between  !

the neutron detectors ar.d the reactor fuel, material that will j absorb or deflect neutrons so that the detector reading reads I lower than expected for a given power l evel . (1.00)

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b) Operator would be reading power instruments i nac cur at el y lo (3.00)

REFERENCE WPI - TS - 2.3 Page 4 j i

ANSWER C.02 (2.00) l

a. Count rate taken at start. Ratio of count rate i.aken after react i vi t y addition and original count rate is plotte b. Where plot crossen zero axis, reactor is critical l REFERENCE WPI - TS - 5.10 (3);

ANSWER C.03 (2.00)

Because the detector for the B-10 Counter " sees" more l directly neutron multiplication of Source neutrons due to added fuel being more nearl y between source and detector (1.00) where as fuel additions between the source and the CIC linear detectors "see" scattered and refl ected neutrons f rom each fuel additions which are more diffuse effects.(1.0) (2.00)

REFERENCE WPI, Operating and lest Pr ocedures, Page 1 l

, GENERAL OPERATING CHARACTERISTICS

PAGE 24 ANSWERS'-- WORCESTER POLY. INSTITUTE -87/05/11-TURNER, .

ANSWEH C.04 (2.00)

a) True (0.50)

b) False (0.S0)

c) False (0.50)

d) False (0.50)

REFERENCE WPI, T.yp i c a l Operator Exam Questions, pages 2 and 1 . WPI, SAR, Section 5, page 28 and 2 !

ANSWER C.05 (1.00)

24 (0,5) 5 by 5 (0.5) (1.00) ,

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REFERENCE f WPI, Operating Procedures, Section 1, page ANSWER C.06 (1.50)

a) TRUE (0.50)

b) FALSE ( 0. 50 ) - !

c) TRUE (0.50)

REFERENCE WPI, Sectaon 6.3.1, pace 33: Section 3.10, page 24 WPI, Operating.and Test Procedures, Section 10, page ANSWER C.07 ( 1. 50 )

a) Removes sediment which has coll ect ed in the resin bed C+0.43 and to separate cations and anions C +0.1 (0.50)

b) Regenerate the anions C+0.5 (0,50)

c) Regenerate cations [+0.53 (0.50);

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ANSWERS -- WORCESTER POLY. INSTITUTE -87/05/31-TURNER. .

i REFERENCE WPI, Operating and l est Pr ocedur es, Demi ner al i z er RegenPr at i no , p a p r- 3 l l

i ANSWER C.OB (2.00)

If no control or regulating blade is withdrawn from its fully seated position (1.) or there are twel ve or less fuel elements loaded in the core (1.). (2.00)

REFERENCE WP3 - TS - Shutdown Cnndition - Page )

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9 __ INS]$UDEylp_9Np_CpylSQL5 PAGE 26 ANSWERS -- WORCESTER pot.Y. INSTITUTE -87/05/ll-TURNER, .

ANSWER D.OJ (2.50)

A CIC consists of two (2) concentric chambers with essentially equal volume One chamber is sensitive to neutrons and gamma energy because its walls are coated with B-lO and it contains a counting gas C+0.53 and the other chamber is sensitive only to gamma as it contains counting gas only [+0.5]. Voltages applied to the chambers are such that the currents resulting from gamma energy in each chamber are opposed and subtract C+1.0 The remaining chamber current due to neutrons only is amplified for power and period d et er mi nat i on . [+0.53 (2.50)

REFERENCE WPI, Oper at or Ex ami nat i on Questions, Cat egor y 5, Number '

BWR ACADEMICS SERIES, Instrumentation and Control,by Hopkins & Johnson, Nov. lo84, General Electric, Oper at or Trai ni ng Servi ce ANSWER D.02 (1.00)

A " slow" scram actuates the Scram Rel ay which drops power to the current amplifiers to the Control Blade holding magnets causing the Control Blades to be i released and droppe (0.50)

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A " fast" scram directiv cuts current t o the scram magnets al l owi ng the Blades to dro (0.50)

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REFERENCE WP1, SAR, Section 4.3.12, page 2 I

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. ANSWERS -- WORCESTER POLY. ]NSTITUTE -87/05/11-TURNER. ANSWER D.03 (2.00)

a) The detector is a movable chamber and i s wi thdrawn to a (0.50) .

low flux posi ti on during operatio i b) The detector, an ion chamber,( operates in the proportional l region, on the (n a) reaction to its counting gas BF3.) (0.50)

l c) Its sensitivity extends from counting source neutrons to (0.50)

neutron fluxes equivalent to about 1 ;

d) An audible s3gnal W count rate met ep 2 r r-- .m . SCd. f, #" (O.50)

%y Me ) . l REFERENCE WPI, SAR, Section 4.3.8, page 24 {

l ANSWER D.04 (1.00)

0.2 W to 15000 W (.5)

2x 10t-33% to 150% full power (.5) (3.00) j l

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REFERENCE WPI, Technical Speci f i c at i ons, Section 4,lnstrumentation, page j

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ANSWER D.05 (2.50) l SAR, Figure 21 attached (2.50)

REFERENCE WPI, Bl oc k diagram of Safety I nst r ument at i on , Figure 21, Appendix "B" to Technical Specification ANSWER D.06 (1.50) l

j t.evel switch [+0.5] Less than or equal to one(1) foot crop in pool water level [+0.53 Building evacuation C+0.53 (1.50)

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9:__ jug]SgDENJg_999_ggy]BgLS PAGE 2G ANSWERS - -WORCESTER POLY. INSTITUTE -87/05/11-TURNER, .

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REFERENCE WPI, Technical Speci f i cat i ons. T abl e 4.1, page 1 l

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i ANSWER D.07 (1.00)

The trip mi x er f uncti on is to scram the reactor on either a high flux (.5)or short period si gnal ( .5) . (1.00)

REFERENCE WPI - SAR - 4.3.6 Page 23 1 ANSWER D.08 (1.00)

The annunciator horn would sound (.S) and the red light for the j period trip would come on (.5). (1.00) j i

REFERENCE WPI - SAR - 4.3.13 - P .

ANSWER D.09 (1.50) i 1) Startup Channel -(0. 50 ) !

l 2) Log N Period Channel (O.50) )

3) Linear Channel s 1 t< 2 (0.50)

REFERENCE WPI - Techn2 cal Speci f i c at i ons - 4.5.1 Pg l

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ANSWERS -- WORCESTER POLY. INSTITUTE -87/OS/11-TURNER, j

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ANSWER (7.50) Its failure must not interfere with insertion of the c ont r ol blad (0.80) l I Its failure must not damage the reacto (0.80) Its failure must not release excessi ve ai rborne contaminatio (0.90)

REFERENCE WPI, Technical Specification, Section 2.3, page i ANSWER E 02 (2.00) j Function Condi t i on for Bypass Neutror count r - less or When Kef4 less than equal to set point + ' 53 . [+0.53 (1.00) Pool water level less than A li censed SRO is present set point C+0.53 1 he facility [+0.53 (1.00)

REFERENCE WPI, Technical Spec i f i cat i ons. Sect)on 4, T abl e , page 1 ANSWER E.03 (2.00)  ;

Condition Set Poi nt Reactor power greater 150'/.  ;

than set point full power (1.00) j (Power level safety channel)  ; Reactor Per2od 3 se (1.00)

<= set point REFERENCE  !

WPI, Technical Speci f i c at i ons, Sec ti on 4.5.4, page 10.

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ANSWER E.04- (2.50) i 1) >15 kw on log N chart

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2) < 7 second period 3) HV failure 4) Manual Scram 5) upscale past 10 kw on safety channel s 6) disable log N am j 7) HV monitor fails (any 5 at .5 each) 12.50)

REFERENCE WPI, SAR, page 2 . WPI, 1987 r equal i f i c at i on exa ANSWER E.05 (3.00)  ; A seven (7) second delay period subsequent to switching the master switch to "on" must pas (0.75) Log CRM count above 50 cp .(0.75) Regulating b}ade is at the lowest positio (0.75)

4.- Reactor is not in a scram conditio (0.75) _,

REFERENCE WPI, SAR, Section 4.3.10, pages 24 and 2 !

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Y AND EMERGENCY SYSTEMS

PAGE 31 ANSWERS -- WORCESTER POLY. INSTITUTE -87/05/11-TURNER, .

I ANSWER E.06 (2.00) l l Switching off a fail safe radiation station at the c onsol (1.00) Tripping a low water al arm devi ce adjacent to the reactor bridg (1.00) j Ma c t. s LtsL Iml Sou r s e W *" W Thrs O ~)

REFERENCE WPI, SAR, Section 6.5.4, page 3 f ~}

I ANSWER E.07 (1.00)

The building evacuation alarm sound (1.00)

REFERENCE WP1 - TS - Safety System Functions, Pg 1 l

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ANSWERS -- WORCESTER POLY. INSTITU1E -87/05/11-TURNERg a

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ANSWER F.01 (2.50) l

l 1. Detectors i Consol e ampl i f i er . Scram circuits 4 Blade . Rod permi ssi ve interlocks (.5 each) (2.50) ,

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REFERENCE i WP1, Operating and lest Procedures, Section 10, page )

d ANSWER F.02 (1.00)

The NRC Licensed Seni or Reactor Operat or (SRO). (1.00) .

REFERENCE j 10 CFR 50.54 (y). j

ANSWEP F.03 (2.00)

two (1.0) and 15 i nches (1.0) (2.00)

REFERENCE ,

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WPI, SAR, Sect)on 6.3.2, page 34

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ANSWERS -- WORCESTER POLY. INSTITUTE -87/05/11-TURNER, j l

l ANSWER F.04 (2.50) f a) Shutdown the reactor (0.90)

l b) Call for Worchester Police Department Ambulanc . Render CPR, first aid treatment, i.e., treat the vi cti . Notify Campus Police as soon as possibl (Any two (2) at .80 each) (1.60) (

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REFERENCE i 1) WPI,SAR, Emergency Plan, Personnel Injury or Sudden )

Illness, page 38 '

2) WPI, Technical Specificaiton 2.2 (1).

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l ANSWFR F.05 (2.00) the reactor is in mi ni mal safe operating condition prior to approach to criticality (0.50) proper security precautions have been taken relative to all restricted areas (0.50) j A licensed reactor operato (1.00)

REFERENCE WPI, Operating Procedures, Checkout and Op er a t i on , page ANSWER F.06 (2.50) Wait 8 seconds (0.84) Ac knowl edge the horn with red button (0.83) Pr es s t h r: R e s- r t tiu t t on (0.83) (2.S'

REFERENCE WPI, Reactor Checkout Procedures Number 9. Master Switch to On, page , F_. _ _ _S_T

_ _ A_N_D_A_R_D_ A_N_D_ _E _M_E

_ _ _ R_G_E N_C_Y_ O_ _P_E _R A_T _I NG_ _P_R_O_C_E _DU_R_E _S

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ANSWERS.-- WORCESTER POLY. INSTITUTE -87/05/11-TURNER, .

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ANSWER F.07 (2.50)

i Open Master power switch to reacto . Turn room ventil at i on to ON in CasP of a spi. Turn room ventilation to OFF in case of fir Evacuate the building i mmedi atel . Evacuate other persons seen as they themselves evacuat (.5 each) (2.50) REFERENCE WPI, SAR, Reactor Emergency, Section 5.5.4, page 3B I WPI, Nuclear Reactor Evacuation Procedures, page I l l

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G. __B9D19I10N_CggISg(_99D_S@[Ely PAGE 35 ANSWERS -- WORCESTER POLY. INST]TUTE -87/05/11-TURNER, , l ANSWER G.01 (1.50) Isotope Source Ar 41 

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Ar 40 in air _x,. , 

     (0.75) '. ^ , c-
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N Ib O 1Ain water (0,7N) b.b3 REFERENCE Introduction to Nuclear Engineering, J. Lamarsh, pages 471 and 47 ANSWER G.02 (1.50) f a) 1.25 rem (0.50) b) 25 rem (.5) if a 12fe threatening situation is pr esent ( . 5) . (1,00) REFERENCE WPI, RHSC Radiation Regul at i on . WPI, SAR, Section 3BD, aage 38 ANSWER G.03 (1.00) i l 

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In a radiation area an 2nd)vidual could r ec ei ve a whole body dose in excess l of 5 mrem /hr but less than 100 mrem /hr wh21e an a high r adi at i on area the dose rate would be in excess of 100 mrem /h (1.00) REFERENCE  ! WPI, Radiat2on Regul at i ons, page ANSWER G.04 (1.50) r ea c t or room [+O EJ and thc two sma); rooms directly a b C'v F Control For dr2ves o* 7 : .d 6rd 3rd f}oor of Washburr Ha: I f**' ) Posting w2th normally locked doors C+0.53 (1.50) REFERENCE WPI,TS, Site ano Des 2gn Features, Section 4, paragraph 4.2, page ,

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9___B8918Il9N_CQN]BQL_9Np_S9EEIY PAGE 36 l 

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ANSWERS -- WORCESTER POLY. INSTITUTE -87/05/11-TURNER, i l l 

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I ANSWER G.05 (2.50) i a) 2 mrem /hr (0.75) 

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b) time or distance or shielding (any two of three for 

[+0.5] Pach    (1.00) '

c) twice [+0.5J (0.75) REFERENCE WPI, Radiation Regul at i ons, pages 4 and ANSWER G.06 (2.00) 

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i Beta-gamma measuring devi c es with ranges .0. uv JG uu m _ (1.) and j neutron measuring devices with ranges .04 to 1000 mrems/hr (1.). (2.00) 

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l REFERENCE WPI - Technical Specifications - 3.3 Pg l i ANSWER G.07 (1.00) I Radi ati on Safety Officer (1.00) 

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REFERENCE WPI - RHSC - Radi ati on Regul at i ons Memorandum - April 1980, pg 2 

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9 __B8919II9N_CgNJBQ6_9Np_@@[Ely PAGE 37 i 

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, ANSWERS -- WORCESTER POLY. INSTITUTE -87/OS/11-TURNER, ANSWER G.08 (1.00)

By inverse square law  ! 2 2 R1 = R2*(d2/d1) 100 mrem /nr = R2 * (25/100) i R2 = 1600 mrem /hr (1.00) ) REFERENCE Introduction to Nuclear Engineering, J.R. Lamarsh, Pg. 409

ANSWER G.09 (2.00) Thermal neutron Neutrons are very massi ve compared to beta or gamma and though not charged, as beta, the neutrons cause more ti ssue damag The QF is 10 which means one RAD dose of thermal neutrons will have 10 times the effect on the body as one l RAD dose of beta or gamm (2.00) l REFERENCE Introduction to Nuclear Engineering, J.R. Lamarsh,Pg 373

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DATE ADMINISTERED: _g7/ggfil________________ EXAMINER: _ TURNER 1_R.______________ i CANDIDATE: _________________________ j l' INgIRUCI]QNg_lg_C9NQJpSIE1 i Use separate paper for the artswer s . Arite answers on one side onl Staple question sheet on top of the a n. ,wer sheet Points for each quest i on ar e indicated in parentheses after the quest i on . The passing j grade requires at least 70% in each categor Ex ami nat i on papers will j be picked up six (6) hours after the ex ami na t i on start j 

    % OF        1 CA1EGORY % OF CANDIDATE'S CATEGORY        ]

_ _ V_ A_ L U E_ _ T_ O_ 

-- - T A_ L- ___S_C_O_RE_---- ----_E--_

VALU ___---__--------_EGOR_Y-------------- CAT--- l l 19199__ 19 99 ___________ - - _ _ _ . . _ _ PRINCIPLES OF REACTOR OPERATION _13 99-- 13 99 ___-__-_--- _-_-_--- FEATURES OF FACILITY DESIGN _13:99__ _JS 99 ___________ ________ GENERAL OPERATING CHARACTERISTICS 13 99__ _16:99 ___________ ________ INSTRUMENTS AND CONTROLS 19199-- 29199 -__------__ ________ SAFETY AND EMERGENCY SYSTEMS I _19199__ _lE:99 ___-______- __._____ STANDARD AND EMERGENCY OPERATING 1 PROCEDURES _16:99-- 19199 ___________ ________ RADIATION CONTROL AND SAFETY 199199__ _____-__-__ --___-__% Totals Final Grade All work done on this ex ami nat i on is my ow I have neither given nor received ai _-_--_-----_-----_------ Candidate's Signature

l r NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the admi ni strat i on of thi s exami nati on the f ollowing rules apply: Cheating on the exami nation means an automatic denial of your application and could result in more severe penaltie l Restroom trips are to be li mi t ed and only one candidate at a time may j leav You must avoi d all contacts with anyone outside the examination I room to avoid even the appearance or possibility of cheatin . Use black ink or dark pencil gnly to facilitate legible reproduction I Print your name in the blank provided on the cover sheet of the 

     - ex ami nati on .     .

l l Fill in the date on the cover sheet of the ex amination (i f necessary). l l Use only the paper provided for answer . Print your name in the upper right-hand corner of the first page of each I section of the answer shee .I l Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category ors a.new page, write gnly gn gne side of the paper, and write "Last Page" on the last answer shee . Number each answer as to category and number, for example, 1.4, . Skip at least three lines between each answe . Separate answer sheets from pad and place finished answer sheet s face down on your desk or tabl . Use abbrevi ati ons onl y if they are commonly used in facility literatur I 13. The poi nt value for each question is indicated in parentheses after the j question and can be used as a guide for the depth of answer require Show all calculations, methods, or assumptions used to obtain an answer ) to mathematical problems whether indicated in the questi on or no . Par t i al credit may be give Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN , l 16. If parts of the ex ami na ti on are not clear as to intent, ask questions of l the e n ner onl . You must sign the et at ement on the cover sheet that indicates that'th work is your own and you have not received or been given assistance in completing the ex ami nati o Thi s must be done after the ex amination has been complete ) i 

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/ 18. When you complete your enamination, you shall:

. Assemble your examination as f oll ows: I (1) Exam questions on to (2) Exam aids - figures, tables, et (3) Answer pages including figures which are part of the answer 1 Turn in your copy of the examination and all pages used to answer the ex amination quest i on lurn in all scrap paper and the balance of the paper that you did not use for answering the question Leave the ex ami nati on area, as defined Py the examine If after 

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l eavi ng , you are found in this area wh 4le the examination is still in progress, your license may be denied or revoke i l l i 

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9:__EBJNglg6ES_gg_ggggIgg_gggggIJgN PAGE 2 

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i QUESTION A.01 (2.00) i a. Why is a neutron source used during startup (rod withdrawal) in your reactor?  ! b. What material is used in the source, and how does it produce neutrons? 

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QUESTION A.02 (1.00) If each one of the three (3) safety blades is worth appr ox i mat el y four(4) percent delta Keff, briefly ex pl ai n why their total combined worth is 14 to 18 percen l QUESTION A.03 (2.00) ]

Usi ng words, define the f oll owi ng: a) delta k/k b) Keff l l QUESTION A.04 (1.00) l 

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What is the amount of reactivity that is necessary to make the WPI reactor prompt critical and what reactor physics parameter is equal to the requestec) value? l 

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QUESTION A.05 (2.50) Give three reasons why ex cess reactivi ty in the WPI Reactor is greater than that needed to just achieve initial criticality, i I 

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QUESTION A.06 (1.50) If reactor power at the WPI reactor increases steadily from one(1) KW i o -5 KW in 50 seconds, what is the approximate. period? Show cal cul ati o , 

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

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i e 9 __E51Ng]fLEB_g[_SEggIgB_gggggIJgN PAGE 3 

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QUESTION A.07 (2.00) How and why does a pool temperature increase affect the reactivity of the core? Include the effects on water density and Kef QUESTION A.08 (2.00) I i 

  , . i With the reactor critical , a 25 inch di aniet er cylinder of air at i atmospheric pressure is suspended from the bridge next to the core. What will the reactor power do and why?

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

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r e __EE@ LUBE @_QE_ESClLily_DE@lGN PAGE 4 

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. QUESTION B.01 (1.00) What design features are pr ovi ded to assure security for any fuel el emen t s, not loaded i r, the reactor core? l QUESTION B.02 (2.00) Wtkh!, when at power (10 KW),is the ratio of the fast flux to thermal flux in the reactor greater than one and the ratio of fast flux to thermal in the beam port is less than one? QUESTION B.03 (1.50) Where are the three (3) area radiation monitors located? i l QUESTION B.04 (1.50) List the f ollowing pool water limits when the reator is in operation: a) Resistivity (purity)

b) Activity j l c) Pool temperature  ; l QUESTION B.05 (1.00) Answer the f oll owing TRUE or FALEE: a) Ventilation intake as well as exhaust are both f i l t er ed with fiberglass filters, b) The normal exhaust duct flowrate is greater than 5000 cu ft/ mi (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

r B_ _. _ _F_E_ A_ T_U_ R_E_ S_ _ O_ F_ _F_ A_ C_ _I L_ _I T_ Y_ _ D_ E_S_ _I G_ N_ PAGE 5 l i 

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QUESTION B.06 (2.00) With the Regulating Blade full out, assume a slow positive change in reactivity of .0065 delta k/k is occurring (such as a 180 second ramp).

Will the Regulating Blade be adequate to control this addition? WHY ? State all assumptions and show all wor QUESTION B.07 (1.00) Briefly explain why no dashpot is required at the end of a Regulating Bl ade assembl QUESTION B.OG (2.00) I Answer the following TRUE or FALSE: a) If the pool drained uncovering the core, no fuel melting or dangerous release of r adi oacti ve f i ssi on products are anticipated. WHY? b) Flooding the Beam Port with water would li kely resul t in an approach to prompt critical. WHY?  ! QUESTION B.09 (1.00) Select the proper answe The poi son section of. the Saf ety Bl ades are composed of: , i a) boron carbide and al umi num plates b) stai nl ess steel plates c) boron carbide and stainless st eel plates d) boron carbide and nickel plates (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

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' li FEATURES OF FACILITY DESIGN PAGE 6 

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l l j QUESTION B.10 (1.00)  ! With the entire 6 by 9 grid filled with fuel elements, the control and regulating Blade system is sufficient to maintain the core sub t r i t i c a l '? T r u t-or Fa1se? 

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

. 9 __gggg596_OggggIlyg_gbegggIg6]g]]CS PAGE 7 

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QUESTION C.Ol (2.00) Technical Speci f i cati ons requi re that no experiment shall be installed in the reactor in such a manner that it could shadow the nuclear instrumentatio Ex pl ai n what is meant by " shadowing." Why is this undesirable? QUESTION C.02 (2.00) How are the points on a 1/M pl ot determined ? Describe how the 1/M plot is used to predict the approach to criticalit , 

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QUESTION C.03 (2.00) Why during a core loading, is the B-10 Counter more reliable in responding l to reactivity changes as fuel elements are added than the linear detectors I in terms of its locatio ) QUESTION C.04 (2.00) 

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l Answer TRUE or FALS ! When WPI reactor is operating at 10 KW, the radiation levels are approx i mat el y: a) 25 mrem /hr at the pool surf ace moni t or , b) 15 mrem /hr ath the thermal column doo c) 20 mrem /hr at the shielded beam port, d) 500,000 mrem /hr at the core surfac (***** CATEGORY C CONTINUED ON NEXT PAGE *****)

T C.__gENggg6_gfgg91]Np_CH989CIEBl@IJC@ PAGE 8 

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OUESTION C.05 (1.00) ] Fill in the blanks in the f ollowing sentence so the statement is true: ! The WPI reactor normal feci loading is ________ elements in a ______ by _______ array, i

QUESTION C.06 (1.50) l l Answer True or False, i a) During a reactor start-up, flux indications are available from the )' Safety Channel s prior to usable flux indication from the Log "N" Channel Chart recorder, b) The manual scram initiates a " fast" scra c) Instrument and control power switches are normally left on at all time QUESTION C.07 (1.50) Explain the purpose of each of the following steps in the regenerati on of the demineralizer, a) Buckwash b) Caustic soda treatment (NaOH) c) Acid solution treatment (H2SO4) i QUESTION C.08 (2.00) How is shutdown condition defined for the WPI reactor? I (***** END OF CATEGORY C *****)

, 91__JN@l3Uggyl@_3Ng_ggyJ3ghg PAGE 9 

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QUESTION D.01 (2.50) Describe a Compensated Ion Chamber and explain how gamma compensation is  ! accomplished, i 

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QUESTION D. 02' (1.00) l Explain the di' Prence between a relay " slow" scram and an electronic j 

" fast" scra )

DUESTION D.03 (2.00) Answer the f ollowing with respect to the Startup Channel: a) What feature extends the life of the detector? b) What type of detector is used? c) What is the sensitivity range of the detector? d) What are the two output devices? l

l l QUESTION D.04 (1.00) What power l evel range is monitored by the Log "N" period channel? State thEl range in Watts and in percent power in your answe l OUESTION D.05 (2.50) Sketch the Log "N" channel in block diagram form from the CIC through the scram relay.Show major components and output (***** CATEGORY D CONTINUED ON NEXT PAGE *****) 

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. 1 l QUESTION D.06 (1.50) , Describe the safety system and required response associated With the pool water l evel alarm, giving (1) detector, (2) the set point range and (3) the action (response) require l QUESTION D.07 (1.00) l What is the function of the " trip mi x er ", wi t h respect to the react or safety circuit? l

l i QUESTION D.08 (1.00) 

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If the reactor was scrammed during startup by a too short period, how Would the operator know that it was the period trip that caused the scram? 1 

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QUESTION D.09 (1.50) What is the minimum nuclear instrumentation required for startup? l 

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

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EL__E9 Eely _@ND_@[@@@@NCy_@y@l@[@ PAGE 1) ! 

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l l l QUESTION E.01 (2.50) l Name three constraints specified in the Technical Specifications wi t h respect to potential failure of experimental assemblies i nstal l ed in the reactor cor I QUE . ' 02 (2.00) i Two (2) of the safety sys 3m functions may be bypassed. Identify them I and the conditions for each that mus satisfied in order to permit bypas Db b OUESTION E.03 (2.00) Of the Safety System functions listed in the Technical Specifications, whitt conditions will cause an electronic scram and alarm? Give the set point range for eac QUESTION E.04 (2.50) Gi ve five (5) reasons for a relay scra i QUESTION E.05 (3.00) i Name the four conditions that must be met before the saf et y bl adt> drive j motor interlocks are satisfied prior to a reactor startu DUESTION E.06 (2.00) State two (2) ways the r eactor st af f may manual 1y set-off the err er g en c y e vac uat i on al ar l l l l 

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I (***** CATEGORY F CONTINUED ON NEXT PAGE ****4) j l l l

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. E1__g@Egly_@ND_gDEBggygy_gygTEMS PAGE 12 

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QUESTION E.07 (1.00) What automatic action occurs if the pool water level drops one foot unexpectedl i

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'E __SIBNpggg_gNp_gMggggNgy_gPgggl]Ng_ggggEQUBEg  PAGE 13
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QUESTION F.01 (2.50) Source checks are used to verify the correct oper at i on of what f i ve t ypes of-reactor components? QUESTION F.02 (1.00) In order to protect the public health and safety, a facility licensee may take reasonable action which departs from the Technical Specifications or license conditions under emergency conditions. Who may authorize this action? OUESTION F.03 (2.00) During fuel loading and core al t er at i on , how many control blades have to be withdrawn and how far should they be withdrawn to provide the fast scram ! capability desired? l OUESTION F.04 (2.50) I The only SRO wi thi n one half hour of the operating reactor suddenly becomes unconscious, heart attack suspected; what must the nearest staff member's response be? Li st three (3).

QUESTION F.05 (2,00) Give two objectives of the start up check list and who must approve the list (lowest cognizant level)? QUESTION F.06 (2.50) During start-up procedures. the operator turns the MASTER Switch t o t he Operate position and accidentally scrams the reactor. Give three(3) steps the operator must f ol l ow t o get an indication of magnet curren (***** CATEGORY F CONTINUED ON NEXT PAGE *****)

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,, E __@l@NQ@6Q_@NQ_gdE6@gggy_QEEg@llyg_PRQCEQUREQ PAGE 14 

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QUESTION F.07 (2.50) Name the five actions the reactor operator must complete in a general evacuation procedur I

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

, RADIATION CONTROL AND SAFETY PAGF 15 ! 

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QUESTION G.01 (1.50)  ; What are the sources of three radioactive 1sotopes (argon 41, sodium 24, ant i t nitrogen 16) that are byproducts of research reactor oper a ti oh ? f l l 

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QUESTION G.02 (1.50) a) Give the normal maximum permi ssi bl e whole body dose for WPI personnel for a calendar quarte b) Give the emergency worker authorized dose and the condition for l receiving this dos ) GUESTION G.03 (1.00) I In terms of radi ati on done per hour, what is the ciifference bet. wee,. a j radiation area and a high radiation area? I i QUESTION G.04 (1.50) Where are the RESTRICTED AREAS at the WP1 reactor when the reactor is operating at levels above one(1) kilowatt and what are the normal l precautions associated with these areas when entry i s not require (***** CATEGORY G CONTINUED ON NEXT PAGE *****)

i, s G.__Be910IlgN_ggNI@g6_@Ng_S@EEIY PAGE 16 ' 

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QUESTION G.05 (2.50) The following questions should be answered based on the " Radiation Regulations" for your facility: a) What is the max 2 mum radi ati on l i mi t at an accessible place on the outside of the shielded storage space provided for radiation sources? b) What are two (2) of the three (3) factors that c6n be used to minimize radiation dose to personnel? c) Skin c ont ami nat i on should not exceed ______ backgroun (fill in the blank) OUESTION G.06 (2.00) Give the types and ranges of the portabl e survey instruments that must be located at the facility to meet Technical Specification requirements, j QUESTION G.07 (1.00) , 

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I Who is responsible for maintaining exposure records and handling the WPI film badge service? I l I OUESTION G.08 (1.00) l If the dose rate from a radiation source is 100 mrem /hr at 1 meter, what it the dose rate at 25 cm? Show wor DUESTION G.09 (P.On) Assumi ng equal RAD doses, which type of radiation will have the greatest bi ol og i c al effect on the body: beta, gamma or thermal neutrons? Explain your answe (***** END OF CATEGORY G *****) 

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

L

E00AT:0N SHE~T 

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#   v = s/t
    ^ycle efficiency = 'Ne; work

, . = ma cut;/(Energy in) 

   ,
, s ,g  s = 'l t + I/2 at'
: . -
      -it
 ?     A = A,e A=
.( ~ = '/2 mv~ a = (V - l ) /*
   '

AN s 

?E = mgn
'/ , = V - at  w = 0 /t  A = :n2/t)j = 0.593/t)p

_ t ,g  :, j;ef f = [( t ,,,,)( ts)] W,y se _ u r . , A= a . r q ,31 

      .\.9)a
:E = h31 un  -

m=V Ap -Ex av .= J . . Q = mCo ~ 5 = JA;. T I=._e" , , , , Pwr = W,.h I=I 10'*'- TVL = 1.3 /u 

? = P,105 ""I )   HVL = -0.593/u
 *       J 3 , a ,t/'t
'       f O~

SUR = 25.06/T S CP, = 5 / ( i - Kgff) 

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CR x = S/(1 - Kef x) i 

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CR,(i - K erri) = CR,(1 2 erf2) 

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SUR = 250/1' - (5 - o)T i 

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T = (l'/c) + [(3 -oVIc] M = 1/(1 - Kgff) = CR;/CR, T = 1/( - 3) M = (1 - Kefr.a )/(1 - Keffi) T = (3 - c)/(Io) SDM = (1 - ei,4 K ,,)/K,,, ., 

; = (K ef-l)/Kg ef = :Keff /K gff  t' = 10 seconcs g     -1-x = 0 . 3, seconcs e = ((t'/(T Ke##)] * b ef -III * II3     l I)d) =1d   j P = (SV)/(3 x 1010)   I d) 2 ,2 9y'2 d 2

: = :N    R/hr = (0.5 CE)/d (meters )

R/hr = 6 CE/d2 (feet) Water Parameters Miscellaneous Conversions 1 gal. = 8.345 10 curie = 3.7 x 1010 aps 1 kg = 2.21 lbm Igaj.=3.78 I ft = 7.48. ga liters I np = 2.54 x 103 Stu/nr Density = 62.4 lbm/ft 3 1 mw = 3.41 x 100 Stu/hr  ; Density = 1 gm/cr lin = 2.54 cm i 

    *F = 9/5*C + 32  j Heat of vaporization = 970 Stu/lom     j Heat of fusion = 144 Stu/lem   *C = 5/9 (*F-32)  4 1 Atm = 14.7 osi = 29.9 in. H BTU = 778 ft-lbf i ft. H O 2
 = 0.4335 lbf/i , _A_. _ _ _P_R_I _NC_I _P_L

_ _ _E _S_ _ _ _O F _ R_E A_C_T _ _O_R_' O_P _E _R A_ _T _I _O_N PAGE 17 j 

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l ANSWERS -- WORCESTER' POLY. INSTITUTE -87/05/11-TURNER, R.

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ANSWER A.01 (7.00) To provi de the core with a enough neutrons so that as rods are (1.00) withdrawn, multiplication will occur under vi si bl e condition Non-regenerative- Pu-Be-- Pu decays with alpha to U -235, (0,5) Alpha reacts with Be to form. neutron plus C -12 (0.5) (1.00) l REFERENCE 1. Principles of Reactor Engineering, Lamarsh, page 4 . WP1, SAR, Section 4.4, page 2 ANSWER A.02 (1.00)  ! 

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The blades shadow each other;.i.e., overlap in t hei r regi ons i of effectiveness thus reinforcing each others effectivenes (1.0) REFERENCE WPJ, Reactor Operating Characteristics, Section 5 of SAR, page 2 ANSWER A.03 (2.00) a) delta k/k is a measure of react i vi t y which measures how far awa I a reactor is from critica ,* (I k Cf C., W(k h hshe~h /Ch o f (1.00) l k e44- 1 : b) Keff is a value from which the state of reactor criticality . l can be determined, that is greater than one if the reactor is supertritica), less than one if the reactor is subtritical, and just one, if the reactor is just critical (1.00) M h+l 5 (tal;lld.C.f.Qf $ REFERENCE ghh A @t Introduction to Nuclear E n gi 6eer i ng , R. Lamarsh, Page 10 , ANSWER A.04 (1.00) rho insertion equal to approximately .65 percent delta k/k (.5) to make the WPI reactor prompt critical.The reactor physics paraneter is Beta (.5) (Beta for WPI reactor is equal to that for a U235 fueled reactor) (1.00) 1 l 

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L . l . l l REFERENCE Introduction to Nuclear Energy, J. Lamar sh , Page 25?. ANSWER A.05 (2.50) To overcome neutron losses due to leakag . To overcome neutron l osses due to poi son . To overcome negative temperature coefficient . To overcome negative void coefficient I To accommodate negati ve reactivity of experiment . To give operating flexibility. (.834 each to max. of 2.5 ) (2.50) 

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REFERENCE Introduction to Nuclear Engineering, R. Lamarsh, Chap t er s 6 and pg. 273-295 

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ANSWER A.06 (1.50) P = Poe T/ tau P = 5 kW Po = 1 KW t = 50 second (0.5) i P/Po =e t/ tau 10/1 = e T/ tau In 5 = t/ tau (0.5) i tau = 50/In 5 tau = 31.1 second (0.5) REFERENCE Intr oduc t i on to Nuclear Enoineering, R. Lamar sh, pg. 255 

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ANSWER A.07 (2.00) 

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As pool water temperature increases, the water becomes less , dense, reduceing H2 per ec(.5), resulting in less t h er mal i,z a t i on ( . 5 ) , j the neutron spectrum hardens, leakage i ncreases reduci ng Kef f t . 5) . l The change in rho is to make it smaller and1the delta rho i s j negative (.5). (2.00) ( REFERENCE Introduction to Nuclear Engineering, R. Lamarsh, Page 27 j l

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i ANSWERS -- WORCESTER POLY. INSTITUTE -87/05/11-TURNER, ANSWER A.08 (2.00) The reactor power will decrease (1.). The air cylinder will displace water next to the core thus increasing leakage and reducing reflectance (.5) causing the neutron population to decrease (.5). (2.00) REFERENCE Introduction to Nuclear Engineering, pg 220 221, J R Lamarsh 

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@ __{g@lU$gp_OE_[9CJ6]Iy_pg@]GN   PAGE 20 ANSWERS -- WORCESTER POLY. INSTITUTE -87/05/ll-TURNER, I O
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ANSWER B.Ol (1.00) Fuel el ement s stored in the under wat er racks can be l oc k eci in 

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place (.5) and a locked storage cabinet i s provi ded .f or " cold fuel el emen t s . (1.00) REFERENCE WPI, SAR, Section 4, Facility Descri pt i on, Page 17 

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ANSWER 9.02 (2.00) The core is small and undermoderated, with insufficient j vol ume of water (H2O) present to slow down all the fast l neutron population to thermal neutrons, resul ti ng in the fast flux being greater throughout (i.e., the ratio of fast to thermal flux is greater than one) (1.). i Additional moderator (water) in the space between the core and face of the beam por i thermali zes addi tional fast neutrons p r i or, to their reaching the beam port thus reversing the rati (i . e. more thermal than fast neutrons at the beam por t ) ( 1. ) . (2.00) REFERENCE WPI, Appendix "P", Reactor Facility Data, Figure . WPI, Appendix "E', Figures 8 and 1 ANSWER B.03 (1.50) At the bridge (0.50) Near the thermal c.ol umn (0.50) Near the beam port (0.50) REFERENCE WPI, SAR, Section 4.3.9, page 24 l i 

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B_ _. _ _ F_ E_ A_ T_ U_ R_ E_ E_ _ O_ C_ _ F_ A_ C_ _I L_ _] T_ Y_ _ D_ E_ S_ _I G_ . N_ P(n G , ANSWERS -- WORCESTER POLY. INSTITUTE -87/05/11-7URNER. . 

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l ANSWER B.04 (1.50) j

a) > 5x 10 to the (5t h ) _or i b) < 10 to the (;pp Ff mi cr ocur i es/ml l c) 60 - 100 degrees Farhenhei t REFERENCE l WPI, TS, 2.1 pg 3

l I ANSWER B.05 (1.00) a) True (0.50) { I b) False (4 reactor room air changes / hour) (0.50) ) l l REFERENCE WPI, SAR, Section 3, pages 15 and 1 . WPI, SAP. Section 7.4, page 4 i ANSWER B.06 (2.00) I l 

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Yes, (.5) a reactivity change of 0.0065 delta K/K is less than the worth of the regulating rod, 0.007 delta K/K,(.5)and the speed of the rod is sufficient to overcome j 

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this additio (1.) (2.00) REFERENCE WP1, SAR, Section 2.3, page 1 ANSWER B.07 (1.00) The Regulating Blade does not scram (drop) by gravity as it is direct coupled to a motor driven mechanis No dec el er ati on dashpot is neede (3.00) REFERENCE WPI, SAR, Sec ti ons 4.1.3 and 4.1.4, page 1 i l \ s l 

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EL_ EE9196E@_OE_E9ClLily_DE@lGN PAL 4E Mj o ANSWERS -- WORCESTER POLY. INSTITUTE -87/05/11-TURNER, l

ANSWER B.08 (2.00) a) True [0.53 because loss of water would shut reactor down, and rate of internal heat generator would rapidly decay to minor levels (air convection cooling sufficient to prevent loss of clad integrity etc.) (0.5) (1.00: b) FALSE [0.53 the amount of excess reactivity added in this ) manner would be approximatel y 0.1 percent and effects ' minima (0.5) (1.00) REFERENCE j 1. WPI, SAR - Loss of Coolant, page 40, paragraph 7. l 2. WPI, SAR - Flooding Beam Port, page 42, paragraph 7. l ANSWER B.09 (1.00) I a) (3,00) REFERENCE 4 WPI, SAR, Section 4.1.1, page 1 I ANSWER B.10 (1.00) l

True (1.)( according to the SAR about 300 gms of U-235 per el emen t would be required to cause the core to go critical with all blades in, about twice that now used) (1.00) REFERENCE WPI - SAR - REACTOR OPERATING CHARACTERISTJCS -Page 2 . - _ _ _ . - . _ . _ _ _ . _ _ _ _ _ _ . }}

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