ML20132E908

Exam Rept 50-087/OL-85-01 on 850620-21.Exam Results:One Senior Reactor Operator Passed Written & Operational Exams

ML20132E908
Person / Time
Site:	05000087
Issue date:	07/29/1985
From:	Ferrell R, Mcmillen J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20132E865	List: ML20132E861 ML20132E908
References
50-087-OL-85-01, 50-87-OL-85-1, NUDOCS 8508020136
Download: ML20132E908 (37)

Text

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U.S. NUCLEAR REGULATORY COMMISSION REGION III l

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Report No. 50-087/0L-85-01 Docket No.50-087 License No. R119 Licensee: Westi ; house Electric Corporation 505 Shiloh Boulevard Zion, IL 60099 Facility Name: Westinghouse Nuclear Training Reactor Examination Administered At: Westinghouse Nuclear Training Center Examination Conducted: One (1) SR0 1

Examiner:

h R. Fetrell 9 2 'y )

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Date '

Approved By:

k- V J. McMillen 7[M[FT Operator Licensing Section Date Examination Summary l Ext on administered on June 20-21, 1985 (Report No. 50-087/0L-85-01) 4 e s-R_e One (1) SRO passe:I the written and operational exams.

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I i REPORT DETAILS

1. Examiner i

i R. Ferrell - Chief Examiner ,

j 2. Examination Review Meeting

' At the conclusion of the written examination, the examiner met with Karen Reuter and Roy Sackschewsky of the NTR staff to review the written examination. A list of the comments was generated and, along with the i examiners responses, is included in a separate attachment.

3. Exit Meeting i At the conclusion of the site visit the examiner met with members of the NTR staff to discuss results of the examination. They were informed that the one (1) NTR SR0 candidate clearly passed the operational portion of the examination.

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, o Westinghouse NTR SR0 Exam Comments j

Attachment Comment H.01 No starting point was given for this question which may lead to a number of different solutiens for the first section of the desired curve. The i examinee couls assume that the initial fission rate was that associated with the intrinsic neutron level in the core and thus would not decrease as those in the key.

Examiner response H.01 Agreed - The answer key was changed to reflect the above comment.

Comment H.06 and H.07 Both of these questions are valid reactor theory questions, but really do not apply to the NTR since the restrictions on Power levels and the minimum integrated power effectively eliminates any " Decay Heat" or " Xenon and Samarium" buildups.

Examiner response H.06 and H.07 The examiner agrees with the above comment but at the same time the terms

" Decay Heat, Xenon, and Samarium" are basic nuclear theory concepts the candidate'should be familiar with and therefore, the questions are i valid. The candidate did well on the above questions.

Comment I.06A

Since the q'iestion did nu specify if the foil was irradiated or not, the answer could include the foils stored in the NTR Office File Safe.

Examiner response I.06A j Agreed - The additional answer provided above was added to the key.

Comment I.06C Samples that have decayed to insignificant levels may be returned to the NTR File Safe; however, often they are simply kept in the Radiation Safety Lap (HP Lab) safe until they are again irradiated for another experiment.

Examiner response I.06C

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Agreed - The additional answer provided above was added to the key.

Comment I.07 The effected wall may be described as the " South w?ll of the Penthouse" or " North wall of the Reactor Room."

Examiner response 1.07 Agreed - The additional answer provided above was added to the-key.

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, n Comment J.04 The answer may be derived from the Precautions and Limitations and Procedure for Experiment 2u in our Experiments Manual which includes reduction in trip setpoints for C1 and C2, lowering of Channel F neutron level trip, providing portable monitors, stable periods longer than 30 seconds, close monitoring of radiation levels in the control room and limiting reactor power to less than 2 watts. Reference Pp 20-6 to 20-10.

Examiner response J 04 Agreed - The additional answers provided above were added to the key.

Comment J.05 The answer key describes the supercritical reactor vice the critical reactor referred to in the question. At the NTR we can illustrate the respor.se of a critical reactor in the source range with Channel A. A critical reactor in the source range will be noted by:

1. No rod motion

2. Linear increase in power in the source range with the source installed.

3. Vertical trace with the source withdrawn.

4. The perico meter will tend toward infinity.

This is probably unique to the NTR since our source range power level is monitored by a linear recorder and the source may be remotely removed from the core. Period meter will tend to infinity.

Examiner response J.05 Agreed - The additional answers provided above were added to the key.

Comment J.06 Success is determined in Experiment 6 (page 6-3) by simply subtracting the shutdown reactivity from the total rod worth. In doing the initial core physics tests for this core the methods outlined in the FSAR were used.

Examiner response J.06 Agreed - The additional answer provided above was added to the key.

Comment K.04 The LCO for excess reactivity is given by two specifications (3.1.1 and 3.1.2) are shown to be equivalent in the basis. In 3.1.2 it states that the maximum excess reactivity that can be loaded into the core is 8.55$.

This quantity assures that spec 3.1.1 will be satisfied which states that the core must be able to be shut down by at least 1$ with the most reactive rod stuck fully out of the core and failures of experiments.

The pertinent basis section is on page 13 of the Technical Specifications.

Examiner response K.04 Agreed - The additional answer provided above was added to the key.

Comment K.05 Sections 3.5.3.1, 3.5.3.2 and 3.5.3.3 of the Ops Manual (P. 3-30-3-33) outline precautions, personnel protection and procedures for the movement of fuel. These points may also be given to answer this question.

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Examiner response K.05

. Agreed - The question was graded very loosely based on the above comment.

Comment L.01 The use of "Who" at the beginning of the question may lead the examinee to believe that only one person is desired as the answer.

Examiner response L.01 i Agreed - Examiner will accept only one (1) of the two (2) for full credit.

Comment L.02 Additional points should be added to this list. A summary of requirements are given on the " Reactor Room Entry Checklist" which is attached. Also it is now the practice of the instruction staff in training situations to require all personnel to wear lab coats, safety glasses and rubber shoe cover when entering the reactor room. 4 I Examiner response L.02 j Agreed - The additional answers provided above were added to the key.

Comment L.04 Answers 1 and 2 are no longer valid with the Technical Specification i revision included in the recent NTR Facility License renewal. Items 3 I and 5 are performed as a single item and are identified by a single title i

on the current surveillance list. Thus the list of quarterly

surveillances has been shortened.

j Examiner response L.04 1

Agreed - items 1 and 2 were deleted from the answer key and 3 and 5

combined into one (1).

Comment L.05 The Ops Manual section 2.3.3, Pp 2-8, specifies that a SR0 shall maintain the control board under direct surveillance when the reactor is not secured. Thus the Ops Manual is more restrictive than the Technical

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Specifications. Consequently according to the Ops Manual: L.05 A is l

False and L.05 B is True.

! Examiner response L.05 i Agreed - The answer key was corrected.

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Comment L.08 I There may have been a typographical error in the answer key. " approach procedure" should read " approved procedure" or " approved experiment"

! (Exp13).

Examiner response L.08 Agreed - The typo was corrected.

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L?. S. NUCLE AR RFGUI A10RY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION k'

REACTOR TYPE: NTR DATE ADMINISTERED: 85/06/20 EXAMINER: R.R.FERRELL APPLICANT: _________________________

INS T RUr T 3 0t!F. TO APPLICANT:

Uce separcto paper for the answers. Wri te answer s are one side only.

Staple ques. tion sheet on top of the answer shnets. Poi nt.s f or nAch questi or. tr e indicaind iri par entheses after the question. The passirig grada iec,uires at least 70% in each category and a final grade of et les t 80%. Enamination papers will be picted up sin (6) hours aftet the e:< smi nati on sta r t s . -

% OF CATEGORY  % APPLICANT'S CATEGORY VALUE 1 01. SCORE VALUE CA1EGORY 20.06 20.00 REAPTOR THEORY

________ ______ ___________ __ ___ H.

20.00 20.00 RADIDACTIVE MATERIALS HANDLING

________ ______ ___________ ___. .I. .

DISP 00,AL AND HA7ARDS .

20.00 20.00

________ ______ ___________ ___ .__ J. SPEC 1rIC OPEPAT1NG CHAPACTERISTICS 20.00 20.00 FUEL HANDLING AND CORE

________ ______ ___________ __ ___ K.

PARAMETERS

'O 0 ADMINISTRATIVE PROCEDURES,

_'__I_0___ .2'O 00_I__ ___________ ___-____ L.

CONDITIONS AND LIMITATIONS 100.00 100.00 , iOT At s FINAL GRADE ____ ,_________,%

All work done on this examinstion is my own. I have neither given nor received sid.

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hPPL5C5U5~5 556U55URE

H. REACTOR THEORY -

PAGE  ?

QUESTION H.01 (2.25)

Figure H-1 shows positive reactivity being inserted irito an initially suti-critical reactor. On the same figure, sketch the corresponding fission rate and assume no sour ce-sketch only.

1 QUESTION H.02 (3.00)

A.If during a startop,the count rate i s 40 cps,and Kcff=0.95,what will the count rate be where Keff = 0.98? [1.53 B.If the contr ol rods were moved an increnient of 2 inches to sc hieve this increase in econt rate.about how niany more inches would you have to with-dr*u tha rods to schieve criticality? Assume rod worth is linear n"et distance to be treveled. E1.53 DUESTION H.03 (2.00)

F::p l a i r. how a 1/M plot it uted to predict criticelity. In ynor antwer discurs tha variables that can affect the accuracy of the plot.

OUEF. TION H.04 (3.00)

Evpl eiri the f oll owing terms.!

A. Reactivity,p E1.03 B. Reactor Period [1.03 C. Prompt Critical r1.03 00ESTION H.05 (3.00)

A. State 2 purposes for the instelled neutton source i re the N-24-S cot e.

E1.53 B.Ideritify the source type and uri te the reaction that produces rmotrons.

[1.57

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(arrr* CATEGORY H CONTINUED ON NEXT PAGE maars) v v

H. REACTOR THEORY ,

PhGE 3 GUESTION H.06 (2.00)

What is the source of decay heat in the reactor?

QUESTION H.07 (3.00)

Explain the pr oduction and r emoval mechanisms for Xc-135 and Se-149.

i QUESTION H.08 (1.75) ,

A.If Keff of the N-24-S core were made to be 1.0016, calculatt the react-ivity insertion in%&k/k, t, and PCM. [1 03 E'.Caicolete the rescitant resttor period and SUR from this positive react-ivity i nsertion. Strte all a s s o nip t i o ns . [ . 7 5 7.

(rrrry END Of CATEGORY H a****)

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j I. RADIDACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS ', PAGE 4 V

00ESTION I.01 (2.25)

What are the weekly NTR Permissible Working limits for r adi a t ion e:<por ur e octablished at the facility for the followins?

A.Hesd and Trunk '

O. Feet and ankles C.St.in of the whole body E.75 es,3 QUESTION I.0? (2.75)

(..Where are the 3 aree samma monitors located in the NTR facility? r!.503 Er.What additions 1 function is provided by one of thi se monit or s tha1 the other two do not have? [1.253

, GUESTION I.03 (2.00)

Describe how to check if a low r ange beta samma instrument is functioning i properly.

3 00ESTION .I.04 (1.00)

If I-131 has a biologicel half-life Of 130 deys end c radiologicel br?#-

Ifre of B days, then half of the ingested radiocctive atoms will tr>msin in the body e+: (select one-no calculation necessary) ,

A.138 deys F:.73 deys C.B days D.7.56 days DUESTION I.05 (2.00) 4 What i ndi c t.ti ons must e::ist at the NTR to indiccte a contamination trchlem is present?

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(arrra CATEGORY I CONTINUED ON NEXT FAGE mamma)

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I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS .

PACF 5 QUESTION I.06 (4.50)

Gold and Indium f oils are f requently vesd as, irr adiation tsn.ples. Answs t the following concerning these samples.

A.Where are they stor er;? [1.253 B.How are they s.arted/ identified? , 02 M C.What happens to there samples when the activity has decayed to insignifi-cant levels? , E1.25]

DUESTION I.07 (2.00)

Why is the ' CAUTION-RADIATION AREA

• sign attached to the cover over the srett snce to the laddar leadirig to the NTO ' penthouse'?

00ESTIGN I.08 (2.00)

What levely of radiation would you e::pect to find in are s'rea s.arked ss fol-lows:

A.C(.UTION-RADIATION AREA C:.03 -

B. CAUTION-HIr.H RADIATION AREA r:.03 00EF. TION I.07 (1.50)

, Per 10CFR20 (St andar ds f or Protection agninst Radiation), give 3 torenris that would require notification to the NRC in the following tise fr!Fet!

A.Immer'iate Not ific ation E.753 I D.24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification [.753 1

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

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l J. SPECIFIC OPERATING CHARACTERIS11CS -

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GUESTION J.01 (2.50)

Answer the following questit.ns TRUE or FALSE.

A. Power is limited to 100 watts when an experiment is installed in the i reactor tank.

B.An unplanned or inadvertant reactor trip,in 14self constitutes en ABNORMAL occurrence.

A C.The higher differential worth of the shim ro,ds makes then, inapproprirte for making fine reactivity ad,iustments.

D.Dur ing contr olled critical oporttions at power levels in excess of shout 5,000 watteit i s permissable tte silence the Contiol Room audible alarn.

for the criticelity moreitor.

E. Power i e, liniited to 100 watts when the reactor is in the N-24-S configur-

r. t i o n .

[.5 es]

DUESTION J.02 (3.00)

E::pl ain the basis f or ' ,

A. Rod speed at 3.76 i n / n. i n . 01.53 I

B.24 cps at count-rate - cutout

• low' setpoint. t).53 OUESTION J.03 (2.00)

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Why is it preferable to operate at at low a power level as possible when >

o;< tended steady state operation is to take place.

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DllESTION J.04 (2.00) j When appronching criticality,under whst condition /s may the reactor be con-trolled by moderator level? Why are these condition /s necessary?

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QUESTION J.05 (2.50)

Doceribe how an operator can deteimine when the reactor is critien) du'ing otertup. Be specific in your answer and list at least 3 indications.

(umar* CATEGORY J CONTINUED ON NEXT PAGE uma'um)

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J. SPECIFIC OPERATING CHARACTERISTICS -

PAGE 7 OUESTION J.06 (2.00)

How was K excess of the core exparimentally deters.ined?

OllESTION d.07 (2.00)

Why are graphite rods a better reflector than weter?

OllFSTION J.08 (2.00)

What ere 4 purposes of the interlock system?

OllESTION J.0? (2.00)

Refer to figure J-1. Identify those regions indicated by ar rows A thr ough F.

A.

E: .

C.

D.

E.

(***rr END OF CATEGORY J **wsm)

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K. FUEL HANDLING AND CORE PARAMETERS PAGE 8 QUESTION K.01 (1.00)

Who must approve all fuel handling procedures?

DUESTION K.02 (1.50)

What 3 individuals can direct radioactive netterial handlins' operations (other than fuel)?

DUESTION K.03 (2.75)

!.What are the approved storage areas for reactor fuel in the Rt actor Ro o ri?

0.751 2.How sieny fuel elements can be out of approved storage arest et any tin 90 E.503 3.Where can the control rods be stored? t.503 4.Who cari aut hor ire the r enioval of Special Nuclear Material from the Reac-tot room? t.503

5.How n.uch Special Nuclear Material can be removed frons the Reactor Rooni at -

any one tis.e? t.503 GUESTION K.04 (3.00)

State the Tech Spee limits for each of the f ol lowirig A.Ma::i n.un, contr ol rod and moderator-shield water reactivity insertion rete. .

[.753 B.E:: cess reactivity C.753 C. Control rod drop time 0.753 D. Required moderator water level C.753

-0UESTION K.05 (3.50)

Briefly discuss 7 fuel handling precautions that you would outline to a closs of trainees who were going to unload the NTR core for,their first tice.

(xmswr CATECORY K CONTINUED ON NEXT PAGE manza)

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4 i K. FUEL HANDLING AND CORE PARAMETERS PAGI 9 s _____________________________________

00ESTION K.06 (2.75)

Describe the NTR Biological Shield.

QUESTION K.07 (4.50) ier each of the following NTR components,sive a brief descriptior. et appro-i priate.

A. Fuel enrichment.

B. Upper Grid Plate.

C. Lower Grid Plate.

D. Absorber materie).

E. Norms) Core Configutation.

F. Reflector. [75 es.3 I

j .GUESTION K.08 (1.00)

What persons 1 dosimeters must be worn by the work staff during fuel handl--

1 lang operations? _

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' END OF CATEGORY K mazza) e

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L. ADMINISTRATIVE PROCEDURES, CONDTTIONS AND LIMITATIONS PAGE 10 DUESTION L.01 (1.00)

A.Who cari author ire r adi c tiori e::posur e i ri e:: cess of the 1.25 PEM u h o ' s- b o rt .j l i nii t s ?

00ESTION L.02 (2.00)

List 4 conditioric that ni v s t be s e t i s f s eri i re o r rie r to allow per c nnr.o' to occupy the Repctor Roon,?

O LIE S T IO N L.03 ('.00)

A . V h t. r. i c. the r e r e tot c o n e. i rj e r e r; ' secured'? F1.03 D . Whe r, le the reactor c o n f i rie r e d ' c r e r s t i o ri r l ' ? T : . r?

OUTSTION L.04 (2.50)

L3rt 5 I t e ni t t S c t. hava t o b t- verifiert o,o r t t e t t y p t t the c o r v e i l l e n c r ' n.s t rit -

e fe& n c e sChedv}<* .

DUrS1!OU L.05 (2.25)

For the f ol l ow i ng c,.in s t i ons c oric er rii rig l i c erie < r: o p e r e t n r e. , a rir w e r TRtli er FALSE A.A 13 eeris ed SE N] fi 'L oper at or is not r e o u i r e r' t o be pr escrit when r e e nve- ) rig f r o n, en unplarined shutdown whan the cense h e r. b e r> ri identified. f.753 D.A licensed SENIOR operstor has to be present ori arey approrch to criticil-ity. f.753 C.A 15 censed SF N1OR oper at or a.o r. t t.e present dur ires arey change in the core configuration. f.753 (arras CATECOPY L CONTINUED Off Nryl PAGE rrrrr)

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^

L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITAT30NS PAGE 11 GUESTION L.06 (3 00)

A.Who has to review arid cpprove charige s in the oper stirig procedur e S t 01.03 0.Under what conditions can ten.por ary changes be nia ie to the opor tti ng pr o-cedur es? T1.03 C.What action is required ef ter the tenipor ar y change is n.ede? [*.03 00ESTION L.07 (2.00)

What a r e t h e nii n i n.u ni saftty systen, systen. thanrirls r equir ed t o net te i ster top o , the NTR?

OUEF1IDN L.00 ( ? . C t< 1 List 3 situtt ions dur i rig whs c h r r. i n t e r l o c l- een be bypassed. ,

DUEC1 ION L.00 (3.00)

Concet n.nc t he NTR EMERrJ NCY pl AN.gngwet the fol]owing quertions: -

A.Where is the PP! NARY EMERGENCY C.UPPORT CENTFR? t.A3 <

D.Where ear,the EMERGrNCY ALARM be sc.toated fron? r.63 C.Who essonies retponsibility for el) appropriate actions? t.63 D.Ureder whct e n titti tinra can not s.cl activities resumir at the NTR f ollowirig terniinstion of the incideret thit causod the En ergersey Plare to be i nip l a n - t ented? t.63 .

E.When era Enier gaticy Pl an dr ill s conducted et the NTRS C.63 t

P i

l Issen END OF CATEGDPY L sassa) .

(uwessnesasser END OF EXAMINATION sessansarsussum) 1 l

l I

s.

• o s/t Cycle efficisncy o (.etworv N

f o ca .

out)/(Energy in)

' 2 P . = ag . s = V,t + 1/2 at

{=

a = (Vf - V,)/t A = AN A = A,[ I' xi = 1/2 av ,

PE = agn

• /f = V, + at w = e/t A = an2/t1/2 = 0.693/t1/2 t

y ,y, -

1/2*II*EI*UII*S)3 ,

((t 1/2I

• II b)3 .

sE = 931 an "**

I=Ito 0 = aCp at 0 = UA at.

I = I ,e~"*

pwr = w ah I = I,10-x/ m f

TIL = 1.3/u 5

P = P 10 "'I*I HVL = -0.592/u p = p et /T .

o '

SUR = 25.06/T SCR = 5/(1 - /.df)

CR, = 5/(1 - Kdfx)

SUR = 25s/1- + (s - s)T CRj (1 - K gfj) = CR 2II ~ *eM Z) -

T = (1=/s) + [(s - s)71s] M = 1/(1 - Kgf) = CRj /G, T = s/(e - s) M = (1 - K,ff,)/(1 - K,ffj)

T = (a - e)/(As) SCM=(1-Kgf)/Kgf ,

• • = 10-5 seconds .

s = (Kdf"II/Ea# * #'KMEdf - A = 0.1 seconds *I e = [(&=/(T K gf)] + [fdf /(1 + AT)] -

Ijj=1d d I P = (I4V)/(3 x 1010)  ! d) I =2 1d 22 2 2 z = eN R/hr = (0.5 CE)/d (:neters) l I

R/hr = 5 CE/d2 (feet) )

Water Parameters .

Miscellaneous Conversions 1 gal. = 8.345 lem. 1 curie = 3.7 a 1010 dps l 1 ga.1 = 3.78 liters 1 kg = 2.21 1he i 1 ff = 7.48 gal. I hp = 2.54 x 10 3 8tu/ar Density = 62.41Wf-3 1 se = 3.41 x 108 3tu/hr Density = 1 gn/cW lin = 2.54 c:a -

Heat of vaporization = 970 Stu/lem 'F = 9/5'C

• 32 Heat of fusion = 144 Stu/les *C = 5/9 (*F-32) 1 Ata = 14.7 psi = 29.9 in. Hg. I STU = 778 ft-lbf

.Z

.f .' '.

EQUATION SHEET s

6=mAh -

g , CR3 CRo '

Q = UAAT A = 0.1 sec I Q = ac paT ,

1* = 10~ sec hg = kak'2 1 = 1,e-px Qc A " In 2 DNBR = -Qx C1 /2 P = Po10SUR(t) p = Ak/k P = Poet /T k' total - (hin ~ hout)DT g g , 26.06 A = AN T

,8-o N = Noe -At AD 1* 8-p 17.58 watts = 1 BTU / min T=7+ 3, ,

1 psi = 6.895 Fa kgf-1 1 psi = 2.036 inches lig 9 0*C

• I 1 psi = 27.68 inches N2 0 f 4'C k2 - kj A8

• k2kg CRg _1 - k'f f2 CR2 1 - k,gg g >

RR = Igeth S CR =

1 - k gg

_______--__j

b_'A54\

itM'iur'iASIER CORY H. REACTOR THEORY FAGE 12 ANSWERS -- WESTINGHOUSE ELECTRIC CORF -85/06/20-R.R.F E RRELL AN S L!E R H.01 (2.25) f'^Fi3Cgl-1 /, /2$ , , p ,,,. T 3 s'J ii O C')

N c. t e : T he # di s tirec t s vt- eorve trseet et e w ter t h E c a . A,'

ica 'J3tr CCAd Wiw SE wirT F FFIChapter 7,p.7-69 ANC,WFP H.02 (3.00) f, . Q = 1 - l' 7 C2 1 - 6: 3 C1= O. l~! 0.05, l'2=0.90 c1<1-et) 40(1-0.9.) . .

C2=1-U2 = (1-0.9n) f2=100 0 0.07 F: . p = I =0.9'. =0.0315 &l /t

• 6.03150 /6 = 6. 0157 A /6 For 2 t ri, of t r a v r.1 thir, gives a total of 4 ar. 3 r. .

A= &vn 1 rig t ht t the c orit r o l t ori worth r e n.a i ri n corit.t v.t over t h r. re- <r, e. f i re t t t e t t . t he r e qi.i t r e d r e a c t i v t v e dd s t n o re to ter-h critacelsts -

1.0-0.90 p= 0.98 = 0.0204 Al /6 i T r rvel =0.020t'/0.0157=1.29 t ri .

Rrr.0P Chapter B.F.8-27

H. REACTOR THFORY t A r.r 13 t NSWERS -- WESTINGHOUSE E L F C1RIC CORF'-85/06 /20-R.R.F ERRELL ANSWFR H.03 ( :' . 0 01 1/M=Co/Ci wher t :Circourit trio of the NI S c ha r. riel with r r e nc tivi ty chtrigt Cotha?e c o'8te t tF Ie LThi~r 't i the ' con ('i t 2 ons f or the bec.c c ourit r ste,t he . */N value le 7. A' t o Pr -

tivity 15 added.thr count rate ircreaset. The rip w r et v) .i t . ? t' o u ri t ret.e 501.

T h e i , # o r e- this 1/M value is leu thar. 1. F:y e nt e nd i r.1 the line t: , .o w t he -

Se points, to th* hor i: ont al e.:t s a predictinr. for critirai c o .ef i t t ni. 7 c r.

be o14, i t eet.

10 r,,

CO 'C 1 al Cor.di t 10r f or Crit 1C& 1 i t ,'

/

R e n e t i v i t .' C orid ) t t ore (hod ;;o , shi i 1/M oted dot i ng f otl loadir 3 of rod p.olls or. N1R.

REF.NTR Raqual T t e i rei r.3 Mar oal ,

ANSk'CF H.04 (3.00)

A . p si'e f f - 1 The f r ac tiorir ! charige of the effective nioltsplicattor.

6:aff factor f r o n. 1 [1.0]

I . T i n. e required to change- reactor Fower by a factor of e it.01 C.Resetor is cr i tieel on pr on.r t ricottores orily (np=I') [1.01 REF .Foridan.er.tal s of Re aci nt Fhytics

r 7 H. REACTOR THEORY PA0r 14 ANSWERS -- WESTINGHOUSE ELECTRIC CORP-85/06/20-R.R.FERRELL ANSWER H.05 (3.00)

A.1. Verify NI's are operable 2.Make a coritt olled appt oisch to eritienlity or supply ari .- n- c, o m t t - r.r ot i or, populetsori sveh that sube r i t a r e l niol t t pl i c e t t or, c a r. ba obt9tved si t e e-reactor approachee criticality T.7' t-'

E; . Sour c e : P u-E:e . 2 C i r.001 239 4 235 4 13

• 17 to x Cd + U Ck l C3 C 4 ! r s o

• r e r.

e4 2 9?  ? /, 6 '1.01 RE".NTF F w,vi l i f a c t t r or. Ttstriar.- P : r.o r '

ANSWrF H.0A r2.00)

/.t i eriva t t ori cf t t e b t t r. rr d y m n.s f r o n. f i u or. I t odne t 6 t re r onet or t. '.i-1I)t F f r . F urid a n,r r.t I t of Rt se t or Physter A t'S W C: H.0' (3.00)

Xe ic c dr.o;5ter of T which i s a dr.oshi r t of Te ( a fisstor, product 7. vt also i* 7 dir-rt fistson prodort. It can be rnn.ovad by decry t r. C.eson ce

'bortop' by abroeptiori of t thernial n e u t r o re . [1.51 Se 15 a daughter of F r o n.a t h t o n. ( fornied by f i r r i ori and also e daughter of t:( u d y n. i v n. ). It can be r en.oved by ' bur riop' e but St it stabic. ft.51 Xo PRODUCTION: Direct F1 tenor, rie e a y ( 5 b 10 ', CD-31Te135 00-3>I135 ti-3 Xe135)

REMOVAL! Deray (Xe135 CE-P Ct,135)

Ournop ( neott ori obsorptior )

Es, F'RODttCTION: 03 rect F i t s t o ri Derfy (Ce149 ( 0-D Pr 149 CD-3?Nd149 C D-3 > F e.14 9 [0-31Sn.140 REMOVAL!0venup (neutron abf.orption)

R E F . Funda n eret a l s of Reartor Fhyr.:es

H. REACTOR THEORY PAGI 15 ANSWERS -- WES11NGHOUSE ELECTRIC CORP-85/06'20-R.R.FERRELL ANSWER H.08 (1.75)

A.Mcff = 1.0016

~~

.06: 6 = .00: 67 1.0016 L 160 PCM = .?f 8 00 P C M ,' t 1 1/.0 PCM F:.FW Perten' l p= Toff A t e, i i n. c I = .00000 l 1 +7i , - -1 p + PAT = Urff h .1 a s,c I. - p .00F .fO'/ ps . 0 01/.

l T= 1 = t . l a s .00; . ) e 40 ne l S L' R =  :'6.06/T = "6.0L/40 = .(S DPM REF.N1F Ptc,os' T r a t r.f rij tit r.i> > 1 l

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M9 =HM M}' wM ~. ...-.- ~= f - t1. W mW

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g n .m m m m m._______ ___m_________ __ m__.

I. RADI0 ACTIVE M ATERI ALS HANDLING DISF'OS AL AND HAZ ARDS T Aril 16

_______s._______________________.______________________

ANSWERS -- WESTINGHOUSL ELEC1RIC CORP-85/06/20-R.R.FERRELL ANSWER I.01 (?.25)

A.300 n.Ren.

~

F: .19 7 5 n.R o ni ~~ ~

C'. 7 *,0 n. F o r.. f.75 o,.3 RE F . Ope r a t i rig Me rios 1, p . 3- 01 ANSWER I.0? (0.75)

A . C o re t t 01 Roon, E rit t y w a y R t. a r t o r Roon. [0.5 ei.3 E; . R e a c t o r R o o n. - a t e s n.o ri t t o t s. r . r'. e i t a c a l l t y n.orii tot for fnel s tot . ie 4 er Level n.e t e r s rid n ud i t 1 r a l a r n, ore tt e reertor coritto) tic a t ri (1 251 REF.Or5 Mr rioa l .p. 3-00 23 ANSWER I.63 (0.00) 1.Chac6 the teatter y 2.Ute a s a n ti.e s o.ir c e to e resur r rest.orisc 3.Chec6 the c a l i br r t i ore sttetat f.66 e #, . 3 R E F . 0p e r a t t orni. Ma rina l e p . 4-5 ANCWrF I.04 (1 00)

D.7 56 days E f f , e t t v e h t,1 f -11 f e a l f. n T R /1 r< + T f' REF.Cherter 4,p.4-50

I l

i .

I 1. RADI0 ACTIVE MATERIALS HANDLING D1GPOSAL AND HAZARDS P A Ct. 17 ANSWERS -- WESTINGHOUSE ELECTRIC CORP-85/06/20-R.R.FERRELL AN0uCR I.05 (2.00) rneet saniples-200 den beta geninir of to dpni alphr. activity pei 1 0 0 ., g.,e r e i e n. of s nie a r ar&0 REF. Ops Mer.uclet.3-25 l

l ANSWER I.06 (4 50)

C1.203 A.Fadtrttob cA N T h C.if as@esafetv.

iti 'a e h- Lab r,itored i r. c riv a l o p e s t.53 nar6ed with a r a d t e t t or, w a r re i r.3 s v eib o l C . '. 3 ti.d 1sbeled C.253to show the tin e of ittadiatinri C.253etypt ca n.rtet3a1 [.0b3 ored degr ee of br:ard t revolved (activity erid/or dose rate) C.253 (?.03 E.N1R Fec111ty file safe (1.0L]

l c ., tw +o c ' . " L"i$

REF. Opt Ma riva l e p . 3-29 l

ANTNEP I.0? (2.00) '

I

. u P

l $

l Dut t r.3 full power operrtions the r adt e t s cr It-vel s e t the south wa11'v 11 be I

tri the order of 30 to 40 n.REN/ hour due to 'shirie' ered tre t ter iria f e r n, the r e m e t t.t . Aw .9 . N u'a * % i ' 6'

l R E r . N T R R ew,vt l i f i c a t t or T r a i r:1 r.3 F r o g r a n, .

l ANSWER I.08 (0.00)

A.5-100 ni t EN/ht (1 03

[: . ' 300 n, REM /hr et 100 n.REN t r. . riy 5 cores,ecutive drve (1.01 FFr.10CFF00.00?

l i

O l

I' A f,I 1H l I. RADI0 ACTIVE MATERIAtS HANDLINC. DISf05AL AND HAZARDS ANSWERS -- WFSTINGHOUSI EL EC 1RIC CORP-BL/06/20-R.R.FERRELL ANSWER I.09 (1.50)

A.Whole body enpoure ' 2 5 R E M i d i r. '- 150 REMicutren.ities ', 375 RLM F;e l e s m e s > 10CFR20 l i ni t t s ( 5000 t i n,es ovt r 74 hour8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />.)

~ ~ ' Logs of T* wor 6 i@eet of oper a t i otie D s. n,5 0 e to property of i 1000,000 C3'4 <- i .75 er3

[:.Enposure to whole body L REMis.htn 1 3 0 R E M i rn :t t e ru i t t e , 7L REM F;eleases > 10CFRTO l i n. s t s ( 500 t inic a over 74 hoor+)

L o t e, of 1 day of operatiot.

(3/4 ** 's e,2 O r n. e 3 e t o pr of.et t y of t?.000 .

r;Er.10CFR:0.403 l

l I

l l

l

r J. SPECIFIC OPERATING CHARACTER 1STICC FAGE 17 ANSWERS -- WES11NGHOUSE ELECTRIC CORP-05/06/20-R.R.FERRELL ANSWER J.01 (2.50)

O.TRUE E: . F AL SE C. FALSE D.TRUE E. FALSE f 5 et.3 REF .0F'ER ATING Pr:0CEDURCS.pp . 4- 4 3 4 4 50 ANSWER J.00 (3.00)

A. Rod 1 peak diff. worth i s app .10 F C M/ . 01 T Tech Spec. 11 si t t t .035/sec=20 T't M/u (

(Ucfff. 99)

Therofore n.aq eod sperd tllowable 20 PCM u .01T n /0 ver n 4.7 t r. = 4 .'70 i r, se- TTi"TC M p. t r . . F v t re . n. t r. . -

Ther ef or e1st 3. 7 e. t re / ni f r. t h e- resetsvaty a rid i t s r>re retc is < .00'.1/>ac

[1.53 F. . ".e rit i t i v i t y o f d e t a r t o r 0. 33 c t.t /riv T e c h S p t. r . 2 5 re v (2 5 rev)(C.33 ept /riv)=20.05 ces 24 ept i s coritet vative [1.L3 REF .04-R equa 11 f ic e t s or. T r a i r:1 ris f

• r o g t o n.

ANSWER J.03 ( ;' . 0 0 )

T o e,i ri t a.1 : e t h e total 1ritegrated power R E F . O p t. M a riis a l , p . 4 -4 4 A__-_-_

r J. SPECIFIC OPERATING CitARArTERISTICS P A r.L Po ANSWERS -- WESTINGHOUSE ELECTRIC CORP-85/06/20-R.R.FEPRELL ANSWER J.04 (2.00)

O ril y wher, the rcarior la fir 5t n. e d r erit 1 cal by ecrit t 01 r o r' niovt.t c rit t . Thi-o s s o r e s- that t he cm.t r ol t r.c 19 the pr i n.o r y n nde of reactivitt e nr.t r o l t r> c tritioni r eart or .

.w < t ri R c t% s g .. . .. T h . - h t. . . . . rtr'4 4 ,k...m FEF.TS,3 1,p.7 p u. c.u m ,,cd % ate,,51s,gpa,a u,j st,w, .,g, gs1, \irr.

1,, , n . ,,

C e'k m o c s: n ,,y ,c y u m., ,, , ,' 6 u t n u Q n g i . e U t . ,,; i - u ANtprr a,o5 (p,5oh""'"tt.ni%  % #

2 w N>

W ii h pa r i od nie t e t . t r.d f l e- 1 rit t i e n.eret t [1. 03 whe r e w i t h rio t od niove r,ie rit f l o:

t re c t r on.e rit e ir.dteste a rt(rt i t.c t s . a e t re power t.753 ared a cor e tcrit p o s i t t s.

pr-rtod is t r.d t e c t t 6 c. r . t6 p t 3 r.r' r.. e t e t s L . 7 5 3 [1. M PEF .0; 5 ft : riv e l , p . 4 - 4 5 lb -]'y g ,,, g c 3,: u . r , *g . s i t C TDtt: D A tt C W T f- J.06 ( .00) u,.m 1,uu Wh e m I'ik "

• W

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• • • • n

Iy p o i e.1 o te t r.g thc cori w i ', h t, t d . t t 51 til ez u, *.tcol tods.:1vn.trivr. 1 reset i e a rid te ni e t a n t a r.3 t h e reertisity worth of the poitier, rods ar d the p o t t i c.ri t of

• ht coritt ol fods at:11 ir. tht r or e et t y n. e e r. , the differrro1a1 r<e wctthe n r. the reor n.51 rot e.  % g3 .u .. , n y t g ,w ,g m ,g g -us gy g ,. , j 7, 4 Ftr.FCAD 111-104 R W .h o v. a.t +4 ANSWCF J.07 (?.00)

Mod ra.tio = $S$

f.s (o (gtsphats) -

(s ( witor i Theretore M.F. (g*4.rhais) . r'.P. (watet) 6a (F 0$ = . M barro '

? .'

cts. (C )= 9 : 10 bi r ro.

10 FFF.NTR Requal T a i re a rig N a ti st. i )

I.

J. SPECIFIC OPERATING CHARACTERISTICS PACE 21 ANSWERS -- WESTINGHOUSE ELECTRIC CORP-85/06/20-R.R.FERFELL ANSWER J.08 (2.00)

1. Correct sequerice of oper at j oris pe r f o r nie d

2. Positive reactivity added by orely one piesris it a tinie 3.Irisur es pr oper a rid s a f e teattor coridi t t oris es:is t 4.F er nis ts entr y of reretor roon. Under specified coriditions wi th r e a c t r. ' c.ri '

but pr everits additiori of positive r eactivity dur ing this eritty

5. Assures reactivity addition r ates not er:cceded to/5 at .5 er3 RE'F.FSAR III-61 thru 65 ANSWTF- J.09 (2.00)

Refer to figure J-1 A.Li n.1ied F r opor tionellt y 0.Iorii::s tior Chan bt r regior.

C.Geiser Mev11er F o g i o r.

0. Rec on.birit t i ori Regi on -

E . C o rit i rii oo t Disc har gr Ecss ori F .Pr opor t a orit l Regi ori REF.4,Chrpte-r 2,p.2-4

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Characteristic Curve of a Cas-Tilled Detector

K. FUEL HANDLING AND CORE PARAMETERS P'A G E 2? '

ANSWERS -- WESTINGHOUSE ELECTRIC CORP-8S/06/20-R.R.FERRELL l ANSWER K.01 (1.00)

Facility Manager

-REF. Ops Manor 1,p.2-3 ANSWEP 10 . 0 2 (1.50) 1.SRO 2.Radi atior. Saf ety Coor di rer. tor 3.u1C staff mtnber deemed caprble by the N1R Facility Mariage r t." es.3 ,

REF. Ops Menotlep.2-0  ;

ANSWER K.03 (?.75)

A. Reactor core Fool stoisse ares 4 fuel storage thin.blen in the Rs actor T e r l- f.20 co.3 B./ t.503 _ ,

C. Appr oved Stor age Re ct (? Incations) t.501 D.NTR Facility Meneset t . 5 07.  !

t.500 gran.s t.503 RE".Opi Minoslep.3-28  ;

ANSWFR K.04 (3.00)

A.O.10t/see when Peff is <0 99 ph W AAa>Pr4TS & 6Dh  ;

0.03L5/see when Keff >0.99 t.753 B.3t C.753  !

C. Full out'to full in at < 1.2 see which include- a situ carriage relcrrr  !

t1me of 0.125 sec, t.751 1 D.S ft. above the top of the core C.753 REF.TSep.5,6,13,14 l I

l 1

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F K. FUEL HANDLING AND CORE PARAMETERS PAGE ?3 ANSWERS -- WESTINGHOUSE ELEC1RIC CORP-85/06/20-R.R.FERRELL ANSVER K.05 (3.50) 1.SRD in charge-follow his direction

2. Adequate SDM (tt least 3 t) 3.R e qu i r e d ' i'n s t r UiTUIt a t i on- 1 SR w/ audible count rate a rid i nt e r coni wor t.ing 4.Use of handling tools and equipn.ent

5. Recor d siovenient of fuel

6. Personnel dosinietry, portable survey instrunients and protective clothirig

7. Initial radiation sur veys and es tinistes of e::posure

8. Plan job rotation

9. Job r+sporisibilities and tacts 10.do not rush.htndle fuel car efully to avoid mechanicel d e nia g e C 7 /16 at .53 REF. Ops Manual,3.5.2.p.3-16 ANSWER K.06 (2.75)

Core is surrounded by about 3 feet of water at the sides,sbout 6 feet of er ter at the top. Core is located about !! feet below ground level. Ther ef or e _

the ear th and c eniorit dunip tent str or tur e af for d shiriding in sideuar d da r -

ectiores. A cone of radiction is en.itted upward in the antiolos betwears the don,p arid i e me tor tanks e li n.itiris power levels to 10 Lw PEF.75Appenefix A.p.A-4 ANSWER K.07 (4 50)

A.93.5% U-235 D. Alunii nusi,1 inch thict , elongated he::asonale shape,with 93 position holes C.A1,"51 in.in dia.,4 i ri. thi ck at edgen,6 in. thick in center,with properly positioned holes. Located 44 in.below the upper grid plate. This piste is directly coupled to reactor tank flange.

D.Cadsive E.19 fuel elements and 5 control rods and followers configured with dctect-ors and source as in NTR-RX-1. Cs11ed N-24-S if all 19 elements ate ctrn-dard.

F. Light water," 2 feet thick,and graphite cylinders REF. Ops.Manuel A-2,3 C.75 e,J

f K. FUEL HANDLING AND CORE PARAMETERS PAGE 24 ANSWERS -- WESTINGHOUSE ELECTRIC CORP-B'J/06/20-R.R.FERRELL ANSWER K.00 (1.00) 1.Neutr on and E: eta-Gen n.a t ensi tive TLD

2. Direct recdout pc.eket son t h e n.b e r s C , *: ea]

REF. Ops Menval,p.4-3 A_ - _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ . _ _ _ _ . _

l L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS P'GE A 25 ANSWERS -- WESTINGHOUSE ELECTRIC CORP-85/06/20-R.R.FERRELL ANSWER L.01 (1.00)

Site Radiation Officier and the N1R Manager Anst AGeTT EME D REF. Ops hanut-1,p. W O ( ODU ANSWER L.02 (2.00) 1.2 people ir visual contact ( 1 must be are authorized individual) 2 . R :: suberitical by at least 31 (2400 PCM)-no remote changas which c o u l ri produce + resetivity effects

3. Audible s i g ra,1 of R:, sour ce multip1icetion

4. Personnel dotinntiy nost be worn 5.Personnr-1 e::iting must he n.o re i t o r e d for c::t-r n;1 contrninetion 6.Ettingedtinking.or smoting is prchibited 7 F.o c u r a v n.a l l sten.s thtt could fall into the t a ni [4/7 et.5 es.3 AboiT m At Mc.s .pctm e r a.TS s o n Arrou+t ti O R F .Oper ; i i ores M isti u s ? , p . 3 - 4 0 ANSWER L.03 (2.00)

A.Conti ol rods fully inserted and the master powtr svitch Iey is ts-n.oved fron. the switch OR no fuel in the core C1.03 F:.When it i t, not secured r!.02 REF. Ops Manual,p.3-41 ANSWER L.04 (2.50)

Any 5 of the following ct .5 each 1.Ar== *2d =-i tor-/por 4.abis+stvey ir.c t r ument- +cel-ibt ation S tT M c D (.65 L W iT 2.0eer eM r c o r.t F a i r. a t i e r. a s e s ; . e e; r,' - - - -

' #w 1-elements TgeSen bou-

@X,'3.Lest-test of sesled rediation sources

4. Emergency cabiriet inventory and eqpt. inspection

5. Inventory of radiation sources

6. Reading of environmental monitoring badges

7. Sample of ion exchanger beds for low level contan.inetion 8.Socurity key inventory 9.Socurity systen. tests and inspections REF. Ops Manual,p.5-6

r L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 26 ANSWERS -- WESTINGHOUSE ELECTRIC CORP-85/06/20-R.R.FERRELL ANSWER L.05 (2.25)

A.TRUE F: . r A L S E

---

C . T R U E [.75 eel REF.TS,p.38 ANSWER L.06 (3.00)

A. Review of RSC Appr oval by f acility nianager T.5 er.:

E: . D o not change the intent of the origint1 prcredore/npproved by fFci1:ty nansger E . 5 e r. 3 C. Recorded in the opercting r ecot ds Repor ted to RSC [.5 er.]

REF.TS.p.44 ANSWEP L.07 (2.00)

A.Meff <.99 1 Linear-Log N level with high N level trip 1 Linear-Log N level E:.Keff > .99 2 Linear-Los N level with high N level trip 1 Period with trip 1 Linest or Los Gsmnir f.evel with trip REF.TS,p.51 ANGWFR L.08 (2.25) iey-on rcom entry Donagenient authorization in writing apr"cech pr ocedur e( n ra mssd 0.75 es]

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