ML20155G252

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Exam Rept 50-150/OL-88-01 on 880503-04.Exam Results: Both Candidates Passed Exams
ML20155G252
Person / Time
Site: Ohio State University
Issue date: 06/08/1988
From: Damon D, Jordan M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20155G243 List:
References
50-150-OL-88-01, 50-150-OL-88-1, NUDOCS 8806170225
Download: ML20155G252 (47)
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Text

1_ -

-5 U.S. NUCLEAR REGULATORY COMMISSION.

REGION-III

-Report No. 50-150/0L-88-01 Docket No. 50-150 License No. R-75 Licensee: Ohio State University Nuclear Reactor Laboratory 1298 Kinnear Road.

Columbus, OH 43212 Facility Name: Nuclear Reactor Laboratory Examination Administered At: Ohio Sthte University, Columbus, Ohio-Examination Conducted: May 3-4, i s Examiner: hf!f8 Date D.Q.Vamon Approved By: Ah, '7M

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[ /!88 Ofte /

K ael J. Jor 0 rator Licen gv5ection 1

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Examination Summary Examination administered on May 3-4, 1988 (Report No. 50-150/0L-88-01))

Examinations administered to two Senior Reactor Operator candidates. 1 Results: Both candidates passed the examinations. )

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8806170??5 880610 PDR ADOCK0500gO N

{

t REPORT DETAILS

1. Examiner D. J. Damon
2. Exit Meeting

~

On May 5, 1988, the examiner met'with R. D. Myser to discuss findings made during the examination. Due to the limited number of candidates, no findings of a general nature were made concerning candidate strengths and '

weaknesses.

The examiner did note that not all preventive maintenance items had an associated written procedure. Mr. Myser agreed to review the need for written procedures for maintenance items that currently do not have a procedure.

3. Examination Review The facility comments on the written exam and their associated NRC resolutions are attached.

Facility Comments Comment H.03:

I can work through the problem in one of three way none of which is particularly easy to ascertain correct answer. They are listed below:

1. Similar to how you worked the problem.

C2 = 1-K i C1 1-K2 1- K 2 = l-K i C2 j i C1 1 1-K 2 =

(1-K ) 1 t

3 1-K 2 = 1 -

1K i 3 3 l K2 = 2 + 1K 1 3 3 The value 2 shows up but I'm not sure how to interpret this,  ;

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- - - . . - --- ---- . - , .,. - - - - , . , , n-- e e

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2. Similar to above except using real values for K tand C1 and C2 is a littler easier to understand.

CR t = 10 _ K 1 = .94 CR 2 '= 30- K 2 =  ?

30 =-1 . 94 10 1- K 2 1-K2 = 1 .94 3

1-K 2 = .02 K2 -Ki = .04 = 2 K2 = .98 Crit.-K 1

= ,.06 3

3. Using an equation from another training manual.

=

M 1 Where X is the fraction toward critical and M is the count-1-X rate multiplier, in this case 3.

3 = 1 3-3X = 1 3X = 2 x = 2 1-X 3 Again this works but why seems rather ambiguous.

I don't really have a recommendation for how to grade or improve this question. In my judgment it is too ambiguous.

Resolution H.03:

Comment Accepted. Credit will be given for alternate ar.swers that are supported by applicable formulas.

Comment H.05:

An additional correct answer is to utilize the gamma ray spectroscopy system (analyzer) to identify the radioactive materials present.

Resolution H.05:

Comment Accepted. Answer key expanded to include additional correct answer.

Comment H.07:

From another training manual it indicates the correct answer to be "critical".

I have attached a copy of the page (Question 203) for your review. I believe that if you keep the "units" as K then the answer is critical. If one converts K to reactivity then the answer appears to supercritical.

3

1 3

1 Due'to the conflict in training materials, I would suggest credit for either critical or supercritical. Also I don't think Section 5.14 of Glasstone & Sesonske is the proper reference for this question.

Resolution H.07:

Comment partially accepted. Keeping the "units" as K is acceptable when K is sufficiently close to 1 so that K is linear with reactivity. Generally, reactivity is a log function with K.

Answer key modified to include critical as a correct answer if the assumption is stated that K is close to 1.

Comment H.09:

Please refer to Appendix H of RS-06 on the calibration of the PNR-4. The correct answer should include at least an awareness on the part of the exeminees that the source actually increases with time up to a point. I have included a copy of the discussion about source increase for your information.

Resolution H.09:

Comment accepted. A discussion of the source counts increasing will be <

accepted for credit.

Comment I.01:

"Supplementary" surveys are done as deemed necessary by the SR0 on duty. The phrase "whichever is most frequent" is weighted too heavily in relation to the other parts of the question. Perhaps make all parts worth (.33).

Resolution I.01:

Comment accepted. Point values redistributed.

Comment I.02:

The Eberline R04A air ionization chamber will detect both (f) Otr.ma and beta radiation.

Resolution I.02:

Comment not accepted. No additional materials sent to support the facility comment. The reference cited supports the original answer. Answer key i remains unchanged.

Comment K.03: l l

Reg Rod Shim-Safety Rod Smooth Grooved  :

Solid Hollow Ref. Fig. 4 OSU Reactor Control Rod Poison Sections.

l 4

l Resoultion K.03:

Comment accepted. Answer key expanded to include additional answers.

Comment K.06:

Only answer 1 to this question is correct. Answer 2 is a correct statement but does not strictly apply to the question. Perhaps delete part two.

Resoultion K.06:

Comment accepted. Part 2 of answer is deleted and point value adjusted accordingly.

Comment L.01:

The correct answers for d. and e. are reversed. Correct answers are as indicated below:

d. (80% full scale on any range; this is the same as 120%).
e. (150% full power; this is the same as 15KW).

Resolution L.01:

Comment accepted. Answer key modified as requested.

Comment L.05:

The correct answer should be that one person is required to be in the control room any time magnet keys are unlocked and in the control room.

This one person can be an R.0. or an S.R.O. It must be a licensed individual.

Resolution L.05:

Comment accepted. Answer key modified as requested.

Comment L.09:

The important part of this question is that the examinee realize that a licensee from the University of Wisconsin is not valid at the OSURR.

Therefore, the individual from Wisconsin could not perform a startup by himself. However, it has been the practice at the OSURR to interpret 10 CFR 55.13(a)(1) rather broadly. As a part of the individual's training as a "student" we would allow a visiting professor to startup the reactor if we deemed it appropriate. It is standard practice to allow legitimate directly supervised operation of the 05URR by as many "students" as possible. We define a student similarly to Webster's New Collegiate Dictionary as:

1. Scholar, learner.

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2. One who studies: an attentive and systematic observer. .

I would recommend the following point distribution for this question.

(1.5) for recognition that the Professor could not operate by himself.

(1.0) for familiarity with 10 CFR 55.13.

Resolution L.09:

Comment not accepted. Per 10 CFR 55.13(a)(1), a "student" is defined as follows: a person who'is in training for a license on the reactor, or a person who is enrolled in a course that includes manipulating the controls of the reactor as part of the course. No other definition of "student" is in keeping with 10 CFR 55. Thus, the visiting professor is not considered a student unless enrolled in a course to manipulate the reactor.

Credit will be given for a "yes" answer if.the statement is made that the professor is at OSU as part of course work and performs a startup under supervision as part of that course.

The answer key remains unchanged.

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l MASTER COPr

.. s NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the f ollowing rules appl y:

1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2. Restroom trips a e to be limited 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 possibility of-cheating.
3. Use black ink or dark pencil only to t'acilitate legible eproductions.
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).
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.
8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a ngw page, write gnly gn gne side 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 th[ee lines between each answer.
11. Separate answer sheets from pad and place finished answer sheets face down on ycur desk or table.
12. Use abbrevi ations only i f they are commonly used in facility LLtecatuEe.
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 PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
16. If parts of the examination are not clear as to intent, ask questions of the examinet only.
17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.

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.' 18. When you complete your examination, you shall:

a. Assemble your examination as f ollows:

(1) Exam questions on top.

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

(3) Answer pages including figures which-are part of the answer,

b. Turn in your copy of the examination and all pages used to answer the examination questions.
c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.

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DOIO_EUEEI BE8CIQ8.IBEQBY EQBduL8S:

'* SUR(t) p = p et /v p,p g E I th

SUR = 26.06/T p = 3.12 --------

x 10 J --issions/see f

1 2 1 eff p , ,-(B Lg 2) 9 = -- + ------

g+ gy th 2 2 y 1 + (B Lg )

2 g 2 K- 1

-(B 3 p = _____

Pj =e f K

K A0 = In i!O*l--

p , ,-CN3C1,,,3/lE initial

'N Cg - (1-Kgj g) =C T " ~Efi ~~~0 2 (1-KHf 2} $

m=-- = 1!O*1-- 7 .

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initial 2 2 1 of 1 op AL 2 , __f _ + A L__g3_,

a = - -- + - -- - B 7

f at p at at at .

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pP g fn p =p _eif___E_O Kg=( P g Inff P1

- -- - - - - - -- --..,-.,,.r-,.-_ -_ _,,.,__,.,. ,,--- . , - , , , , . .

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2 w LAT g . _______________________

1 In R2 /R 3 in R3 /R 2

=UA (AT,) - + -------- + --------

K K K 2 3 G = m. c (AT) .

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Q (h -hout) ideal in in W PV g g Pv 22 actual yP W T T supplied 3 2 A = pAV pAV gg 3 = p2 Av 22 3

$ = KA J 6P p x

A nc

= KA Q

E = KA ST M = KA op 4 oP E

AT (in) - AT (out) th AT

= ------------------ G = -f ------

AT (in) 8.Bx10 in (--------)

AT (out)

Gr ,

kAoT T -T = --- Q = -----

c1 ps 4k ox .

, total Q = gg--- gg-- oX a b n

___ + ___ + , , , + ___

K K K a b n

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Ng sg W)g Hg g Pg N 'h (N ) H (N ) P 2 2 2 2 2 2 88D18I1QN_eUD_GUEd1518Y_EQBduLOS:

R/hr = 6CE/d I = 1 0

e CVg ga C 22 G = Qilutign_Batt I=1 0 Ill "

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Volume 10 A=A O

e A = AN l CQUMESS1QUS:

1 gm/cm = 62.4 lbm/ft Density of water (20 C) = 62.4 lbm/ft 1 gal = 9.345 lbm 1 ft = 7.48 gal Avogadro's Number = 6.023 x to 1 gal = 3.78 liters Heat of Vapor (H O) = 970 Btu /lbm 2

1 lbm = 454 grams Heat of Fusion (ICE) = 144 Btu /lbm

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

1 HP = 2545 Btu /hr 'C = 5/9 (*F - 32) 1 Btu = 778 ft-lbf 'R = 'F + 460

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

-21 h = 4.13 x 10 M-sec 10 1 W = 3.12 x 10 fissions /sec 2 2 g = 32.2 lbm-ft/lbf-sec c = 931 MEV/ AMU 1 inch = 2.54 cm C=3x 10 m/sec

~0 4 r = 0.1714 x 10 Btu /hr ft R

, DOIO_SUEEI BYEBeGE_IBEBdeL_CQNDUCIIVIIY_1El dataCtal K Cork O.025 Fiber Insulating Board 0.028 Mrple or Oak Wood 0.096 Building Brick O.4 Window Glass O.45 Concrete 0.79 -

1% Carbon Steel 25.00 j 1% Chrome Steel 35.00 '

Aluminum 118.00 Copper 223.00 Silver 235.00 Wster (20 psia, 200 degrees F) 0.392 Steam (1000 psia, 550 degrees F) 0.046 Uranium Dioxide 1.15 Halium 0.135 Zircaloy 10.0 dlSCELLGUEQUS_INEQBdGIlON:

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

=VO + at Geometric Object Area Volume

  • Triangle A= 1/2 bh /////////////////

2 Square A=S /////////////////

Rectangle A=Lx W /////////////////

Circle A = nr /////////////////

Rectangular Solid A = 2(LxW + LxH + WxH) V=Lx WxH 2

Right' Circular Cylinder A= (2 nr2)h + 2(wr2) V = nr h 2

Sphere A = 4 nr V = 4/3 (wr2) 0 Cube ///////////////////////////// V=S

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10 CFR 20 Appendix B l Table I Table 11 I

Gamma  !

Energy Col I Col II Col I Col II MEV per Air Water ,

Air Water Meterial Half-Life Disintegration uc/ml uc/ml uc/ml uc/ml  ;

-6 ~0 Ar-41 1.84 h 1.3 Sub 2x10 -----

4x10 ------

~7 3 1x10 ~0 ~3

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Co-60 5.27 y 2.5 S 3x10 1x10 5x10

~

D -1 -7 9x10 '

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1-131 8.04 d 0.36 S 6x10 1x10 3x10 i

~3 ~#

Kr-85 10.72 y 0.04 Sub 1x10 -----

3x10 ------

-7 ~0 ~

Ni-65 2.52 h 0.59 S 9x10 4x10~0 3x10 1x10 "

~A2 ~

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

  • 6x10 5x10

~ ~

0 ~ll Sr-90 29 y ----- S 1x10 ' 1x10 3x10 3x10'# I

-6 ~#

Xo-135 9.09 h 0.25 Sub 4x10 ----- 1x10 ------

I Any single radionuclide with T > 2 hr -10 -6 which does not decay by alpha br 2 -9 ~

3x10 9x10 1x10 3x10 cpontaneous fission 2

Neutron Energy (MEV) Neutrons per cm Average flux to deliver l equivalent to 1 rem 100 mrem in 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />  ;

t thermal 970x10 670 l 0.02 400x10 6 280 (neutrons) l 6 30

  • 0.5 43x10 --

3-----c 10 24x10 17 cm x se Linear Absorption Coefficients p (cm-1)

Energy (MEV) Water Concrete Iron Lead 0.5 0.090 0.21 0.63 1.7 s 1.0 0.067 0.15 0.44 0.77 1.5 0.057 0.13 0.40 0.57 2.0 0.048 0.11 0.33 0.51 l 2.5 0.042 0.097 0.31 0.49 l 3.0 0.038 0.008 0.30 0.47 i

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U __0UBGIRB_IdEOSY PAGE 2 i .

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OUESTIOf! H.01 (1.00) 14r i r 1 y c::pla.n the difference between K effective and K infinity.

DUEG7 IL'N H.02 (3.00)

De r.,c r I b e wh a t tu reecnt by each of the f ol) owi ng t.er m s : (.75 ea)

,. Frompt i, cut ron e

b. E . ] 6ty #:i Nettt rons
c. F:st IJet tt r ono
d. ^l 'u >r m a l leutr on s CUCST)DN H.o~ (1.S0) 14 the c ou r.t r at e iri a subcritaca: rcartor wcre to tr1ple. ca:culste how m .i c h 1. h e n r.r g i r to cr.'tical2ty would change. Show all caiculat2onn uned ta so nc - t mt i- m ,v o.pr .

DXM lt N it, o 1 (1.50)

Yoa are r equ: rt d to i ric r e a s e p c wo- from ) watt to 10 LW 2n 10 minuter en c.

ur.c a t h raep. Calcelete the reactor period rec;uired to accomplish th i s..

Ghow clI var F . 1 OCELTION 11. 0 S ( .7G) 1 Ast tre that c er.p l es cf icur different mnterialt werc placed in tlie r e c,r. t c.r i c: i r r an 2 e t 2 ~.n cmpc. i ment n snd that the r e enp l ca u varr e ml > ed up e f t e .~ tary v.v o r o r:ic a d i r on, the reactor. Ycu r:e 1 c.n ty r.r i n e-t : t.n 2 c h s -4r,pl e t i n: - h.

E :pl as n how, using on1y radaatton T.rvey i n str ument r, avai l 4.bl e at O ' 'A N . ,

y(su Cdn 1 d Ctfit 1 i v t w sartples. 51 et e eny assur pt t or.t y o tt rul:t. l i

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1 DUFi::Y I ON F.(% (1.50) 1 1

H0w niuch r e cc t i v2 t y has t>een adoed to a Eubtr it ical reactor if tne cctoit rate han i n c r e a r,e d iram 7S cps to 150 cpu en ti af the initial valuc of t .ef f w ei s .9M (4144* CATEGORY H CONTINUED DN NEX7 PAUT *ea:>) l 4

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Uz__B5BCIG9_IUE0BY PAGE 7 i

OUESTION H.07 ( .50)

'r ou are per f orming a reactor uttrtup and add enough reacti vi ty t o dc ut>1 c the count rate. If the nett i e amount of reactivi ty were again added to the subcritical reactor, unat condation would the reactor be in? Lamit your anuNar to SULCRIlIC:.L. Ord i I CnL , Oh SUPERCRITICAL. ,

Od.S I J UN ti. OL \ .7b)

The -FO seccod per ied (- 1/. IWh LOR) t cl } OWi no a reactor tr;p i s c aitt ed te y wh : ;:h :)i the i .il 1 ou: on'

c. . Inc decay r ont.t cr t ui thp 1 ongent 11vcc grcup oi dt' layed no t t r or. :.

precursors.

b. The ab211ty of d- .:30 t o f i s si on with cource neutrons.
c. Thr emcer:t of neest i ve react 2vity added on a trip being greater than the Lhut down 116 r ci n.

c' . The a tt cen t t>f nege t i ve r eact 2 v2 i y addrJ cr. a t r i p b s-i ng grEnter thJa beta.

Lld.i iluh H.'9 ( 1. 5.0 /

Ascun+ tnot t he Pu-be neu tr or, tource used in the r c-ac t or wi. r. a 'J. curse I s.nu r c c: w h eri at was manufactured 20 yeerE ego. If that cource were rep'ateu

t. y a ru-w L c.ur i r coiir t e, uhat would tw t h r- change in c o u r i t e., per r.e c on ti.. tiee n ,

on the startup channel" Show all calculations and stato all e s t> u rr p t i or 2 .

hyrume that t ocisy ' e cour:t r ed c befort. r erlacunent in 1000 ccuntt per

! O c on;1.

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DUE.12DN b.2O (1.50) I 1

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Dc u :r i ta tt e nec : e .r e e e. t : o . t f.; t tcLe p 2 e t e t t. p - tm u t * . : i eu ' r t. n i. e th F 1 uten2 um-Ue; v1; : um mu bei tource.

t*4.t4 Uf :i l GC - '. H CC NT ; NUE.o ON NE X T F' AGE **444)

Liz__0E0910B_Ibs08) PAGE 4 QUESTION H.11 (3.00) .

For each et the fol]cWino tterms from the four-factor f ormul a, gave i. woro i definition: (1.0 ea) ,

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a. f at t itss2on fattor (epnilon) ,

t' . toprocutt2on factor (eta) i

c. t h er m.81 u+ 1117.at i on iattor (f )  ;

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I W W1JON ti 12 (2.00) 1ct'cribe hcw an uncompt?nsated ionization chamber detects inc2 dent t hter nal neutronn, including 1r your a n y.w r>r any nuclear r uac t i on t, that tc4 e p l a cc- in the detector.

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r DUhST104 H.1? (1.SO)  ;

Are i ri ini) at erd r emp) e, .) u c t r emcVeo f r ori t he r r4a r t or . reeds 21 mr em/r r on an f

.'i b i- c i 2 ra t ot e-c i m a i nc i r umeril: . A U+rvev ?0 nii n u t e r, i e t.er sh o' ' -

1..' .m m. {

por l u eu . ( 1. < ( eJcte t his belf-12te c. f i he 2 r ri.c 2 a *. tri t.6 .p l e . I r

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1

(*: **t ENI OF CATEGui:V H it446)

h_ 06M00GIIK 001EB1965_U6dd6190.AIEC95EL_ GNU _UGl8BRD FME b DuriSTION 1.01 (1.00)

Act.or cia ng t o RS-E', "Area Radictson Surveys", how often shall rout a nt.

b 2t a-g am.n t area rad atian st'rveyu be periormed in the Reactor but) din, aree?

DL E T 10 4 1. 0; (b.001 Co r,r 1 t'te the t oli coa n) t < t i ) e-- e armer n) ne radi et i on det ecc t 2 on : n : t r u nte '. L used et U.=:' E : ( . ~. c c .'

i n t.t u rn: a F br te r t er 1. pr. Niid 2 at i on E tu r J 2 nu L-t.3v (a) (b)

J oh n r or. GCh-U O_ ) (d)

EL.e r 11 n r F O- 4 (, ( re ) (f )

ARUi ' c (gi (h)

Laer 3 2 ne l'tw 1 t2) (1>

l i

t ut S1 j ulJ ) . .O (Z.%;

4 g e rn mi, srner te esto t r I. h/hr at one foot. How l orio could 5, perron work .it r d :. st e.n c e! 01 4 f re e t fram the sourcc without exceeding the quarterly whole- ,

body 12 m2 t an 10 CF R 29;' **

i Ehow vcur w or5:. I l l l

l

\ l l

DUEST I Dij I.04 (3.00) '

e. 6 S. veer al cl 2 nda vi dt'el h a r. accumulett'd a 12 f et i rne cc:.upat) oni.1 dobr>

ct '. 6 ee. of wh o l t, b tec' y c^ p osur e cior umen t er; 2n acco-dante with 10 :t R

)

o. - e n :1 tir s e u t m v c- 3 no e p 1r ur r- rit e 2 r .- true pe ert nt ta.' enc +r q. ice t t r .  !

l ic.e img :ni v he wert 2 ri a 3 mrt:m/nr arei and not r'v e umi sny 10 C.i G .' O 12n.2t r, 2t he norts ao ? hour day ~'  !!,cw your work. (1. ,1

b. far 10 CFt' 20 an 2r'd2,2nuc] in + rentr2:ted area may br al l emr d to rt:co vc o wnole b r e d / citte in o:ter.t ur the quarter)y i a mt t uncNr cer t at n or.d 2 t ; ont . Dcr,cr2be thc 50 t ar ere Lond t2cnn. (1.b.

(?4414 CClLoOHy } C.DNT I Nth o 0,J Nt: X l FCE 444**i

1. P 6D19e CI1 W _ bOKBl eL9_ Unt!DL2 L9_010E050L _ et4 D_Ue Z 6B eg Pr.ee t O

DJE5 TION I 05 (3.00) 1.aw 1 on:. .vottl d a person have t o spend its etich oi the f ol 1owi ng ii ei rit ta rece?ve h : s / h r- r quartstriy whole body dose? (.73 es)

n. /; 0( > n r ,' h r p a rnnc. .
b. 10 ' r.l cid /iir neuttc.
r. Joe r.hL ,tir bMa
d. F. ' i s I t' c on t a i ra n g til of the ie b ov e U _'E Z.'I I C N I.06 (7.50)
9. 1+ fine
  • h c. . following per 10 CFR 20:
1. FtA Dif.il OIJ ail +' t ( 1. 0)

. - -' :llGH fatbi AtI ON 4 %4. 11.0)

1. fi is) c:rm at it r en.o v ed t r c n. ti t e pocl i nd tne r adi ati on d o r,c r ai t- ist lv 1ect in 10 c, ,nr. A r. mnmit di ::t e nc , trca the f uel e'j en;o n t nr. ! c wm pCFi e 'i- i:d J i ~ 1 07 l .1 e di F ; s!! /

OUE511Dl4 1.07 (1. 0,)

Which rf the f ollowing rani at i on rm p ont tr r* c t.'ou l d inflict thr- g r e h t c-r : .

bi c,) og: cil c a raan s' ta nan: 1 R e.n of ( M M114 , 1 Reni of ALFHA, or 1 Re rn of N l)li-Gl41 s Jt'st1i y your n n r.wer .

l 1

l l

4 4

l 1xt Ei,-r , 3[p;y y g:g,,)[) p[,t[j, g74 pt x-[ [ ggL 4444p)

11__S02196GIl2E_081EGISLS_UGUPLJUO_DISE0586_8ND_UOZ8BDe PAGE 7 4

DUES TI ON 1.08 (1.GO)

For each of the f ol l ov i ng ciocurt. erit s, ntate whether or not the dccuwr.t is required to br? por.tod per 10 CFh I '? . 1 1. Limit your answer to YE!3 cr N r' .

(. . rm )

c. the 1aconse f or the facilatv
b. the operator's licenser L. i. h t' Operai fig [J"'OCCdLPtu
c. i v t F i< !'
u. l i. ; CF f: JO
f. form TEL ^l (f!ot i tc to F_rup l oy erF )

OU ET1CN ..O ( 1. ':20 ) i What pi ( . e s .t s 3 m s e.p r end lea:52n3 a.' rcdioacts'e pool in t er through t h *-

c ar t r ei t e of the pcol wz1.) '

b (t**ti LND OF CHTEGO:n 1 4444ti

J.  :. PIT I F ? C DPii R AT I LJL3_ CHt 3F5/3E Kf31 E T ).GL PAGE d QUESTION J.ul (1.50)

What t wo int er i or 6 : must be met tudore n ae)nct pourr can be applat C ici.l:.J 1 1 jig J.v2 (1.00)

Ld e,- )i 3 L r;ne i cr.tt'r e ; r av 2 o c; 4 or the Low St;urce Level Ecror

  • OCui i I: .

J.01 ( , S .> >

T r a. r- Ialcc:

L24e cf tbe i u e) e2 ert.en t ; at 0 5La d>: i t. clot er mi n ed by corrocirn c on s i cim a'. t on s end not tr/ t u e :. La u r n up .

L J : '- i I L N J.09 4 1. '. v: )

L e t.c r 2 o c t'w ra , . i eu p ci t t.e LOU! R - uri ' it er i> 1, i nc) or12 no ms or101 s ou .

t he p. c c t.ro c o ' i ? o 1 or, cf e: c- c. . n t - 41. c.r.c " u i rhm : r r .

e _: ! I _ia J . ' - t, s;.O>>

L e '.t r ) i .' the a i 4 i r r F r.c e t +> t w e r n e ' t. ! c w < c r e n. " anc$ o "4 att screr".

OJi G1 IL N J.06 ( ? . e 'O >

nt l ei: power, e.ch u t t. ) n g t t ca compensetin; vol t e:ge cri a cenrenrated 2 cri c h e rc.im t- (CIC) will ha m a vi:ry not a ceabl e o f f ect on the cwtput of ttw detrcLar. Houeve r , ar toeer ) r-vc ? eppr e acht:r 10 MW, tiic c f -l c r t ;r ih JJC autr A cr ent:ngiru, ccxr.cht M ir.; ', - 1 L a - . - 1 !; a)mcrt nrglitiblu. Eq>tn tl n p t a. n un. w icm .

L4((44 L H I .' U O l ': J E ON ! : TU.i. N NEA1 i N,E 4544t)

J. ?E UG151G_0EliU911 N9_ GUSB0 EIESIBIJ.GF FAGE. 9 OUrIST l ON J.07 (4.00)

Rei er ta tne attached figure.

[13tch the l e t t ter ti on the f29ure to t ht? f oll owing components in t ie nh :. m--s z t on y contrel rod atin ernb l y : .

1. Magnet 6. Up suitch
2. 11ag n a ar matur e ~/ . Down swttch

,J. . Conn 6-cting rea B. Bottom switch

4. F-oinen w : t i t,n 8. Drive motc'r
~ . F us-1 r i en er.t 10. f-ot2tton indicitcr t r an c e.n t +. t r (find or CourFD) 2 LIE DT !!>h J . ': S (2.50)

Ftr I c e l.r.1 c 7 1 3prrsi2 cat 2ans, compiete the f ol1 ow2 ng cor.c.er ni ng s.poci f i c a t : or.n a:id ch nr a c t er i nt : cv, of the OSURR: (.5 ea.'

). 11c o : 2 riur r a11owab]e power 1e n ) i? _,,,,,,,,.

.'. M s. : 3n;t ]ogii e , c e s t. rvict: .Ity 1L . , , , _ , , _ .

~. In t: : r: ;r r m : re s t :- t i un i i mi . r %) I ntit e :c ec-ci _ , , _ _ . _ .

4 M .) :i: r. n.c3cr ci f veel o;ementt that may be 3cacec intc i f.e cn" ar .

L. 7Fe c oi i- t r e l n ytt om rhtJl h we a chu t tj oNn mi< r g 3 n of t Iw:t . .-

C"JiL11OrI J.09 ( ~.'. . vo s Pcr Te_hnice1 Spec 24acat) ont nec t 2 ori 5,4, there cht11 be S chtnnc1! of n u c 1 c. 2 - I n str umant + ti on v .per at i ng et ell 1 2 rt.e s . List the m cher ries ta tnJ t r.D Dil r.10 U1 o n e?r M i n g r pt ri M [ nt l et. hnica] Qipc 2 4 _ c tit } pi e s .

I i

I 4

(442 4t Ela; O r. L p l [,r a t s y ) ,4444)

I i

. l l

1

[t _.OEL. dOUdl=ldl OUD CO35. '8!!6dElflBU PAGE 10 I

.01 (1.60)

. e pool l < al cir?vrel o p s wri t c h ne cesul tatea cira2 ning the pool for r upri r ,

expl ai n h o e, proiection frem fusi element radiation in provided.

C'Uc. J,1 J U N 11, w ( ? . W .'

D e t.c r 2 t , e hev a cont r ol -r od tue1 e l erwn t differs f r orn a vtsnnerd fuel c l c> n e n ' .

Ed C.T 3 i si a n.US (;.UOs lie s.c r 2 .m t h r tc e di f i e rcent er between e chim-cefety tod and the regul atina rod. (1.0 ce)

Dut.t f luiI l. 04 (2.00) i .r p c. : +me (ei 7. "rice' E J in a r.t J r.n p t c t ; c r,' " , t. l i o t pre:c.3: 2rn m ir *

.,t.-q t r. r ?t i.r d ; '. c tt e c<rc p a ct t c? ' c re: vr i or a corn roz e . n cu: q t la .H .

l ' i ;. [

2nn 2 'r 10 tt' p c r f t" 1. H ; tl.s' Lin t risi t 3C ' tit' CUEF T I t.r J K . 0"- ( .50)

Truc- or F a l 5.e :

Tne ' nouti ng' of the Lic n t e i.d Irradaet2on Fiscal 2ty (CIF) can on)y t,c locrteo in raid r 1 : p o t. 2 t 2 on ( 2. , J. ) .

Di;E C,: 2 C M  !.0<. < 1 . O'. ' )

D5sc rsue t .e i n t er I nc. 6- feature uscoci.ted with the t h a n -- c af te t y r c'n L V 2 t F fD t !) A

  • P r Oc Di t E' ; C: Ped i n y 4TiG M 2 m'im r C a c t ) V l t y O'lO ; t l ora r dt f
  • h.

1

( 4 4, s t Cril L GO,tY I: C.0tJT I NJt D DiJ NEX1 Pe6L t4444) i l

I

L.__EUh._tiOUD6190 9LG.30fiE_E8 bet 4I!ib5 PME 11 I

DJEM10N P. . M G.00)

T here ar e several light o prov2 ded on the control panel for each shi m-cM et y roo. For each of the f oll owireg lightei, deveribe what the light indice_ut; when illunanated, and what color the light i t. :

a. Jia
b. Lp
c. . Down
d. 12-t t on us .  :.n g a p DUESTIC4 L.OD (1.:A')

F e t- i ts c hn : c o J EpectfIcettenn, cic t a rm an ' e :per 1 meat" .

D',!LS T : d . v'i (. .'c' Anwar eci.1 thc i c '11 ( m n p ( p " ri i i u n s, li UC x A . :: t- r t c; r. r d. ) ,( l i t n ; t :-

Epc: 1i . cat i or n: ( . 5, ecj

s. The tw u t r o r. ,ou ce nr.a1I bc pos) t 1 oned vert a ct.11 y bet ueen tbr gr o plato and the top of the fuel elementn during startup.
b. A ria na rnum of four channels of nuc} r ar instrumentation thnll he esu scale. provi d2 ng m.Pa:n ne f o'. 1hfotmation through al1 power t*angt n.
c. During a critical e -t p e r i men t , subtritical nultiplication p l ot t. 5%) ) 1.

cbtasned frce et 1 east four 2 nut rument ati on channels. '

i

d. Tna r, a : .mem r ee t:ti vi t y vorth of Es n y n:ngle independent e a p er i i.t-n t stiv 11 rDt e:.ctm a O. V . in r e a c i.1 v 2 t y .
e. lho escior sh:11 ne op er e t e :J on1y when all latticr. posi t 2 or.o it ierni1 t o th9 c :t i , e s uel b_unnary arc occupied by either .A s '. a n c a r d or  !

contrc) !uoi e 1 emer.t .

r (46(46 LRTE tiORY t: CU91 I Nile D LuJ NC)T FHuE $At44)

I

E z _ _E UE L_tiSb'Di-l ND_099_G OBE _ EGBOUEI EBS PAGE 12 ULiS110N N.10 (2.00s Lc.ncerninn tuej handlino, per Technical Opecifications:

a. liow many individuatu are rectu r ed to be present wheen handling i u e l

( . b)

How cianv 1 1 c i- nu d a nn2 viti ual c aro reqtta red t c b e? oresent? (.S) 1.

c. Wnst i v p e tit lici.n ws sre regt.iired an a r41 rei n ties? (1.01 l

l l

l l

e g b , ,

L,___BLUlblEIBOI M EBOGEDUELEs._GONDlIlGNS_edD_L).011811000 PA iE 13 OLEST10N L.01 (2.50)

Per T ec h n c r.1 Spet_ifications TobJe 1. for t he f ollowing conditions or c ) g n.i l s , provide the applacrblo scram setpoint. Astume that none of the

< c r a n t. are bypanted. ( . b e a ')

a. Neutron count rate t.. Necctc3r p or i t'd slcm t c. r a m
c. Restior porton fa*at scram
d. Reactor poer .510 w c c r et m
c. Reactor p ouar - fast scram OUE:ul 1 CJ J L . u;. C.75/

ew r u T.c that you or e the Son 2 or Operator t,n Duty and that the Laboratcry D. rector anu A7. se c i : t e Di r ec t or are n cet availabic when a nucl ear emergency occure, f'e Enargency ProrcJure LP-01, wnst 5 actions or e you rergantable for per t or an n)?

OULL T I _ir. L.t'? -

( 2. L .' )

i er

  • o r t e. 2 c i, j 'e 12 c.at ; or . > s~ tIcr

., 4. at nr e t t,e 1 2 n.i t on p: 1,. 1 c' -

r t.:

-J e . t 11, w e t ..r 1 F- o p r ': ' t i . r >> , [=M, a n:- cc .duc t: s 1

  • y O L E E T I L'l4 L.Q4 ( 1. 50,)

Wno n.ust approve nu procedurec before they may be entered i n t o t *.t. NhL Procedure <t t1c n u a l

DUE ST I Old L.vi (1.50)

-er Ot1- 1, "Rosciar ' c.wer (n.m.y:L. hew nir4ny pc bc.s t.ith wnet c i n c, c, licenuem curt t e pr ew'it t r- thc conu al . oom cny timo t. h e ninnet c o . t r e. .

power iey 2c e n 1 c c L P'J ?

t4**ne C 4 T E.uD F :1 L C O NT It'.ut.l* 0,J tu. A T FME A84ei>

I

L 2._ _6201015160112 C_ C60 G E U U B E M 2 _ G E U DIII DU S _ GU D_ L i b110I196.3 PAGE 14 LUECTIGN L.06 (1.50)

Antwer the 'cllowing questionn por DM-7, "Fuel Element InspcNtiono":

a. How often should At.L fuel and ,:ontrol rod elements be va nu.a13 v i nsp ec t(.

for evi cience o f patting and corroston? ,

b. In between comp)ete inspectionn, how many funl elementn must 1, e l 1r.rpected si t ; e ct e t annual 1y?

C .'. i, ! i i)N 1..t% (2.*"5) .

1hc 1 ec h r.1 c a l Eperii2ci;tiorm J%c. ribe on " t >: c ] tS 2 or i erea" for OUU: A. '

e. . Dref2ne "ea:)uuton eres". t1.5)
t. What in tho boundar y f o '- the en cl union area for 05Uh7<? *.75- t r

r F

DUC al 1 O'1 L.06 ('..O')

i e- 'e:.inira: u;tc!f2: si t 2 o r v. . 1: Lt ' oi , orest 4. n at nurt be h;,n tor ou L' f at et re :1c .: n , tion ; i c.' s .

DJECfl0N L . '.' 9 ( . . t.0 ) '

A g. s,u m e that v c.u ar e the licenced tson i er reactor cperate- en duty at O. .lHh . ,

A n usting profunnar from the University of Wittonnin asLL if he may  ;

per i or as a rtertup. He currtnt1y holdt a senior o;ier e t or 11 conte on t im lik Tr go reacta . A1) personnel requirementu of the lechnicel Specii1cataenn ere nw t . Do you 1et h2n ptriorni ihe Ltortup u n cle r your superv1c2c:? Why -

oi whv not i I

1 l

l (4444i EN! Of C AT L^ GD < y L i444*)

(**44441444*t* END OF C AnMINn11(:N a64e444444:,,at) l

U,.._ OEGEICE ltjE98Y. F' ACE l t, AN5lER3 -- 01110 LTATE UNIVERGITY -06/05/03-DAMON, D.

A N.3WI H H.01 (1.00)

K ef?cctive tuket. into account the non-leakage factors thet K inf i n) t y

gnores. ( l '
infi ni ty onsum ?s no 1eal: age ) .

F5FEfiENCE Li1 a c t.t on c J. n d Gr-s ons kc , tet 4.4 AN aid. fs 1 : O.; ( .~ 00)

a. p r c a.pt . neut r on s. are t crit d)rectly i r ntr the fission procens ,
b. Colcycd neutrons cre born from unstable fission daughtern
t. fact n eu t r ce n t, have energy levels cn the or der of 1 Mcv (or greater)
o. thermal neutrons have onergy levels a n equi) ibr t om uith their env2ronment (usual 1y less than 1 ev) liFEhENZL L l eabt one a :d ! est nri e, ter. 3 T'. .1. 4 t(> .1M AlJStK R ii.</2 (1.50)

M= l e ( 1 -l;) wher e l'i - c ot;n t rat e mul t i;.l i er and K u fract2on toward critical M= . cc i: - 2/3 (.7S)

Mar gin to crit)ctility is cut by 2/3 or reactivity in the core ir 1/3 ci the oraginel , . 75)

Cred:t gisc, -f or al ternate onswer e that are supported by applicable fo'nujau.

NiiF Ei<E f.h E OSUnR student notos, pegt 5c

Us. GEBEll:!E-.lbE9CE PAGE: 16

. ANSWERU -- OMID STATE UNIVERCITY -08/05/03-DAMONp D.

t ANSWER H.04 (i.50)

Pr Po u.p (t/1) or 4 = t/(In P / F'o ) (.76)

P 10E_. w?tts Pon untt t %OO se c onrj u (.25)

T= 600 bec/tln 10L3' = 600 / (/.' n 61s set:ond s (+/- 1 s e c

. ( . D)

REFERENCE 05 Uni Stuacot nctes3 p a g e- 13 l

AN3WTR H . O'; t ./S) 1+L+ 2 n i '. l e l rcad)ngs of each sample and record. Wis i t sorae per i od of t i mi9 tem an o t h:: r set of r e e.d i n g s . +nd record along with the t i rne di f f erence bcrween r e a d i r+ g s . Ih1s woul d al1ow you ta calculate is hol f 1ii e, an't t hu t.

Identify u"11th s am:21 e wan which. (Alternete wordings acceptable.

Al terr ate exp3 brmtions ac e r-p t s ts l e as l or g as they are supported by v)abic c4 hh iJipp t 1 Cils . )

Will accept t : s+ oi the jan..u s pect rosc opy systen, for credit.

F.& ENEM.E t 31 a . n t o:it i. n t ' w .cr p e. we_. ..' _o 2.

A N '.W E.R H.Oh ( 1. '50 )

c. r 1 /cr 2 t3-Ket12)/(1-Keff1) -> 75/150 = ( 1 -kef f 2) - / ( 1 --C . 95 7 thereicre Kelf2u.975 (./5) r h o =- ( K e f f - ) > / I w f -f r=> r ho1 =- . 0526 anc' rho 2= .0256 and delta rhou4.Q27 UH delte rha e in ( n c l i 2 /lW f 1 ) = :n . 9/S/.95) a + 026 (,'br hEi LNLNG G1 a n s t aru e'irl Setonute. Soc. S.14 ANSWER H.o7 s .50) supc r c ri ti c el W) 11 accopt cr 2 t. c al if as sumpt i on i s. .

-- t a t e d that k is c)ose to 2.

i dt__6E6CIOB_]UEQBY PAGE 17 t ATI5WERS -- OHIO STATE IJI11VEfS)TY -08/05/03-DAHONa D. I

. r a

i,

)

REFEhENCE ,

C1esstone anci Sesonske, sec 5.14  !

I nl EWE.h 14. 0/) ( .7D) .

3 l I

Falf EbEld.

I Glatrccine and bencnnie, se . 2.1 ?6 t c. 2.17 2, 5.28 :o S.32, D.40 to 3 . ,' -

i I

i AN9l1ER H.09 (1.501 l 4

P1utanium heo a half 1ife of '?. 411 : 10E4 yearn. Using i.h e f or:m.t 1 a N = ha exp ( . 6 9 ^'.t ,' h a l f l f e ) , rafter 30 years the production of s]phan t+ /

the p l u t c n a uri t 'ou l d t,e

- ( 3Oy t x .693'2.411

  • 10E4 y'r) I

>' = .9991 ,

i t)n< c iti 3 f i; i ) L} / t. '_ U r , cr tI.e neN T r*ur c( L JC'J) d De proturInp -

'/. /1 d . . ". . i ,' . 3 m e. .

r,t r e thra the old not rce . Ther ef ore .:l i t c h m ; c., 21:  ;

c e: .t rite io t. a c u t ? 1%. Ih2c 2s ecout 1 count p ar nt:c ar.o . (Ut1i c e;

  • i a . t. r i o.w r t t t ai t tne rhman it not not i c eab) c- &s )ong as t i' e or oper c al c t rl i; t a on e, are pe r r ormer. . >

Wil1 iccer t e::pla21ation of cource t er n. increasing io- f$rst 30 year E WIth a pltnoniu.m nource.. .

l iiFF E Rfii Ct: I i

tsl at t,t anc and E.esonske , Dec. 2.4 I

ANL.&h :4.1 O (1.50) 2::  :. '.E 4 l Fu U + He (0.75) e,,.*, c.2 .

l 9 4 :P i ne + He --. C 4 n (0.75) 4 2 4., O 1

i

. L .0Ee&10B ItM90Y t AGE ic ANSt<EfG -- OH10 ST ATE LIN] VERSITY -09/OS/03-DAMON, D.

l l

t hEFCl(ENCE 31atutone is n d b e s o n s i; e , Sec. 2.71 to 2.72 ANSIGR H.I1 (3.00?

u. n o mn c-r of fett neutrons niowing down part fits)on t.hresho]d for U- 2M number cf neutrons produced by thermal neutron f i ssi onn
b. -4Wrapa number of neutronn pr oJutesf cfirectl y f rom t i su) on numter rd r.eutrons absorben in f sf el
c. number o-f the mal neutrons absortied in fuel tat al numoer of thern61 neutrons at serbed t 1. O ci:)

FEFERUiCU f.. > v u r

  • c n c end L e - o n s i:r.. Sec. 4.1 t o e .14 Ali3Wl:R I i .12 (2.00r NHutraric interact en t h the boron in the detector accortf 2 ng to the io]1cw ng iormula: ,

10 1 11 A 7 4 3 t n -O ( B) -> l. i + He + electrons L 0 0 3 2 (1.0) i 1

The ions er e at:cel w ated in the electri c fi eld of the detector, c a u t. i r.g l add i t i orea l i on) : ct i on s: in the cas. When the xor:s resch the electrodcs, A l pujce is genera *.ed. (1.0) j hEr:Li(ENL E Else, stone ent! Eesonst;e, S c. 2.P4 l

RGec,Ig8_1tjEOGX ppc6 19 ti .

. Al SiWERS --- UHIO OT ATE UNIVERSI1Y -03/05/03-DAMON, D.

ANSWEli H.13 (1.50)

A u Ao en:p (- . 693 t /hel f l i f e) ( . 5) hal 11if u "

(.693 t's / (1 o A/Ao) (.2b) ne.lilite s- (.0 R. 4 00) / (in 21/3.2) = 7.26 tr i rx t 9 s (.7b) b EF EREICE Rb-06, Hl p ?:r.d i t ee, A tin c' L a.

i i

l l

l l

1

.b._ _US D106LI1E _t10IL610kS _U SN DL INO_D12 LOE,O L _QN Q_UO l6B D E PAliE 20

. Ath5WERS - - OHIO STATE. UNIVERSIT -88/Ob/03-DAMON. D.

s ANSWER I.01 (1.00)

W e el:l y (.33) c. r on the day of reacter opcrations (.33), whichever is nect t freiquent (.34> ,

REFGhENCE hE-9 sec V.h.1 n!!M i T . 1. O'1 , ( 7. . 0 7.o (a) G - il (br t.'t t a gamcu -

(c r C-M (d) b c t a g a r,rtir.

(+) a2r ion: cation (f) gemma (o) St a nti ] ] ati on (h) g lim m a (2 ) 15 3 p op,m t : on a l (j ) neutrons Ri FERE IEE R 5 --O o tip p en tii n C hiivh 1; z.O' ( ' b e,-

': 2 D1 , i f(1 ) ' D2 ( h!. ) LO.6]

Li R/hr ,

I sqft  :: D2 :: 16 sqit (0.4]

D2 = .5 R/hr {O.1]

stay time : total allowed done / oase rate LO.6]

" 1.25 R / .5 N/hr LO.41 LO.3 for l i ru t ]

2. Li hr LO.1]

REFERENCE 10 CFR 20.101

13 89EIO % 11YE_PJ01EB16LE 06dEklb@ El@I?OpGL_6UQ_UG16 Bps .

l'nUE 21 4

ANSWERS -- Oil 10 GlATE UNIVERSITY -OO / 05 / 03 - DAr10N , D.

6NStvCR I.04 (3.00)

a. mey receive 1.25 REM this quarter sante he has no quarterl y empentr e

. ( . S) fla x . lic t3 e s- Done Rare X Time 1.2aIMm u O.003 Ren/hr >- O hr/ day X No. of Days No. of L'a y!! r: S2.1 days ( 1. 5.0

o. Pr ov2 dred that (!> Ho doec not c,': c oc d 3 rem per qunr t er (( L)

(2) l 11., radiation history 2s I.n o n n a r. d record d on the proper form (NRE Form 4) '..b)

(3) Tne done received when added to has radiation I.intory does not exceed b(N-18) rems, where N =2 f.he parnon's aoe at his 1 at,t barthday .bs R&fERENCE 10 L F R ; O . 1 (

Ai40: AR ] . O' 4 (: . i n. )

c. 1' 210 a.NE rR 4 GO r.F Eh

" *. 125 hr ( iF.- 1 )

b. 12"s0 m:lCh/ ( ) OOmr6-iD ', OF of 10) = 1.25 hr
c. 3250 MREM /3OO r. REM =- 4.1'. hr
d. 12S0 MREM / (400 mRid1 + 1000 inREM + 300 MREM) = .74 hr '

I REFEREEL i l

IV EFR l:0,101 l

l l

l

13.__ fiOQ19tK 11ME. E'Oll.12.Obh HANI'L I NO D1EPE E6'n_6@_t305bfiPU P AC E- 22

. ANS A'ERS - - Ol110 51 ATE UN:VERSIT -88/Ob/03-DAMON, D.

AI EWic.R I.06 (3.50)

A.1 Rar:>ation Area: Any accessible area in which a major port)on of the body cot'.ld receive in one hour a done in e:< c e s u of 5 mi.l l i reti u . or 2n any 5 c.onsecutive days a d o :-s e in excess. of 100 millirems (1.0).

4.2 lit gh R.2 d i at 2 or. Area: Any s.:c s-s c i b l e aree in which a major por'2cn of the bccv could receive in one hour a doce in excess of 100 c.2112 r en s (1.0).

11 h1 bitt? = hi LC. 4 4 : ( 0. 3 ;)

Radaat2 ort Arcc- S mr en:/t.r !IR 100 Tc err / wee k (2. L inr em 'br )

i4 4 4 T u 10 (200)/5 = 200 OR == 10 (100)/2.5 D. '  :-- 14.14 It u 20 it ( 1. O )

fulEHENCE 10'CFR 20.202

. .i ? v ..!< 1.ii/ s J ,, v o )

e4) : 4 Ec.c. ( . J ;) i em 23 a _' t 3 - (f b) ctc ott c.1 dema ge r e:mr d j e: c!

  • n c-sat rr.e o f rad 2itsor. (.75; RU EkEtaCF 10 CFh 20 AN5WER 1.08 (1.50)
b. no. all othern yes (.23 ea)

RF.F E N[. NCE 1<' CFR 19.11 ,

i l

1 4.idWE R 1. 0r/ ( 1. E 0) I l

Tre pool as co.nrietui y 12 nt'ci 'o t o an epony-bar.ea paint, rez ni or crci sni..

i1barg) ass.

Td:F E F ENCE OSUHh H a :- A r d bucimery f:c por t , e oc: 1.6.1

J . __ EE G Gl l'I G_ DE'EB011 L49_ G U0E OGIE BID.TI GS PADE 22 ANSWERS -- OH10 STATE UNIVERSIl~ -8B/05/03-DAMON, D.

ANSWLR J.01 '1.50)

1. Coritrol and Iristr umen t power mutt t,e supplied.
2. Ne y switch must be inset-ted and turned on. .(.75 tm)

REiEHliNCE 05Uhk licz ard E,umn.ar y fuep er t , sec 1.7.6 Al :ilC. h ..i . 0 2 (1.00)

This 5, c r u m u c t be bypassed during fuel changing opereticos, s i . .s e the sham-cafetv r ed r. n. 2y be, parti al l y wi thdr awn when changing fuel ponitions.

1 REi ERENi.

DEURR Ha.:ard Suw.ise y heport, urc 1.7.7 (4 N SNE T. J.03 ( .00) l 1 r t. _>

RElER/NCE 0:3Ur R rir : 4rd t u tmar y Rcaport , src 1.3.1 l l

l

  1. 4NSWER J.04 (1.5u) l 14.1 uei ght- % (.5) U-f41 r,11 oy (.5), 93% LI- 235 ent 2 chment ( . b) l l

R.EFEREI JCL DSunR Hrard Summtery Peport. sec 1.}

l ANSWLR J . Oti ( L' . 00 )

7,1 os r,c r c m poucr is r en cived 4 rom the bl ow ncrem col 1, opening a t o.a t # t. t in the n agnet cir cui t, al l owi ng the control r od to drop (1.0) f a r't sc~nm - b2ating is removed from r. tr ans1 ct or in the magnet c.) r c u: t .

acting es an electronic switch, al l owi ng the control rod tc drop

( 1 . O '-

_J_._.,_ _ F-%G E 24

. S.

_ .F.. E.

_ _G _ _ _I

. -F- .I. C_ C' P E _R _A_T _I_ .N..G_

_ __ _ C_. H.. A Fs.A. C.T. E rH_.9._1_1 C.S.

nNbWEFE -- Cri10 ETATE UNIVEh517Y D.

-88/OS/03-DAMON, f:Ef EFRENCL D E.UXR ts tuaen t noten ANSWId J.06 (4.00)

At 1oa power, gamma co rent i ts relativoly I er ge compared t o thc' neutr col c u r r e . '. in t.h.= octector, TTus, chnnging componn.iting voltsee wi11 hnoo l arc t- c+fect ori the t ot al currFnt output of the detector nince t n i s e d i c- e t s, coly t.ha car,ma portlen of the dete:ctcr current. (2.0) at h i ( t. p :, w . r , g a, m.a cur r er:: .t r e.' e t t vtd y umal I c on,p ar ed to the r.c utc c 1 cu-rent. C h ze.n g i n g t 'm c:mpennsting voltage agair. chsnges only the g a r, m e port 2cn of the d..:t.-;ctccr current, but tinte the percentagc i s n o t .ir a l l , the e-f f ec t in almost nat nottceable. (2.0)

REF EREl: t 05U memo f cr: E.. l.. Hajcl cat eci 7/29/77 A'C. L E H J . 'T/ (4.003 L. -

6. U Z W 7. D s- > U. T
4. U (? . N i D. H 10. F. o c ri RE f
  • El aiNCE. .

O M-- 1 1 at t ac hmerit C '

1 l

ANEWER J.03 (0.50) '

i

1. 10 k W I

.: . 1 . 5 ', ct 'k S. 6. O m e ec 1

4, >c ,

5. 6 ". (.S en)

REPENENCE OLUhR Ha.' erd Lunrra r y Hrport, rec 1.1 T ect,n1 cal Epuctficat1onc 4.1.3, 4.2.3, 4. 2. 4

as R EClELC R EBQllNOlO@@@GIEhl@llQ I"AGE Lb ANSWERS -- UHIU STATL UNIVERDITY -80/OS/02-DAMONg D.

ANSWE!i' J.09 (3.00) st. art up chantiel 2 cpc to ISO :- 10E -4'.'. f u l l power Log N-period charinel 150 x 10E-6:'. to 150% full power Lineer level u n a n n t .' (i l 150 ' 10E- 6% to 100*/. 4 ul l p ov'er Lovel sal et.y chanr el 41 150 .: 1 0 E - 3*/. to 150% iul1 power Level sr.i ety channel 42 lbo x 10E- 3% t o 150% full rower

(.3 f or each ch annel , . :.', f o r e / c h r a n ;) e = ~ . 0 total) fief E hlt !CF T ec h n i t. s ! aper) . ic at ; cnc Lec t i or. S.6 I

i l

l l

l 4

I I

K. F u g 6_ {j @ N D L ,1 NO_ G N D _[O R g _ P6091;1g I E R S PAGE 26 ANSWERS - OH10 ST ATE UNIVERSI T Y -08/05/03-DAMON, D.

ANSWER K.01 (1.60)

The f ut: 1 would t e moved into the storage pit and a lead cover it put cver the pit, reducing the radi ation levels. -

REFERENCE 05URR Harard Surr m ar y Report, s er. 1.6.2 A;E WER R.02 (2.00) lhe central 4 fuel platts are removed (1.0) and the plates edjacent t o I nt.

channel are pure aluminum. (1.0)

REFERENCE O S U R E }li : a r d Summery Report, ucc 1.3.2 ANSheN k.O! (3.00) f- n '. 3 of t ar. 4 c .) : owi rio : ( 1. O c'a )

1, po2 son rect 2cn of r eaul at ) . g roct attsched d2roct1y to cJrive ccru

2. n u rna y a m. or m.sgne t an :pg e light on regulating roo 3, 10-turn potentiometar 2n the drive train of the regulat2ng r sd
4. poison sentior, of reguiating rod is an al urns nutt c)ad r,t a i n l es t steel can instead of barated s t a.i n l cu s stee)
5. fteg rod lu smooth, shi m-sM ety i s grooved.
6. Img rod i n hull ow, shan-eafety is sol 3t.

REFERENCE 05LiRR Hanerd Summory Report, sec. 1.6.2 AN3WER K.04 (2.00)

AJl stcnda-cl 4 uci el emt nt 5 shat 1 be unloaded (1.O) an ci ctored 2n the f u t- 1 elonent r, t o r a g <e p2t (1.O)

RUFERENCE OM-7 so'c t or, IV.E

U,. _EVEL.U60061.00_0012_G00L.P.0000EIEBS PAGE 27

  • AtJSi)LT<S -- OHIO ET ATE UNIVEHSI T Y -88/Ob/03-DAMON, D.

AN%ER K.OS ( .50)

Falve RE FER E.NCE DOURh Har4ird bumniary ficpc rt , sec. 1.5.6 ANGl'ER K.V6 (1.00) p .t s,t.o t t t er.r tr e- r. et han 2 c i J i v i nt e:-l oci:r d to prevent w2 ttedr awa rig mor e than one snim-Aaftaty at a t. i tw (1.0)

F .!F E Rf;f E.E CG uro < } .4. s. r d bunroary Neport, sec. 1.O kN:.HL:\ : v. . u7 Q.Qu)

.b .o- e t. c t. pt* pote .1 +cr eisc h co]or)

7. inJicate: con:rol rod fr9.1on:t cn. colar - rod L' . )sidic 4ct ( t,: . t r e l red 1 ot-d Sc'ea v upp"r J2ra* of travel, c.el or - or arg ?
c. 2 n t. i c a. t t 's. c ont r ol r c .cl levd sc'eo M. Iower limst oi trave 1.

color - green ti . ind)caten contrrsl rcd at bottom of core. color green

o. indicates contr 01 rod engaged io the magnet. c ol, or - whi tte f!EFE f ErJCE USURh Hn:.ard E u tr.r.a r y Repor t , sec. 1.6,1 AliBUEl? I. 03 (3.30)

Any apparetue, devace, 0: rst<.2a; ) note 1 led in or r. r a r the ccr.5 ter 2 ( r, could conctuvaL31y have a reactivity offect on the corte (.7b' and wh2cb iLLt16 2 c .ot a corc> c omacnent er er p r+ r i men t al iac211ty. t.75)

REFENENCE li.m b r:i c a i b;.ec 2 i i r a 12 on 6. 2.1 9

L.__L2Ei; UOWL. lng,,000,,,GQGE,,E8B600JEGQ PAGE 28 l

, \

' ANSWERS - OHIO G1 ATE LINIVERSIT Y --DS/0D/03-DAMON, D.

ANbWER h.09 (2.50)

a. f rue
b. I-alse ,

c, l'al se

d. False
e. F'a i n s REUEREN;E 1 ec hr 1 c.al Spec)fIcetaen- 4.4.2, 5, 4, 10.1, t, . 2. 3, 7.4 ANSWER K.10 (2.00)
a. 3
b. 2

. l(0, S F,0 REFERENCE T m:hre i c a l Spcc:tIcotinn E'. 4 I

1 l

l I

l l

l l

i

Lt__GDU191SIBGI12E_E60EEDUBESt_GOUD1Il0NS_GUQ_bld11GIl0ND PAGE 29

. ANS.4ERS --- UHIO ST ATE UNIVERSITY -GO/OS/03-DAMONe Do ANEWER L.01 (2.50)

<t. 2 Cfs s (.6 ea)

b. 45 sec .
c. 41 sec
d. 60% ful1 power (120% scale)
e. 150% full powrir (15 kW)

Fd rE RE NG.

T echn2 cel Sp ec: f i c.at i on s, Teble 1 AN5WER L.02 (3.75)

a. Account for all NkL and e:: p er i men t.a l personnel by physi c all y eximi ni ng every office and laboratory area in the Reactor building.
b. I nf orm r,ppr c'pri a t e super v1 sor y personnel
c. bu vsv all pore or.ne) who have evaru+ted thE' NRL
d. Pr c.cc c d with cli :.cr et_ i on , f r.d w i t. h a surve+y i ns tr t'r ent , t ow ar ci thr to t ,
2. 7aka chc' ce of e ' +. a b ; 1 :,h 6w n t a+ c::cl usi on arreas, p er son n tc l r ec ovi-;r y ,

etc.

REFE REl;Eii EP-01, step D.2 AUGUER L.03 (2.SO) depth - 15 feet above the t op of the active core max torporature - 145 degrees F min t einper e t ur r - 40 degrees F pH - less than n- ecpial to 0.0 c ;>n cluc t i vi t y - 1est t h i4 n or requ a l to 2 umho/en t5 e t .)

REFERENCE T ec h ni c s:1 Spec i f i c a t i ons, se c t i on T

.s. -

f' AGE 30

' %>80L11Ni@lSQllME_ESOGEQUGE,$t_GQUOlllQNS_B@O_,LitjlI@llGUh ANSWERS -- C HIO LTATE UNIVERSIT -88/05/03-DAMON, D.

ANSWER  : 04 (1.bO)

The Anstclate l>1 r e c t e r (.75) or Senior Reactor Opern:or (.75)

REF ERilt':E 0, f > - O t , t. n p D.2 A' JM ER L.OS ( 1. S'J i 1 r cac t or oporat c r OF.

1 s,oni or reattor operator Ei ther answer for 1.5 FEFERENCE OM-1, see IV. A ANSWEit L.06 (1.50)

n. esc y the s e yt:ar i./b)
b. f i v' 01c+cnts (.7A RE- F Ei EliCE OM-7, nec 11 AlJS4ER L.07 ( 2. ::S )
a. that crea surrounding the reactor, in which the reitctor licenree h a r.

the authori t y t o daterrna no all acti vi ti es including e:< cl us i on or removal ci percontm] c.n d prcpe-ty ireni the area. ( 1. 5-)

b. the fence LurtoundIng the Research Cent er . ( . 7 tU REFERENCE 10 CFR 100. 5.a Tec hni cal Specsficatiori 1.2

L. ADMINTEIG811yE,['tigCCpWEEg,._C.'gNDlIlgNL6dQ Lit 1116Ilgd5 PAGE 31 ANCkERG -- OHIO GTATE UNIVERSITY -88/ 03/03--DAMON , D.

ANSWER L.00 (2.00) t n e r tr.a 1 column, beam ports, pool surface above core, demineralizere

. ( . S t=:u REFERENCE Technical Specifica1.2cn 6.7 4NiMER L.07 (2.50)

Would not a l l ow h i rt. to perform the startup. (.75) 10 CFR SS allows non-licensed persons to manipulate the control s of a reactor under supervi52on en1y )f ii 2s part of t he non-1 i cer se .

Individuc]s tr aining pr ogram. The professor in not in training. (1.751 REFERENCE 10 CFr< '5=. 13

TEST CHOSS REFERENCE PAGE 1 L'UE31 I ON VALUE REFERENCE H.01 1.00 DMNOOOO349 H . 0;f 3.00 DMNUOOO350 H.03 1.50 DMNOOOO351 H.04 1.50 DMNOOOO352 H.03 .7S D MI10 0 0 0 3 5 ".

Ii. 06 1.50 D11NOOOO3b4 H.07 .50 DMI100003S5 .

H.UH .73 DMNOOOO356

11. 0 9 3.50 DMlJOOOO357 H.10 1.50 DMNOOOO35f3 H.11 3.00 DMNOOOO359 H.12 2.00 1,Mf JUOOO~ 6v H .17 1.30 DMHOOOG61
.O . 00 1.01 1.00 D M N O'.iO O 3 6
'

1.02 3.00 Dl1NOOC O363 I.03  :'. b O DMNVOOU364 1.04 ~; . 00 Di1NUOOO36S I.05 O.00 DMNOOC O'J 66 I.06 3.50 DMNOOOO367

1. 0 ' 1.Ou LMtJ0000360

).v3 1.b0 DMNOOOO369 1.09 1.S0 DMt J0000 '. 70

O. oO J.Oi 1.
O D1N0000371 J . v: 3.00 Dr.NO ~)OO37 2 J . CC.' . 1,,0 DMNOOOO373 J.04 1.50 DMNOOOUJ.74 J.05 00 D Mf10 0 0 0 !.7 5 **

J.06 4.00 DMNOOOO276 J.07 4.Ou DMNOOOO377 ,

J.08 2.SO DMNDOOOJ70 J . U t/ c .00 D:1NUOOO379 ,

20.00 l

11. 0 1 1.50 DMrsOv003rK l 1

L . O' . 2. Oi i D M N J O O O .'.0 1 l K.03 3.00 DhlfsoOO3Dz i h . O ri 2.00 DMNOOOO33J I l..O.- .s0 DMNOOv0334 K.06 1.00 DMNOOOU303 I;.07 '. 0 0 DMNOOOO3Un h.08 1.Su DMNOOOO307 L.09 2.50 DMNOOOO3fd3 L.10 2.00 DMfJ900U339 r

TEST CROSS REFERENCE PACE 2

.. a 60ESflON VALUE REFERENCE 19.On L.v1 2.50 DMNOOOO390 L.02 3.7D DMNOOOO391 L.03 2.50 DMNOOOO392 L.04 1.b0 DMNOOOO393 L.05 1.50 DMNCOOO394 -

L.06 1.50 Di1NOOOO395 L.07  :.25 DMNOOOO396 L.08 2.00 DMNOOOO'.97 L.09 2.50 DMNOOOO3YO 20.60 99.00 DOCKET NO 150 I

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