ML20236P252
| ML20236P252 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 10/28/1987 |
| From: | Elin J, Morrill P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20236P238 | List: |
| References | |
| 50-027-OL-87-01, 50-27-OL-87-1, NUDOCS 8711170214 | |
| Download: ML20236P252 (49) | |
Text
{{#Wiki_filter:. V. S. NUCLEAR REGULATORY COMMISSION REGION V Examination Report No. 50-27/0L-87-01 Facility: Washington State University - Modified TRIGA Docket Nos: 50-27 Examinations administered at the WSU TRIGA Facilities, Pullman, Washington Chief Examiner: /0/Jf/87 j Philip J. orri/l, Operator Licensing Examiner Date S/igned l Apprc ved: -
/ 'LT J n 0. Eliri, Khief, Operations Section Ddte 5/igned Summary:
Examinations on October 6, and 7,1987. Written and orgal examinations were administered to one R0 candidate. The candidate failed the oral examination and also failed the written examination. 53711170214 871102 hDR ADOCK 05000027PDR
s s REPORTDETAILS
- 1. Examiners:
*P. Morrill, NRC'
- Chief Examiner
- 2. Persons attending the exit meeting:
P. Morrill, NRC W. Wilson, WSU J. Neigenger, WSU
- 3. Written Examinations and Facility Review Written examinations were administered as follows:
1 R0 Exam - October 6, 1987. All sections. At the conclusion of the examination, the facility staff reviewed the examination. Based on this review, the facility staff had comments on the examination which were discussed with the Chief Examiner. Based on these discussions, appropriate revisions were made to the master i examination key by the Chief Examination prior to grading the candidate responses. .The examiner's resolution of the licensee's comments are documented in Attachment 1. The Chief Examiner observed that the facility reference material contained no useful description of the control console, associated instrumentation and racks. The examiner also found that the safety Analysis Report sent to the NRC was not up to date. Specifically, six new pages in Section 6 were not sent to Region V. The examiner stated that this situation was not acceptable and that up to date, complete information was required. The examiner agreed that prints, drawings and schematics could be sent to the NRC in lieu of preparing text especially for the NRC.
- 4. Operating Examinations:
Oral examinations and facility walkthroughs were administered to one R0 candidate on October 7, 1987.
- 5. Exit Meeting:
On October 7, 1987, the Chief Examiner met with the licensee , representatives listed in paragraph 2, ebove. The Chief Examiner also discussed the grading process for the written examination and the
-schedule. The Chief Examiner restated his concerns regarding the incomplete Safety Analysis Report and the lack of information the control panel. l
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p (. l 1 i [ ATTACHMENT 1 1 EXAMINATION REPORT - FACILITY COMMENTS WASHINGTON STATE UNIVERSITY R0 EXAMINATION OCTOBER 6, 1987. f
; Question: A.03 .
Facility Comment: Part (B) of the question is not applicable to TRIGA fuel because of the high enrichment. The questions should be deleted. 'i Resolution: The examiner agrees. The question has been deleted. Question: B.10 Facility Comment: i The answer to part (a) should be "NRC building demineralized water". , Resolution: The examiner agrees. The key will be changed to reflect this wording. l Question: C.03 Facility Comment: The purpose of the fuel element inspections is to check for fuel element I deformation. Resolution: I l The comment has merit. The examiner will change the key to " check for j fuel rod cladding integrity" which is consistent with the SAR and : technical specifications.
'I
- _ . -. ___---____b
Question: D.05 j Facility Comment: Part (b); the' temperature readout will fail high if the line breaks due to the way the ' circuit is set up. Resolution: Based on a review of the thermocouple data sheets the examiner agrees. The key will be changed appropriately. Question: F.07' Facility (cnment: Part (c); the emergency ' kit is now under the main office in the transformer - ! vault. ~ The emergency plan must be revised. Resolution: The examiner agrees. The key will be changed. Question: G.08 Facility Comment: There is no really correct answer. " Half life" would be a correct answer. Resolution: The question requests the "best answer" thus " curie" will be left as the answer for this test. Question: G.12 Facility Comment: None - Examiner observed that the candidate can close 3.0 Rem vice 1,25 Rem if he assumes that an exposure history for the individual is ' available. Resolution: Accept 3.0 Rem if appropriate assumptions are stated by the candidate.
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i U.'S. NUCLEAR REGULATORY-COMMISSION - c
' REACTOR OPERATOR LICENSE EXAMINATION-
, Fa,:ility: Washington state University -
l Reactor Type: Modified TRICA ] Date Administered: October 6, 1987 Examiner: _ P.J. Morrill ) Candidate: - KEY L L INSTRUCTIONS TO CANDIDAT: p < E q Use separate paper for the answers. Write answers on one side only. Staple: question sheet on top of the answer sheets. Points for each question are indi-- cated in' parentheses after the question. The passing grade. requires-at least 70% in each category. Examination papers will be picked up six (6) haurs after. the-examination starts. ' Category % of Candidate's % of Value Total Score Cat. Value 15.0 15.0. A. Principles of Reactor Ope' ration 15 0 M B. Features of Faci,.11ty Design i h M.O C. General Operati,ng Characteristics i 4.0 ~ 14.0 _ ._ D. Instruments and Controls f V. 0 ' lL0 E. Safety and Emergency Systems g l%O F. Standard and Emergency Operating Procedures W 100.0 G. Radiation Control and Safety
/00.0 Final Grade %
All work done on this exam is my own. I have neither given nor received aid. Candidate's Signature
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L ES-201-11 Enc?osure 2; r REQUIREMENTSFORADMINISTRATIONOF-WRITTENEXAMINATI f 1. 1 m -A single ' room shall be provided'for_ completing the' written examination.-
' The location of. this room and supporting restroom facilities shall. be sisch
'as to prevent contact with all,other facility and/or contractor personnel ?
< during the duration nf the written examination. , --If. necessary, the facility should make arrangements.for ths.use of a suitable room at ailocal school,-'
motel.:or the licensee. other building. 0btaining this. room is the responsibility of: r
. a H
2.
" Minimum spacing 'is required toLensure examination integrity as determined
'by the
- with chief a 3-ft examiner.
space between ~ Minimum spacing should_be one. candidate per table, tables, No wall charts, models, and/or other training materials shall be'present in the examination 7eom. 3; Suttable arrangement's shall be made by the facility if_the candidates _are
-to have lunch, coffee, or other refreshments.. These arrangements shall
-comply examiner with Item proctor.
and/or 1 above. 'These arrangements shall be reviewed by the 4. The facility. staff shall be provided a copy'of the written examination and ' answer key.after the last candidate has completed and handed in_his written examination. vide formal written comments with supporting documentation o tion and answer key to the chief examiner or to_ the regional office section chief. 5,
< The facility licensee shall provide pads of 8-1/2 by 111n. lined paper in.
unopened packages for each candidate's use in comp'leting the examination. The examiner shall distribute these pads to the candidates. All reference material examiner.needed to complete the examination shall be furnished by the Candidates can bring pens, pencils, calculators, or slide rules M into the examination room, and no other equipment or reference material shall be allowed. 6. Only black ink or dark pencils should be used for writing answers to questions. i
. Examiner Standards .
I
= 4 < ES-201-1
,1 . Enclosure 2
+ NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:.
- 1. . Cheating on the' examination means an automatic denial of yhr application and could result in more severe penalties. ~
2.' Restroom.tripsareitobelimitedandonlyonecandidateatitimemay- ., leave. You must avoid all contacts with anyone'outside the examination ! room to-avoid even.the appearance or. possibility.of cheating. l 3.- Use black ink or dark pencil only to facilitate legible reproductions.
- 4. Print your name' in the blank provided on the cover sheet of the examination.
- 5. Fill:in the date on the cover sheet of the examination (if necessary). >
- 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 new page, write only one 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 three. lines between each answer. -
l 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or. table.
- 12. Use abbreviations only if they are commonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for'the depth of answer required.
i
- 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 examiner only.
L
'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.
t Examiner Standards - -
n . c . U ES2 201-1 6 i Enclosure 2' i- 18. When you complete your examination, you shall: a.- Assemble your examination as follows: '
- (1). Exam questions on top. ( /
n (2) Exam' aids -' figures, tables, etc. '
- l. .
(3) Answer pages including figures which are a part of the answer.
. b. Turn.in your copy of the examination and all pages used to answer ji the examination questions.
l
- c. Turn in all scrap paper and the balance of the paper that you did' i not use for sanswering 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.
l l 1 i i I i j 1 l i 1 i Examiner Standards i = _ _ _ _ _ _ _ - -
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' EQUATION SHEET -i 4 <
h '
.f =.na V = s/t J' w =-28 2 s = v,e + h&t Cycle efficiency:=
y 'E = aC a - = l (vI v *)/t
-2 )
s KE = ' mv A = AN -At
- .vg = v, + at ' A =IA,e .
PE = agh- m - e/t A = in 2/tg = 0.693/tg. - {
~l W = v&P D : 6CE/R,* gh(,ff) , (t )(tJ t
~AE = 931Am a -
.Q ' O R.g',- (*4 +. d. t) -
,.9 " p.Cp6T ;
w -IX .
, I . g.
f.
-k=UAAT y . y e-UX Per = Wg 'A i.I,10*/TVL -
.y - p to SUR(t) yyt . 1,3/p P=P o et/T HVL ='O.693/u-SUR-= 26.06/T- e i
T = 1.44 DT SCR = S/(1 - K,gg) SUR ==26 fA*ffp)
,p CR, = S/(1: K,gg )
T = '(1,/p : ) '+ [( f l p) /x p} CR y (1 - Keff)g = CR (1 - Keff)2 2 7 . ' g */ (, _ g - M = ' 1/(1 - K,gg) = CR g/CR0
'T = 4 -'p)/ 1,gg p -
g , 43 _ g. ,g,) ffI ~ Eeff)1 P " (I,gg-1)/K,gg " AK,fg/Keff . SDM = (1 - K,gg)/K,gg p= ~ [1*/TK,gg .]. + [B/(1 + A,ggT )] , t* = 1 x 10 seconds P = I(V/(3 x 1010) ~I A,gg = 0.1 seconds . i I = No i Idlg=Id22 l WATER PARAMETERS Id =Id2 g 3 1 gal. = 8.345 lbm R/hr = (0.5 CE)/d'(meters) I 1 gal. = 3.78 liters R/hr = 6 CE/d (feet) I ft = 7.48 gal. MISCELLANEOUS CONVERSIONS , Density =,6.2.4 lbm/ft 3 1 Curie = 3.7 x 1010dps
*- 3 Density = 1 gm/cm 1 kg = 2.21 lbm
. .< Heat of vaporization ='970 Itu/lbm 1 hp = 2.54 x 103 BTU /hr Heat of fusica = 144 Btu /lbm 1 Hw = 3.41 x 10 Btu /hr 0
1 Atm = 14.7 psi = 29.9'in. l~g. I Btu = 778 ft-lbf I ft. H o y = 0.4335 lbf/in 1 inch = 2.54 cm F = 9/5 C + 32 "C = 5/9 ("F - 32)
l' X
'li l
l l &J CATAGORY A 1 PRINCIPLES OF REACTOP-OPERATION
)
1 QUESTION A.01-(1.5) l t i An antimony-berylium source f or neutrons is used in the d l ' Washington State Univerisity (WSU) modified TRIGA.
, .f (a) Why i s 'en installed source necessary ? (1.0)
(b) What is the process by which- this source produces i neutrons? (0.5) 1 ANEWERS: (a) lhe scu ce ic needed (to actsur e e suffIciont nu*er af neutrons) for accurate inretrument re mings an ti ::entr ol l e- c'. ort-ups. () , u) (b) Raciaactive antimony (Sb-12e' dccayn-crd ema ts e g :urm ray ! (over 1.62 Mev) which interacts with Lerylium ( De -- 9 ) ta prcduce e l neutron (and De-8).
REFERENCE:
NE DD- 101/6, pane 7 73 , end Unit 6 ., p a g e.t 20 QUESTION A.02 (2.5) The WSU TRIGA uses both moderators and reflectors to help maintain the neutron population in the reactor. (a) Why is a moderator necesscry in a TRIGA reacter? (0.5) 1
.l (b) What three substances are used as moderators at the WSU TRIGA? (1.5)
(c) What substance is primarily used as a reflector at the WSU TRIGA? (0.5) AN5WERS-(a) A rnoder at or is rie eded tc.elow d cn-an or thermal i::e t r e neutrCnc (which ar e pr" aciuted 4 h i ;j S energy 3 eve:l ( ). (O.5' (b) Z i r coni um hydrtd= (0.5), Wate: (0.9' a n' i Graphi t e ( 0. 5 ) (c) Graph:te (0.5)
REFERENCE:
Uro t 7 3 p r.q;e 1 ", & 1-/ i 1 1
; t .. 5 % , l e-QUESTION A.03 (1.0)
The symbol b (beta =0.0065) and b(eff) (beta effective =0.00'70) are both useclto denote the fraction of delayed neutrons. (a). Why is there a difference between beta and betal effective? I '( 1. O) (b )- Why does beta effective decrease with core age?' (0.O? (QUESTION DELETED - HIGH ENRICHMENT.0F TRIGA FUEL-NEARLY ELIMINATES THE CHANGE I!< - EETA) ' ANsWEP,- (a.) 7 ne aver age energy 4nr del eyed neu ..r ons, ;E 1 oed than than t*iat for' prom.pt r:cutrons (1.0) . REFEREN',E: L!n i t 6, page 12
.i OUESTION A.04 (3.0)
The-TRIGA reacter core has been designed to have a large prompt negativa temperature coefficient due to the "ce?1'and inhomogeneities", " doppler", and " core leakage" effects-. How does each of these three items.cause the prompt negative temperature coefficient? ANSWERS:
- Cell end -inhomogenitint is caused by the niccofoum hydr ide in %
fuel heating up. This cauws the hydroge, atom to be at a high:+- ener gy level and herdening of t he neur.r are spec t run, ub . + r e r u l t.: in more Icakage out of the fuel elements and more parasitic cauture. ( 1. 0 OCppler i c Bn inCFPas(? in n f/t ' t r on GDSO'ptiCD in nOO-~f UO1 f~ at e" .i b i ChttMed b) LPQadinir'g Of thE FGEOnB7CM Eb 5 DF p t i C '1 f e J l i in I I~ MM OS f LtU te.peratu t- increarm . ( 3. 0)
-Cort lesbaqu in a. , incre mred 1, . a k a q ra of neutrans tot o' the core c
dttO tD 1 i+ 5' c effeCtiV9 DOdf" Uli On Pnd '!O r e p ilP P'i 1 t 3 C *p I LtP r outsidE- th> C OP r? . '1 O) R I F E R !:' J 2
- l. lr) : t 7, pa jP 6-;'6 2
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- .) 3
- 6 QUESTION A.05 (2. O ) - ..
Assumeithe WSU TRIGA is' critical at I we.tt. (beta effective = JO.OO7,-and the weighted meam life = 12.3 seconds) (a) How much reactivity (in do11ern or cents) must be'added'to cause a +20 second period? { (1.O) (b) With a +20 second' period, how long will it takb , to reach 1 KW? "(1.0) A E ERE: (a) T=(b-p)*t/p 2 0 *. p = ( O . 0 9 7 .-- p )
- 1 ? . J f O , =.1 32.3*p O.0861 p = 0.0727 = 40.32 (+/- 0.03) (O. D e (D) P e Po exo (t/T)-
1000 = 1
- exp (t/20) (0.5-I n (1000) = t/20 = 6.9 t ==
130 tietonds (+/-5) (0.5)
REFERENCE:
linit 6, page 14 - 1E QUESTION A.06 (2.0) Hith all control rods inserted into the WSU TRIGA, Keff is 0.95-and the indicated count rate is 10'CPE. After a control rod is fully withdrawn the count rate increases to 15. (a) Before the rod withdratel, how much reactivity (in dellars and cents) needed to be inserted into this reactor for criticality to occur? (1.0) (b) What is Keff after the rod'is witndrawn? (1.O) AN&E RS : (a) p= (KM 4-1)/ toff r n . <m p = 0,, U"; / O . 95 =- 0. 052 6 p $7.52 (+/-0,10) (0, > (b) C1(i - Keft]) = CZ(1 - Kc t f .;l sO.S> 10(0.0D) x 10(1 - L.eff) 0.5 = 15 - Keff+15 Keff2 = 0.767 ( + / - 0 . OO T.J. ) (O 'i.' RE F"ErsENCE : NEDC -103 ~76, pageu 130 -13 4 3 I i 4
s C QUESTION A.07 (0.5) MULTIPLE CHOICE - SELECT THE BEST ANSWER While increasing reactor power to 500 KW you stabilize power with control rods at 5 watts, 200 watts, 1 KW, 50_KW, and f nally 500 j
.KW. I Between'which'two power levels will the greatest control red motion be necessary?
(a) 5 watts to 200 watts I tb) 200 watts to to i KW (c) 1 KW to 50 KW (d) 50 KW to 500 KW ANSWERE: i
<e) 50--tvo KW c o ,. s s REFEF9NCE: WS : Eefety Ar=slyria Frmor t , p a r,e ' -9 t o '5 - 1 1 QUESTION A.08 (0.5)
MULTIPLE CHOICE - SELECT THE EEST ANSWER How will' peak power vary as a function of prompt excess reacti vi ty inserted into the WSU TRIGA?
- a. As the square
- b. Directly
- c. No change
- d. Inversely v,N rAE R :
;>. . 4. t h e; nqtw e (0 5)
IO5F E.Ri?NC rl 2 Sa f e t y F ' n f l y s i '_, Report. Chapter b
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II 4
.5 l-
[t JOUESTION A.09.(0.5) MULTIPLE CHOICE - SELECT THE BEST AN3WER How will fuel temperature vary as a.functicn of prompt excess-reactivity inserted into the WSU TRIGA? ! a. As:the square
- b. .Directly
- c. No change-
- d. Invernely O N 6I*.ER:
- b. Directly (0,5)
REFERENCE:
Safet" Analysin Re,crt, Chmter '5 QUESTION A.10'(0.5) 4 4 i MULTIPLE CHOICE - SELECT THE BEST ANSWER i It is not possible to obtain a sustained small magnititude reactor period for any value of negative reactivity because:
- a. The delayed neutron emitters with the shortest half-lif e determines the long-term decay rate for neutrcn flux.
- b. The delayed neutron emitters with the longest half-lif e determines the long-term decay rate for neutron flux.
- c. Most of the neutrent are prompt and hence the neutron diffusion time determines the long-term decay rate for neutron flux.
- d. Most of the neutrons are prompt and hence the neutron !
slowing down time determines the long-term decay rate for neutron flux, ] i l , Answan: ; l
- e. 'cos 5)
J RcrEREscE: u, o m mm e m I l 1 1 5 l
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.5 O'UESTION A.11 (0.5)
- , . MULTIPLE CHOICE - SELECT THE BEST ANSWER When the WSU TRIGA is operating at steady state 1 MW, the heat transfer from the fuel cladding to the ccclant'is'best characterized as
- l I i
- a. Natural ccnvection .j b '. Natural circulation
- c. Nucleat boiling 3 i
{
- d. Film boiling j M.is s.::
- a. (0.5)
RFFERE^:E F : U::it 7 , pi< t.O 1 -2e i I i j 1 h 1 1 1 i END OF CATAGORY A ) GO ON TO CATAGORY B e 1 1 j
s- , l 4 CATAGORY'B FEATURES OF FACILITY DESIGN -j f QUESTION B.01 (1.5) i The.W5U TRIGA uses bcth " standard' . and " FLIP" f uel .{nthe i l reactor. ' l What'are the two major differer.ces between " standard" and . " FLIP l fuel? 4 ANSWERS: an em 'a c h rrmn t (U-2V5) o+ 70% ver mur ce 'X4 i r; ' t (- FLIP fuel b zu. standerd fuel (0.75) ' no FLIP fuel c oa t..:.i n s crb t um .s a t;u-nc.b i c p o l t:.on . (0.76) REFEREPCE: Module 11,.page C , QUESTION B.02.(2.0) The fuel clusters contain-3-rod an'd 4-rod fuel clusters arranged around the control blades. (a) How are individual fuel rodsuidentified? (1.0) . , 1 (b) How are fuel clesters identified? (1.0)
-4 W cRE:
(a) Eiot-i al rwnber s ar e l oc ate ' cn the sot torr, end fintur e. (1.0) i' (b) Der i rsi numbers on one cide of the cluster bottom 'doptor identify fuel clusters. ( .t . 0 ) REFE~RENCE : React or core d i ag. arm, , page i " Fuel Cluttern" t i 1 4 _ - - . _ _ _ __w
1 p'. i > f I l
- ;y:
l GUESTION B.03 (2.5) l
'What are ' the f abrication ' materials f or .the f allowing .WSU TRIGA J
- '. reactor; components? ( O. 5 e a t.;h )
\? (a) ' Fuel' cladding material?
'(b ) Safety blade neutron absorbing material? q (c) . Regulating, blade neutron absorbing meterial?
(d) Transient centrol rod neutron absorbing material? (e) 'W t . % " o f uranium 'in the fuel? 4 ANSWER 9. j i te) E:tainleet eteel (b) Borai (c). Stain 1rta st eel i
. (d1 Bare.ted graphite ,
(p) 9.5 Wt% ! RE t'ERE NC E : Sid et y (v.al yui r N e p : - t ,. pege MIL and 6 9 t ' v r- ,5 > ;4 ar; t' 4 '? QUESTION B.04 (1.5) Refer to the attached Figure B-1 which depicts the transient red drive mechanism. Identify as clearly as possible the location.of each of the items listed below on Figure B-1. (0.5 esch) (a) Ball faut (b) Operating (air) pisten ic) Shock absorber anvil AN5tERG j E ar- s t r b re d Figure F-1 REFEf 2NCE: Lefety Aralpib R c r. o r t , p r e ' 4 -20 l I 2
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s l a 1 1 yy'; L1 \ f_ l I W l r l N
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l 1. Pneumatic-Electromechanical Transient-Rod Drive FIGURE 6 -J
= 1 l
g SHOCK ABSORBER RETAINING NUT t SHOCK ABSORBER R SUPPORT a SHOCK ABSORBER AIR VE.NT gg - SHOCK ABSORBER (0,5) anvil ' PISTON ( Oi5) DR M TOR "
' BEAR G BALL NUT (O,5 )
[ CYLINDER SCREW R. __';;. f J, i rF, NBALL NUT DRIVE GEAR s {
. i N' DRIVE POTENTIOMET WORM i
BALL NUT s} POTENTIOMETER DRIVE WORM y DRIVE GEAR d CYLINDER SCREW END CAP { l "O" RING SEAL AIR SUPPLY W. % ROD GUIDE I SUPPORT n.. l 7% PISTON ROD ' ROD CONNECTOR l' DAMPER CONNECTING ROD Pneumatic-Electromechanical Transient-Rod Drive , FIGURE [3 - \
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l QUESTION B.05 (1.5) 4 i
]
Refer to the: attached Figure B-2 which depicts the drive f I mechanism for the blade type control rods. Identif y as clea-ly as possible the location of each of the items listed below on Figure B-2. !O.5 each) 'l L ' (a) SCRAM magnet (b) Bal'l - scr ew , 1 (c) Overload clutch ANJWERS: I See attached 5 2 trur e Es2
REFERENCE:
Saiety Analysis Repo-t, p age 11-17 I QUESTION B.06 (0.5) MULTIPLE CHOICE - SELECT THE BEST ANSWER The N-16 diffuser is designed to: (a) reduce the oxygen concentration An the water above the core and'thereby reduce the N-16 radiation at the bridge level. (b ) - break up the gas bubbles of 0-16 and thereby reduce the probability of forming N-16 and reducing raciation at the bridgeLlevel. (c) increase the transport time for the N-16 from the. top of the core to the pool surface thereby decreasing N-16 radiation at the bridge level. (d) provide colder water above the core to maintain N-16 in solution therby decreasing N-16 radiation at the bridge level. ANOWErG : (c) (0.51 l RE PE NENEE . Lefut Analyui; R yaet, page 4<3 q q 3 4 1 ___ ___ _ __-_______ D
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QUESTION E.07 (1.5)' l 7- .{ [ j The Technical. Specifications state that pool cooling water'is used to cool the reactor and to provide radiatic'n shielding. ta)- What-special measure is required.by the Technical Specification's f or piping which { j extends more than five feet below the~ surface < of the pool? ." (1.0) i (b)- .What.is.the minimum depth of water above the l core required for operation by the Technical 1 Specifications? (0.5) l , 1 L AN5WE;:S: .
.i (a) Prc.vicicos to prevent innoverten, ri phor i ng ef'the poc1 ar e required. ( 1. O) q W) 15 fert c4 water ( 0 . ', )
l i
REFERENCE:
Technical Spec 1ficationc, page 27 ' QUESTION B.08 (1.5)
~ The Technical Specifications limit the reactivity of the reactor and of experiments. l i
(a) What is the maximum excess reactivity of the core? (cold, Xe f ree, critical) (0.5) 1 (b) What is the maximum reactivity of any single 1 experiment? (0.5) (c) -What is the maximum reactivity worth of all installed experiments? (0.5). ) 1 f.NSWERBs (a) 13.00 (0. 5 ~ l (ti) $2.On a S) (ci 15.00 (0.9) RE FE ff. NG. lechnica; Spt>.)ficatio w , p r :.; c + 7 .yt r, d 14 ! l 4
U_ g QUESTION-B.09 ( l '. O ) COMPL.ETE THE FOLLOWING STATEMENT In accordance.With the. Technical Specifications, the WSU TRIG 4 reactor shall not be operated unless the shutdown margin.provided by control elements is $0.25 or greater with: { What three additional pr ovi si ons? (three items O.33 each>- pnwi;g , e (1) the tisgherd worth un cet ur e:' expF-foeit'1E in'jtm rir.t reactix- posit:cr. (2) .the h1Ch eW: Wbr t CDntrc: element. cod r e: yule 3 na e ' enc > . er> fU.11y W i t h *j r n Wr1, (3) the'reacto' iE cold critical, and wiTfwet'denoP, REF ERENCrr.: %chnical Specidicataans, pagc 8 QUESTION B.10 (1.5) WSU TRIGA pool water must be. periodically replenished. (a)- What is the source of normal make-up water? (0.5) (b) How is pool level maintained? (0.5) (c) What two components purify make-up water prior to entering the pool? (0,5) ANEUERS: . (a) i4RE puilding deminer alized water (O. S) (b) p float switch in the pool controi n a s:ol enoi d val ve - i n the make-up water line. ( O E; ' (c) The " C u l l i g ra n " demineralized s y F, +;. e m and the mimed tWd ion eMChhnGr?. l0 3:
REFERENCE:
Saf e' y Anal ysi s Report , pagea 4-30 cnd 4-24 END OF CATEGORY B GO ON TO CATEGORY C l . 5
CATEGORY C GENERAL OPERATING CHARACTERISTICS QUESTION C.01 (2.5) The WSU TRIGA uses five control rods numbered 1 through 5. For each control rod listed below, what is the associated reactivity?.(+ or - 10%; O.5 each) (a) Shim #1 (b) Shim #2 (c) Transient #3 (d) Shim #4 (e) Servo #5 ANSWi:Rt. : (0.5 each) (a' $2.54 (b) 1-3.57 (c) $3.45 (CAF) (d) $4.39 (CAT) (e) 40,44 REFLEENCE: Unit 11, Ap p s titii ;s , u =: g e 5 m:0 FIN, pam D- 1 1 j I 1 1 L-___._______..
l QUESTION C.02-(1.0)
'The WSU TRIGA is critical in manual control at a power level 500 milli-watts when the following events occur, independently. ]
i How does each of these events (considered one at a tjme) affect j reactor power level? (assume no control rod motion) L 1 1
)
(a)- A large bubble of a2- is introduced into the core area. 1 I
)
(b) Pool temperature increases 10 C. i ANUNERE: (a) Ebertor power de7ences to - 2 Lee 1 c. v ca l , CO.b> ; (b) Re:ctor povmr will introase o'd std e}inc et the point of adding heat. ( 0 . 6 ,' FEFEREiCE Unit 11, App:ndix, papc 3, OUESTION C.03 (2.0) The Technical Specifications require fuel element inspections at intervals not to. exceed the sum of $3500.00 in pulse reactivity. The Safety Analysis Report explains the derivation of this interval an .tates that "only those pulses over $1.50 should be summed for is.2pection purposes." (a) Based on the SAR, what is the primary purpose of these periodic fuel element inspections? (1.0) (b) Why may pulses less than $1.50 be excluded from the summation? (1.0) ANSWERS: (a) To check for fuel c l add i r.g i n t ettr i t y (1.C (b) Only pu]ses above $1.50 will produce temper _.tu-es above nornel F,teady Et ab Opt r et i Grm. (1. O
REFERENCE:
S Ar< , p a g e 6-12, ',-14, TG ' 4 r. n g o 21 i 2
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e- , f-DUESTION C.04 (1.5) Refer.to attached Figure C-1, which shows a schematic drawing of'.
'the Pneumatic Transfer (Rabbit) System.
(a) Towheredoestheairfromthesystemexhaust?{ (0.5) (b) . What are the air flow direct 2cns for removing a." rabbit" from the cere?-(Draw arrows on Figu@
'C-1 et points A,B,C, and D.> - ( 1.' O )
~ (.mWEars ; ,
-( a ) Yo t h t.- be!4m r D o m- (menitored) exhaust , /Q.5)
W) See sttached drawing-
REFERENCE:
SM s page 4-37 QUESTION C.05 (1.5) During operation power is produced by the fissioning of uranium in the fuel. (a) Immediatly after a pulse, where is the hottest part'of the fuel? (0.75)- (b) During steady state operation, where is the hottest part of the fuel? (0.75) 4NEiWERF,: (a) Edge of the fuel meat rent to the cleddirm. (0.75)
-(b) Along the fuel centerline. (0.75)
REFERENCE:
Unit 7, page 6- DO :) 1 i 1 3,
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Ja; p-L QUESTION C.06 ( l'. 5 )
-Technical Specification. core configuration limitations are used l to ensure fuel temperature safety limits are not exceeded.
(a) What is the minimum number of FLIP elements in a " mixed" cere? (0.5)
?
l
.; - (b) What are the limitations on water holes in ,- l the FLIP region of'the core?' (0.5) ln I
(c) What does a PTR limit of 1.5 mean? (0.5) ! i ANSUERS- ! ( e, ) ii ,',) 2? (b) an!y non-adjacenmt single rad hol es era eilawed. (0,5) j l (c) Peak ta measured futl t emperatorn i e i es:s t hi-n l '. 5 : 1. O . (O.5) j REFERENCE; 'iethnics1 Specifications, pege 9 i QUESTION C.07 (2.O) l j The dif f erential worth of the control rods varies with their ' position-in the core. (a) Why does integral control rod worth vary from near zero at the top, reach a maximum at the ! middle of the core, and decrease to near zero et the bottom of the core? (1.0) 1 (b) If one shim rod were left fully inserted in the I core, why would the totel wo-th of the other ] rods increase? (1.0) 1 l l A N S W E R E ': (a) F]La varien from the tco tc the cattr~ c4 the 1 l core, r e tic h i n g a maximum in the miMdle Red I worta an determined by t. r f iv 4. ' ros " v oet." . :i t (b) The f 1 t.: wo u : in bs s h : 4 t 4.n ' t atte: dt ttic attier r o d r. , and b re.c e twy v uld t t- e - n i g h :.f r flun. ' ', . ; ) ) RECE RENCE f t'JE D :i- 1 t. 0 9 6 , pager 17- - 128 j l l l 4 e____-_.
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e' ) e OUESTION-C.08 (2.O) Refer:to: Figure-C-2, which..is a sketch of reacto.r power verses time in hours. i A stattup from-xenon free conditions to full pcwer o. curs at' time t == 0 . At t=60 the. reacter is shutdown and restarted a{ gain et t=90 hours.
, (a) SRutch ths Xenun reactivity response in the
" r eactor ' f or this transient on Figure.C-2. (1.0) (b) At approximately what. time will xenon first reach'near equiltbrum concentration for.100% power? (0,5) (c) At what time will the maximum xenon concentration occur? (0.5) ANOWERS: (a) 500 stteched drewir 0 (0. ; ' (b) 30 to 4D h e ar t. ( r: ) 65 to 75 hour > -( 0. 5 ) 9EFERENCE: NLDO 1 0 3 % ., p u e r t- l'- -- 15e i
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i i END OF CATAGORY C GO ON TH SECTION D 5
e' 4 $ I L l ~ . 1 CATAGORY D I INSTRUMENTS AND CONTROL 4 l QUESTION D.01 (2.0)
\
The WSU TRIGA facility.has conductivity cells and temperature j sensors in the water treatment and cooling systeras. i i (a) Where are two conductivity cells located in the '1 pool water treatment system? (1.0) (b) What four temperatures in the pool cooling system can be read out on the control console? ( 1. 0 ) ANSWERS: (e) At the inlet and outlet of the bypass n ' x ed Ded icn eP c h an g tir . (1.0) (b) T*r i mar y into and out of HX. Secondary into and act of HX. (1,0) I
REFERENCE:
Un2t 11, dr awi ngt QUESTION D.02 (0.5) MULTIPLE CHOICE - SELECT THE BEST ANSWER The quick disconnect pin of a shim rod has been inadvertently renoved and not replaced. When the operator attempts to raise the blade out ! of the core:
- a. the blade in light will go out, however the position indication will not function normally.
- b. the blade in light will go out and the position indication ,
I will appear to function properly.
- c. the blade in light will stay on and the position indication will not function normally. ,
- d. the blade in light will stay on, however the position indication will appear to function nc-mally.,
ANEl4ER9
- b. (0.5)
R
REFERENCE:
Unit 11, Fi m>r e 11-1 , 1
QUESTION D.03 (2.O) / A fission chamber is used for detecting neutron flux at the W5U TRIGA !" reactor. (a) How does a fission chamber distinguish neutron l from gamma radiation at low power levels? I ~( 1. 0 ) (b) What two interlocks are dependent upon the power level signal generated by the fi ssion chamber? (1.0) AN5UERS: Ic) A discriminator circuit is ut :d to sd a r !-- :te
+11 pulses below a presct tFreshc1M. (;.o)
(b) Delow 2 CP5 r e d ta cannot be w i t h d r e; w, (0.5) end above 2 KW the reactor c a r.n ot be pul sed. ( 0. 'C ) REFEPE NCEi , OAR Ch ap t er 4, and Lb ,i t O, p;ae (7 1 QUESTION D.04 (2.0) Fo11cwing a reector power calibration a re-startup fo- calib-ation is being conducted. (a) If indicated power was higher than e.ctual power what must be done to the chacbers to correct this error? (1.0) (b) If the pool divider gate was not installed during the power calibration, how will calculated power be affected? (1.0) ANEWERS (a) Tl e t h e rr b tr t; must be r ei s'sd . (1.O' (b) Calculated pow v will be less than actual powar. (1.0
REFERENCE:
SDF 13 1 2 _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - a
l QUESTION D.05 (2.0) 1
'You are conducting a control element calibration us:ng Standerd Operating Procedure 16.
(a)' What-method (name or a brief description of the method used'is acceptable) is used for -{ control element. calibration for license and Technical. Specification requirements? (1.0) (b) What other method'(name or a brief description of the method used is acceptable) of calibration is avai1able to check total rod worth? ( 1. O) ANSWER 4; (a) 1.oub l 3 ng iirw c. <' 4u] ding iimt' rad hod. il.U (b) Rod drop method (1.0)
REFERENCE:
50P 16 QUESTION D.06 (1.5) Two fuel elements are instrumented tc provide signals to the temperature monitoring channel. (a) What' type of temperature senscr is in the fuel element? (0. 5: (b) If the wire to the instrumented fuel element were to break, how would the temperature readout be affected? (1.0) MGWER S - fa) i ner mot aupl et, (O 5'
]
(n) lt woa.1 d f a.11 high ( r. o ' c u r t r" n t i t I . O .' REiFE R.T N:..;E t, EiN0 4-9 ta d e-iO, Elt: trcn:in T a w a n ;) Ft c : .! 6
;- ,i n : 4 u s' Manitor.nr- Ch a n ru.;l and Acrac;a T! -Sp ec s . 31 UXU Type F 3
a QUESTION D.07 (2.0) 1' The transient rod is used to pulse the reactor to'high power
. levels and it is also'used as a normal control rod.
(a) What holds the transient rod up when it is . operating as a normal control rod? . (0.5) (b)- During a SCRAM, whet will happen to the A transient rod if the solenoid is stuck
<- in the " energized" position? ,
(1.0) (c) . How does.one adjust the amount of reactivity in a pulse? (0.5) AN9WEF.5 : ] 1 (e) Air pressure 'O.5) j (b) Ihe red wi l l - nat ' SCR Ai*t er it will follow ttw ' cylinder drive. (1,01 (c) Re acti vi ty is adjusted by the cylinder d r i v e ., (0,5)
REFERENCE:
b AR 4- ? thr ough 4-22 l l l 1. l 4
i 1: jj; QUESTIch' D. 08 -(2. O) s Compensated ion chamber nu'mber 1 supplies a signal to the linear i power recorder. (a) If the compensating voltage is set too high (overcompensated), how will indicated power { j be affected at very low power? (0.5) (b) If the compensating voltage is set too high ! (overcompensated), how will indicated power ; be affected near full' power? (0.5) l (c) What'is the main advantage of a compensated ion chamber over an ion chamber? (1.0) ANSWEFS: (e) Indicated power will be too l ow, (0.5 (b) Indicetcd power will bc only 2,l i r 5 t l y (i' ct e} } } affetted. (It wi11 b e- c.12 c h t j y 1 c'w ) (0 '>i (c) The comp enna.ted h n t., a broader ringc duc to c l i mi ni<ti on u4 the e++ ectr, t f gar na r adi cti or . Or it O?n d E:t CC t n e u t O n f 1 LU tC I. oh EP 1OVC C. with g r e 71 c" a c t ur a t; y . ()- ' ? r::E FERD G : Unit 8, pa,c 29 END OF CATEGORY D ) GO ON TO CATEGORY E 1 I ( 5
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I j; CATAGORY E j SAFETY AND EMERGENCY SYSTEMS j 1 l QUESTION E.01 (2.5) j l 1 Besides the period SCRAM, the manual SCRAM, end turning cff the ,l master power switch, there are seven other slow SCRAM signals in j the steady state mcde of operation. 1
)
What are five of the other seven SCRAMS?.(Include setpoints.) J AN9WERE. ( O. O Ef dt;h #Dr Any i i P )
.. High fuel t e mp eir at ur e , 500 c
- 2. Seismic detectiar.
~; . CIC H'.' f a i l ure 4, leg-N HV failure 3
- 5. Safety Channa] 1 12"% -
- 6. Safe *- Channel 2 1MO
- 7. Bu i d I n :.1 E.vacuatiom RECERENCE: Unit 11, SC'#!1 c ' r t. L i
- y i
GUESTION E.02 (2.0) The WSU TRIGA facility has a heating are air conditioning system (HVAC) which can' operate in normal, isolaticn, and dilution modes. (a) During normal operation what is the pat h cf ,, inlet air to the pool r oom'? (0.5)
]
(b) During the isolation mode, how is the pool room i sol ated? (0.5) 1 i (c) From what two locations can the HVAC system be controlled? (1.0) ANbWERS: (n' Air e et cc r n through a r ou g:.i ng filt& , e apply fan s =. n d italetion dempers ir.tc the paa: roon. (n 5) s (b) Damptru c'n tho pool supply and ed unt ducting j
; hut to isalrtc the r om, ( 0 '5 ) l (t) Controlr are in tn2 main ro,tr01 rarc 'nd (emtrgency ControlE Ere\ in thC 'ijn Off1CO. ( 1. ' i REFERENCE- Em pages 3-1, '#, and 9 1
l
- _ _ _ _ __ _ . _ _ . - _ _ - _ _ - _ - _ _ _ _ _ _ _ i
l' < l i l. I t l ?. , ' l OUESTION'E.03-(2.O) I 1 L What four SCRAMS'must be available in the pulse mode of 1 operation? (minimum safety channels which SCRAM the reacter) A!D!E RG , (o;S enb';
),
i
- 1. in g' f ue] t (Tpr m o i j
1
- 2. M ntes t ..MJRAM i
- 3. Lcmn of hir.- v a l .. a ra r t a p o w.
- rLann13i I
i ei . irenuient rad SCN ' a + t<-:cr pulun j R Ei+:Rb t.lE : E n H ., pane 4-?t, QUESTION E.04 (1.0) One of the interlocks associated with the minimum reactor safety channels prevents control element withdrawl in the pulse mode. Based on the Technical Specifications, what is this interlock designc-d to prevent? p,NRW-- M : TML intrrieci ; i nt :anded t r p r c e:- + p u,1 r :. n c the c_ectt- 'il o an a pacdtive pertad,
REFERENCE:
Ttchn2 cal Spet: fa:erjons, p a cic - 12 QUESTION E.05 (1.5) While the reacter is cperating a sample is withdrawn from the core causing an area radiation level of 300 mr/hr on the bridge. What three alarms cr indications would you expect to see? ANGv;r ::i (O.5 each)
- 1. For 1ight 'u i A! ?
- 2. P. ' i i d a ng ",d t'ta' al. o
- 3. Ye lv 1tg^t o~ Cm tm i e ' 7 L eci -
REF-{RF NC F - EIJ' 39 2
L i QUESTION E.06 ( l '. 5 )
-The conductivity in the primary coolant is 7 micremhor/cm and
- i. increasing.
[ h at three alarms should you see or hear f rom the co sole? ANSWERS-(O. eact) ~j 1 1, re;c I: ;ht r c or clu t t 2 v-i t ,' mcriit:r
- 2. ' F: a 1 Dii 1iCht O ri _ 2 9 6 . 1. e 3 3 9rfn bC3rd
- 3. n,nunc a at c" s c e r rb o r; REFFi:EtJCE: c OF 1-QUESTION E.07 (1.0)
What indication does the operator have if one of the beam port plugs is inadvertently lef t open? ANSWERS: 1 Red }ight ori bear p te t pannel. ;
REFERENCE:
GOF 19 l i i 9 U
. i DUESTION E.08 (2.5) !
The Technical Specifications require that four channels of radiation monitoring instrumentation be available to the operator during reactor operation. One is the area radiation monitor on the bridge. { (a) What are the other three channels? (1.5) (b) If a channel is out of service for maintenance what must be done to meet the intent of this i Technical Spec 1fication? (1.0) cNEWERO: (a) (0.0 each)
). Area ratti a t i on me1)to" in the '
" in r orm-
- 2. Continuous air monitor
- 3. EMhaunt g;ct nonttnr (b) The channel can be reol acea s e *~ h a pretable i n t + r t. im it W1i c h hce its own alrrm er in kcot u r. d e r viauc1 observat)c'n tJ.9) i
REFERENCE:
'echnice2 Speci fi: r.t i e n s , p 2.c r l?
4 i i
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1
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i i I END OF CATEGORY E ! GD ON TO CATEGORY F 1 I 4 l l l I 1
CATEGORY F j STANDARD AND EMERGENCY OPERATING PROCEDURES 1 OUESTION F.01 (2.O) l t Following an Exhaust (sas Monitor alarm you are following SDP 19
- 3 for " Action in Event of Alarm".
(a) What three immediate operator actions should be taken? (1.5) l (b) When'may the ventilation system be placed in AUTO? (0,5) 4NSWERE,. (a) (0.5 eacb> l
- 1. I sol at t.: the vt; t i ?. a t i on svt.mi ;
' . ' . Nati f y tl.r- SRO an duty i
- 3. Irivent 5 u nt.e tF c m.m r f t h t.: el r r:. l (b) The venti 1Etion syntem c.
- bc op ~ :% t d in AUTD w!ien the r e c& it 5- : 1 1. w the c]c>m L.t ;.oi nt . (C J) 4 REFEREtCE: SCP
- l, QUESTION F.02 (2.0) '
i The Technical Specifications define v. hen the reactor is " shutdown" and when it is " secured". l (a) What conditions must be met for the reactor to be shutdown? (0.5) (b) What three conditions must be met for the reactor ] to be secured? (1.5) ANSWERE. (a) Tie reatur i t, s h u t '.lt e Whv ;t in t,c. cur ed la s at 192 .t ..i l . C Q (( " i a i (b) (C . D ec :h) i
- 1. The roet*_ar le nh a ld :. A ~
q J 2 Tbc c a,m,l e Ec y w tch .c cf4 . , , _ t. b e key contro]m by =- 1 1 c t ra:4: " pr- c ~ . .
~"
N7 work i s being dare c ', the carc cr its' control med anicou.
REFERENCE:
Technical Spcci f i ceti en s , page ? 1 I
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( 4 l < QUESTION F.03 (2.0) i Standard Procedure No.7 is used for core changes and f uel 4 movements. . 1 I ,'
-( a ) What tno individuals must be present when I moving fuel from one core location to l another? ,- (1.0) .
i l (b) What i<s the purpose of the inverse j multiplication plot which is maintained r I for core loading changes? (0.5) ; ( c ~) Who must be present when fuel in storage (not in the core) must be moved? (0,5) ANSWERS: i
- (n). A reattcr operttor (at the concole) cnd a ' s e n i t:r operator w.toervising the f uel mov e'nen t . (1,0)
(b) Thici iL done to detercoine the critical
]oading or ttie' ap '-rc:'i nt e recees r e ac t i vi er . (0,5)
(0,5) (c) 'A serior re rtor ar; erat r. i REFFRE C.E: EF ~/ ii t
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p fi , l QUESTION F.04 (2.0) l; In the event of an Emergency Situation, Standard Operating Procedure No. 6 li sts three emer ge-ncy. ce.tegories; . saf ety event , l unusual event, and. alert event. i 1 For each of the events listed below what is the apprlopriate l emergency caterory? (0.5 each) l 1 (a) Anti-nuclear demonstrators block the access to the { facility, l l (b) The transient rod is stuck in the "up; posi ti on. (c) An individual is contaminated and the radiation level i s 20 mr/hr at one f oot. . (d) A " rabbit" sample holder breaks open in the core and { releases its' contents. No alarm setpoints are reached. ANSWERS: (0.5 each) (a) Unusual event (b) Alert event (c) Eiaf et y event ' (ci) Unurual event !
REFERENCE:
SW2 6 l l l i I l i I 3
.____--_Q
'p . f QUESTION F. 05 '(0. 0)
Standard Operating Procedure Nc. 4 is used for Etertup and ; operating requirements for the reactor. l (a) What are three of the five condi tions wh:, ch require a senior reactor operator tobepresent{ p at the facility 7 (1,5) (c) When the reactor is critical, what personnel are 1 required to be present at the Radiation Center? ( 0 , 5 ,' i I
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By,the Standard Procedure for Performing Experiments there-are
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(b) Who may make temporaty changes (that do not .- i change.'the original intent) to the procedure i l for an operational experiments (0.5) (c) Who must approve changes to a non-operational experiment which required a hazzards analysis? (0.5) a i 4! _ 'a w -.c o erets u n:pe-scents requu e cc,no el l
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r + < g 6': 4 4 QUESTION F.07 (2.0) { 4
- During an emergency at the facility, the Energency Preparedness Plan describes facility emergency organization and facilities. j (a) Who is designated to function as the Emergency {
Directer during.an emergency? (0.5) (b) During an emergency, what are the two primary responsibilities of the reactor operator? (1.0) i l (c) Where is the emergency kit (containing protective clothing, first aid materials, and decontamination supplies) located? (0.5) (e:7WERE : (a> Thr r.en i or r ratt or p r." a t o r with the mont conte aty ir the Ermr g en r::s Dire:ter. (0,5) I (b) Thr r e rIt n" cgpr nto* 15 - e r r;. nsi b] e for the ] cafe s 'n.t d owc and securino the recctor. ( 1. ' , (c) U , ct.v . re i n c e f a ce ,i n Tr an r,f or me- Vault ( 0 . ". i REFERF ' CE: Emer g ren c y Pe rep a r ed n ess Plan, pages. 10,'12, 30.s snd- -
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i i l l i l END OF CATEGORY F GO ON TO CATEGORY G l i b l l l l ____ ______-. 1
t P h. h;'>- L. l s . CATEGORY G RADIATION CONTROL AND SAFETY l DUESTION'G.01 (2.5) f A survey of radiation 'and contamination levels has been made by the Health-Physics Monitor. The map (Figure G-1) an the. 7 f o11cwirig page has the results of this survey. Answer the following questions based on 10CFR20. Portions of 10CFR2O Appendix B, Concentrations in Air and Water Above Natural Background (Figure G-2), are also provided. (a) What posting is recuired in the Reactor' pool
- Room? (0.5) -
1 (b) What posting'is~ required in the heat' exchanger ! and pump room? (0.5) j (c) What posting is required in the reactor shop? (0,5) ;
.l
.(d) What posting is required in the sample. j preparation room? (0.5) ,
(e) Which areas must be locked or access othe-wise controlled in accordance with 10CFR20? (0.5) ; i 1 ANSWERS:
-l (a) CAUTION - RADIATION AREA ( 0. N (b) CAUTION-AIRBORNE RADIOACTIVITY AREA (Os N (c) CAUTION - RADIATION AREA (U.5) l (d) CAUTION - HIGH RADIATIOu AREA (0,5) j i
(e) The samp1t; prepa-ation rocm K> f ) ! l REFEREUCE: 10CFR:30 l l
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Port 20 pp.B-APPEN0ix B-CONCENTRATIONS (See loostsees at and of Appenes 0) IN AM AND WATER AsoVE } NATURAL lootope
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we w m0 er Cot 1-4 ' we w, h leene (53) i 126 8 5x104 4 x to-* 4x1r" 2 x 10-' 1 2 x10*' 6x 10-8 8x t0" 1 128 8 O x10** 2 x10" l Ex 10** 9x10-" 3 x t0 ' 3x10*' 3 x10-8 1x10-8 0x10-e 1 129 8 2x10-* 1 x10** t 2 x t0*H Sx10-s
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4 131 8 0 x 10-* 2 x10" 8 0x109 1 x10*" 3 x 10*' 3 x 10*' 2x10-8 1 x10"
$132 S 2x10*' e x t0-a 2 x 10" 3x10-* 0 x10" i' 9 x10" 8x104 ' 3x 10" 2x10" l 133 8 ~ 3 x 10" 2xtr* 4 x 10-" 1 x 10**
1134 8 2x10*' 1 x10-e yx io-o 4xio% 1 8 . 6x 10*8 ! i 4x10 8 8 x 10-* 2 x t0-e 3 x10" Ex t0** 1x10" 6 x 10" 1135 5
'(' l 1x10" 7x10" 1 x 10-' 4 x t0-8 huhan (17) e x104 2x10-8 1 x10-s yx io-o D 190 8 1x 10-e e x to-s 4 x io-o gx ig-4 6 1
4 x 10*' 8 x 10** 1x10" k lt2 5 1x10" 1 x 10** 2 x 10*8 8 4 x 10-* 4 x10-a - 3 x 10** 1x10-8 ext 0*" k 1b4 5 2 x 10*' 4 x 10-* 1 x t0-a 4 x 10" 3x10-8 t 2x10" bon (26) Fe 55 ~ 5 9 x 10-' 6 x 10** 3 x10-e .l 0 x 10-' 2x 10*
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7x 50*' 6 x 10" 3 x to" 2 x 10" I 2x16" 1 x 10*8 Neodynwurn(60) led i44 Fx 104 4 x10 e 8 8 x 10-" 2 x 10" 3 x 10"" 3 x 10-" 7xto" Nd147 1 2x10" f x 16 " 8 x 10-* 4 x 10-' 2x10* 8 1x 10 ' l 2 x 10*' 6 x 10" 2xtr8 8 x 10** 4 x 10" Nd 149 8 2 x 104 8 x 10-8 0 x 10" 3 x 10" Neptumum'(93) 6 1 x 10-' 0 x 10** 6 x 104 Np 237 . $ 4 x f o'" 3 x 10" 9x 104 1 x 10"' 3 x 104 '{ l 1xW" $ x 10** 4 x 10"' Np 239 3 x t0 8 j 8 4 x 10" 4 x 10-8 i 3xtra 1 x 10-* i Netel (28) Fx10" 4 x 10 8 2x 10
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l, V' I QUESTION G.02 (3.0) A radioisotope with a half life of 24~ hours which decays by'one 0.5 Mev gamma emission has just been removed'from the reactor. The measured radiation level at- 1 foot is initially 200 mr/hr. j (Consider each of the following questions one at a t me.) (a) How long will you.have to wait until the sample radiation'is decreased to 2 mr/hr at one foot? ' (1.0) q i (b) How far away from the sample will you have to move to decrease the initial radiation level l to 2 mr/hr? (1.0) ; (c) How many curies .are in the sample? (1.0) ANSWERS: 1 (a) R=Ro 2+ + (-t / t ( j /2)) - (0, b ) 2/200 = 2**(-t/24) 100 = 2**(t/24) ) t *- 7.7
- 24 = 184 hours +/- 10 (0. S) j l
(b) D =t Do(r{o}**2/r**2) )' 2 = 2OO(1/r**2) 10.0) r**7 = 100 r = 10 feet (0.01 l (c) D= SCE/R+*2 200 = 6C(0.G)/1 ( 0, b) C = 200/3 j C = 67 curies U..C) j N
REFERENCE:
SDP 12 a i 1 l I l l l 2
l b 7-QUESTION G.03.(1.5) The Health Physics Monitor performs surveys and takes samples daily which are documented on survey sheets. Based on facility L procedure 10, excessive dose rates or removable contamination levels are noted in the comments section of the surv y sheet. (a). What. constitutes an excessive dose rate in a Radi ati on erea? ,' (0.5) (b) .What constitutes an excessive dose rete in an unrestricted area? (0.5) (t) What constitutes an excessive surface contamination level from hallways or stairways between laboratories? (0.5) i ANSWERS: l (a) 50 or /hr (O. S) ! (b) 1 mr/hr (0,5) (c) 10-4 microturies '( 0. S )
REFERENCE:
EDP 10 a GUESTION G.04 (1.5) The Quality Factor (QF) relates biological effects o+ di4ferent types of radiation to the energy deposited. The GF for gamma reys is one (1). What i s the- QF f or each of the following radiation types? ; k (a) X-rays l 1 4 (b) fast neutrons (c) Alpha particles ANSWERS: ) I (0.5 each) j 1 (ft) ) i (b) 10 ! (t) 20 I
REFERENCE:
Unit 10, Chapter AllI, p iv 1 ei: 3
i 1 1 A:- l
'- . l QUESTION G.05 ( 0. 5 ) L .
k MULTIPLE CHOICE - SELECT THE EEST ANSWER l Which of'these operate on the principle cf a silver halide being altered by radiation? (a) Film dosimetry 4
.l (b) Self ruading pocket dosimeter (c) Condenser type pocket dosimeter (d) Thermoluminescent dosimeter AN6WERc
- a. Fi 2 m dusicatry (0.b)
FEFERENCE: Urot 10, Chapto X111, p a r; t e 15] OUESTION E.06 (0.5) MULTIPLE CHOICE - SELECT THE BEST ANSWER l Which of the f ollowing may be read at any time by holding it up to a light source?
-(a) Film dosemitry (b) Self reading pocket dosimeter (c) Condenser type pocket dosimeter (d) Thermoluminescent dosimeter ANSWER:
- b. Std t reading pot.ket dosimettr ( 0. U )
REFERENCE:
Unit 10, Chapte XII), page 101 i I i i 4 i l l L
,e .o OUESTION G.07 (0.5)
MULTIPLE CHOICE - SELECT THE BEST ANSWER Which of the following'is a measure of energy' deposited in a unit of dry air;at standard ternperature and pressure. { (a) . REM 4 (b) RAD (c) Roentgen (d) Curie (W5 W C M . (c) Roentgen
REFERENCE:
Unit 10, Chcpte+ )IIJ OUESTION G.08 (0,5) MULTIPLE CHOIC.E - SELECT THE BEST ANSWER Which of the following is a measure cf the rate of decay of'a radioactive material. (a) REM (b) RAD (c) Roentgen (d) Curie ANEWERS: l un com e .; ar=TREN;E. Unit 10, Uhq u XIIJ l
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.(a) " Cutie pie" (b) " Snoopy" (c) " Juno" (d)- "Radgun" ANSWERS:
(t) Juno ;
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REFERENCE:
Unit 10, Chapter XI13, p a g :r 147 i i l i 6 l
9 QUESTION G 11 (0.5) MULTIPLE CHOICE - SELECT THE BEST ANSWER
- Which of the f ollowing i.nstruments is used to detect neutron radiation?
{ (a) " Cutie pie" (b) " Snoopy" (c) " Juno" (d) "Radgun" ANwEqs-( i> > 8,c = up y REFERENX- CraF QUESTION G.12 (1.0) How long can you remain in an area with a gamma dose rate of 2.5 R/hr without exceeting the 10CFR20 qu-;rterl y whole bcdy li mi t? ryse-. Oc % $~ +f ']3 ) ; ilt j d 7 1,,'. l. ( I
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QUESTION G.13 (1.0) Refer to Figure G-3 which illustrates the pulse size verces applied voltage for typical gasfilleddetection'chjmbers. What is the name of the regions listed bel ed? (a) Region II (0.5) (b) Region III (0.5) AN5WERS: (a) Re;;i on II, Ioni z ati on ( 0. ')) (b) Region ~III,. Proportional (0.5)
REFERENCE:
Unit 9, Chapter 9. page 42 J 1 I 1 I h END OF CATEGORY G END OF EXAMINATION l 8}}