ML20236E374
| ML20236E374 | |
| Person / Time | |
|---|---|
| Site: | University of Illinois |
| Issue date: | 03/10/1989 |
| From: | Bjorgen J, Dave Hills, Jordan M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20236E361 | List: |
| References | |
| 50-151-OL-89-01, 50-151-OL-89-1, NUDOCS 8903240122 | |
| Download: ML20236E374 (102) | |
Text
{{#Wiki_filter:. . i e 4 i U.S. NUCLEAR REGULATORY COMMISSION ; 1 REGION III l l l Report No. 50-151/0L-89-01 Docket No. 50-151 License No. R-115 4 Licensee: University of Illinois 1035 S. Goodwin Avenue Urbana, IL 61801 , Facility Name: Advanced Triga' Reactor , Examination Administered At: Urbana, Illinois . Examination Conducted: February 21-23, 1989 l RIII Examiner: jo g 03)o/pf Date '
,A h 63//o/g9 Chief Examiner: . Hills 'l Date ' I k
Approved By: M. Jorda 03//o/gf Date Examination Summary Examination administered on February 21-23,1989 -(Report No. ' 50-151/0L-89-01)) -l Written and operating examinations were administered to three Reactor Operator candidates. Results: All persons passed all portions of the examinations.' s f .' 90$hoCgO p . v , Y l ___ .___ _._ __ _ m _
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REPORT DETAILS i i
- 1. Examiners i l
D. Hills, Chief Examiner , ! J. Bjorgen, RIII
- 2. Exit Meeting An exit meeting was conducted on February 23, 1989 between the examiners l and Mr. Craig Pohlod, Reactor Supervisor. 1 i
The following topics were discussed at the exit meeting: The examiners identified no generic concerns at the exit meeting. 4 A general discussion was held regarding the changes in the examination ! process and when the exam results would be available. ' l l 1 a i i , i
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5 0 0 Enclosure 2 WRITTEN EXAM COMMENTS
- AND RESOLUTION
*As discursed with the licensee on February 23, 1989.
1 Comment Question C.04: Part a: The question is confusing as to which power level is intended - administrative limit or automatic interlock. Part b: The question does not state which temperatures - moderate or fuel. Resolution:
,Part a: 'amment partially accepted. Answer key changed to accept 1MW interlock for 1/2 credit.
Part b: Comment accepted. Part b deleted. Comment Question E.07: The training material is incorrect. Primery flow rate is 1500 gpm and isolation valve closing time is 10 seconds. Resolution: Comment accepted. Answer key changed. Comment Question E.08: For clarification, there is only one ventilation valve, not two. Resolution: Comment. accepted. Answer key changed. Comment Question G.04: The question solicits information contrary to operator training philosophy based on the campus radiation manual. Recommend question be deleted. Resolution: 1 Comment accepted. Question deleted. I
' N U. S. NUCLEAR REGUL -- REACTOR OPERATOR \\I A G REGION 3 FACILITY: Univ._of_ Illinois ________ REACTOR TYPE: TEgI_;___;_______,_______ DATE ADMINISTERED: @2f93f31[i_______________ a INglBUCllgNg_lg_C@NQlg81El gfgf /d,' ff MM Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for.each question are indicated in parentheses after the Examination question. papers The passing will grade requires at least 70% in each category. be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY
__YB6UE_ _lgl@L ___@CQBE___ _y@6UE__ ______________C@IE@g6y_____________ i _ _1 _4 _. 0_ 0_ _ _ _ _1 3_ _. 7_ 9_ ___________ ________ A. PRINCIPLES OF REACTOR OPERATION l _13199__ _13 @2 ___________ ________ B. FEATURES OF FACILITY DESIGN a0 GENERAL OPERATING ________ _16:22 ___________ ________ C. CHARACTERISTICS
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_ _L4_ c_5_0_ _ _ _ _1_4_. 2_9 D. INSTRUMENTS AND CONTROLS _13199__ _13:32 ___________ ________ E. SAFETY AND EMERGENCY SYSTEMS l _16:gg__ _13:@2 ________ F. STANDARD AND EMERGENCY OPERATING PROCEDURES I +. 66 RADIATION CONTROL AND SAFETY _tfr?9__ _16:Z9 ___________ ________ G. _lfi I _ _'__________ FINAL GRADE ________% TOTALS l fg,6 All work done on this examination is my own. I have neither given nor received aid. 3 ___________________________________ Candidate's Signature MASIER COP _Y .
4 NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS
'During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application j and could result in more severe cenalties, j 6x, . l
- 2. Restroom trips are to be limi ced and only one candiddte;lat,a' time may leave. You must avoid all contacts wi th anyone outsidefthe.ex amination room to avoid even the appearance or possibility of cheating. ,
- T. I
- 3. Use black ink or dark pencil only to f acilitate legible reproductions, j 1
- 4. Print your name in the blank provided on the cover sheet of the j examination. )1
- 5. Fill in the date on the cover sheet of the examination (if necessary).
l l 6. Use only the paper provi ded for answers. i
- 7. Print your name in the upper right-hand corner of the first page of each ]
section of the answer sheet. j l
- 8. Consecutively number each answer sheet, write "End of Category __" as )
appropriate, start each category on a new page, write only on one side i 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.
l
- 10. Skip at least three lines between each answer.
- 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.
- 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 O' 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. .
I
- 17. You must sign the statement on the cover sheet that indicates that the l work is your own and you have not received or been given assistance in l completing the examination. This must be done after the examination has ;
been completed. L
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- 48. When you complete your ex ami n ati on , you shall
- a. Assemble your examination as follows:
i (1) Exam questions on top. , (2) Exam aids - figures, tables, etc. fl , p
. # 3ff !
(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 e, ;..ii nat i on questi ons.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answeri ng the questi ons.
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in thi s ' ar ea whil e the exami nation is still in progress, your license may be denied or revoked.
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v . . _ _ - _ . . Pcig3 4 A, PRINCIPLES OF' REACTOR
------------------------- --------_N DPERATIO
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.3 :l l 1 QUESTION A.01 (1.OOi !
l 4si BRIEFLY. DEFINE the terms Bact and Beff with regard to del: .hg p.
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neutrons. : r.gg . I . 1 ( l 4
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(***** CATEGORY A CONTINUED.ON NEXT PAGE *****) l
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T:: L. For the TRIGA reactor the core is designed to be optimselygmoderated or slightly undermoderated. W. ;g.M~
- a. EXPLAIN what is meant by thti above statement. (1.0)
- b. STATE TWO advantages of this design. (1.0) b lh k
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' 9___E51NCJE6gS_gE_Rggg}gg_gggg3IJgN g Pcgs 6-1 QUESTION A.03 (1.00)
Q: e ?;. . For light water reactors the average neutron l i f eti me i s about 100 x 10E-6 seconds as a result of low fuel enrichment. For graphite'or heavy ~ water moderated reactors this time: (CHOOSEthecorrect,{ response) ,
- a. DECREASES by a factor of 10 due to the higher neutron absorption cross section of the moderator, i
- b. INCREASES.by a factor of 10 due to the lower neutron absorption cross'section ofsthe moderator.
- c. REMAINS about THE SAME because the lifetime depends on resonance probability, NOT absorption cross section of the moderator, j I
- d. DECREASES'slightly due to the enhanced moderation characteristics- !
of the graphite reflector / moderator. l 1 l i e, , i l
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, . ' A.---_P_R__IN_C_IP_L_E_S__O_F__R_E_A_C_T_O_R_O_P_E_R_A_T_IO_N_
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. k QUESTION A.04 (1.50)
- a. DEFINE the' term reactor period. ( 0. 5 ) -
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3 EXPLAIN how and why-the reactor: period would change over. time i Jf a b. positive reactivity insertion is made:to a: critical reactor. ( 1. 0) 4 i ( t i t
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QUESTION A.05 (1.50)
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STATE the THREE poisons present.in the TRIGA' reactor dur[~lemtended- *
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- A, PRINCIPLES OF REACTOR OPERATION
- )
QUESTION A.06 (1.00) i N ( BRIEFLY EXPLAIN why the TRIGA reactor - may be impossible $e/M!ie to)Testart ( after a shutdown of six to ten hours f ollowing extended'itilgh power ' operation. jv"5;ar f: y.c l l l l , i I i l' 1 1 T l
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I QUESTION A.07 (2.00)
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- o. DEFINE the term." Shutdown margin". (1.0) +j, 3 C d.,.
! 'b. STATE the TWO reasons why the TRIGA reactor shutdown margin is ! determined on Monday mornings at 15 watts power.-(1.0) P H' l 1 1 1
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QUESTION A.08 (2.00) ; 3: x . . BRIEFLY EXPLAIN how'the reactivity of to change if the central thimble were loaded with: theTRIGAreactcy.[/Dg4h1[beexpe ft
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- a. A cadmium cylinder with a length of 15 inches. (1.0)+ ; $=b
-b.-An empty po)yethylene sample container. (1.0) l
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(***** CATEGORY A CONTINUED ON NEXT PAGE 88***)
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QUESTION A.09 (1.00)
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EXPLAIN WHY the experimental chambers, other than the central thimble, ~ have.little effect on the reactivi ty worth of the TRIGA~ reactor. 4
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Pegs 13 bl__fBJNg]Ebgg_QE_Bg69196,9fg83IJgN , l l 1
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QUESTION A.10 (1.00) J EXPLAIN HOW the reactor operator knows when the reacton has' achieved criticality using control rods, reactor period, an d p ower'.). 1 j
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(***** END OF CATEGORY A *****) h 1
v . . . _ _ _ _ _ _ _ _ _ _ _ _ peg ,, 14
, B, FEATURES OF FACILITY DESIGN 4 *,77*.
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QUESTION. B.01 -(1.50) ! Brieflyidescribe the content and construction-of the TRIGA. reactor 7 fuel elements. U dk ., b 7.QN ,'T ., m- rg. }
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# 4 OUESTION' B.O2 (2.00) !
l Complete the following statements: , y+
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17
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,. ps The TRIGA reactor core has a ____ (1)____ shape. During~not; mal operation the B thru F locations-co.itain _____ ( 2) ____ with the exceptions of D-7 and D-16 which contain the ____(3) ____ Transient Rod and the (4) _____ Transient Rod, r espect i vel y. (0.5 pts each)
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' B; FEATURES OF FACILITY DESIGN Pega 17 3
r 1 A QUESTION B.03 (1.50) si# :. _ , + . . . . <,
- a. STATE TWO purposes of the graphite reflector that surrounds the-core of the TRIGA reactor. (1.0) ~%.
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- b. Lead was added'to the majority of the outer 2 inches of the reflector area. STATE the reason for the addition of this lead shielding. (0.5) l l
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****) I 1 1
Pcgs 18
, ~ B _. _ _F_ _E_A_T U _R_E_S_ _O_F _ F_A_C_I L_I _T _Y _ _D_E_S.I.
, G_N a) l QUESTION B.04 (2.00) l
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l' In the space below SKETCH a flow diagram of the Reactor;C .' ant System primary l oop. Show all valves and identify major componen . !tThi s i s a reproduction of the diagram provided in the student handoutiCmateri , ;pp 4 al ) . +
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- 8. _EE@IUREg_gE,[@ClLIIL gE@lgN Pcga 19 i
QUESTION B.05 (2.06) .
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Regarding the Puri'ication and Auxiliary Cooling Systemt[1, > ig ty it.olate the
- a. STATE the reason why a manual val ve must be closed to._O;hlve. (1.0) flow-of secondary water prior to closing the solenoid -
4
- b. STATE the reason why.the inlet valve to the demineralized is closed when the primary pump-is started using the re-set push 6utton above -
the pump control box. (1.0) .j i l W oh (***** CATEGORV- B CONTINUED ON NEXT PAGE *****) 4
, *B.
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FEATURES OF FACILITY DESIGN Pc9a 20 1 I J ! 1 i QUESTION B.06 (2.00) ; I ng g: , I Regarding the Forced Convective Cooling-System: f;Q'g!(, - j G Q(+$ ' Describe how the primary flow is controlled (vari ed ) .j..
- a. f.0.5) o P :, .
- b. Describe (1) the type of instrument installed in the prima'ry-flow .;
piping to measure primary flow and (2) the two locations of flow" ; meters that give flow indication.-(1.5). ! i i 1 i P I
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Page 21 , B _. _ _ F_ E_ A T U_ R_ E_ S _' O_ F_ _ F A_ C_ _I L_ _I T_ Y _ D E_ S _I G_ N_ i l
'! i QUESTION B.07 (1.50) > i
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' STATE or DESCRIBE-the purpose of the f ollowing componentsp' n' the 4 TRIGA reactor Building Exhaust-System: , ; .ts --
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- a. The prefilters. (0,5) b...The HEPA fil'ters. (0.5)
- c. The charcoal filters. (0.5)
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. _B_.___F.E_A_TU_R_E_S__O_F__F_A___L__________ITY
__ DESIGN 4 l QUESTION B.08 (1.00) STATE the purpose of the RETENTION TANK. [Jfeg-< l l l
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' Page 23 , B:___EE91UBE@_gE_E@ghlly_QE@lgN 4
Ib OUESTION B.09 (1.00) STATE (a) the purpose of the Boral curtain in the large! thIgrm 1 column. (0.5) and (b) describe how it is moved in and out of positfon.(0.5) 4:, l
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4 Pcg:2 24 C, GENERAL
----------- OPERATING CHARACTERISTICS
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- 9t__9ENE6@L_QEE6@llNQ,gd@@@gIE61@llg@ Pcg2 25 QUESTION C.01 (2.00)
The VOID coefficient of reactivity ' varies in the TRIGA' reactor . depending on the inserted location of the voi d contai ner.'- EXPLAIN l the EFFECT on CORE reactivity.and the REASON for the~following situations:
- a. A void container inserted near the center of the core. (1.0)
- b. A void container inserted in one of the outer two fuel locations.(1.0) 1 l
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Page 26 - 9:__9gN[ggh,gggg3))Ng_ggggggIgg}gIJgg_ QUESTION C.02 (2.00) 4 The negative fuel temperature coefficient for_the TRIGAJdeastor consists of FOUR significant parts: a}jg ,t[
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- 1. Cell effect
- 2. Control rod absorbtion
- 3. Thermal leakage
- 4. Doppler Match the appropriate percentage (a) thru (d) to items 1. thru 4. above.
- a. 15% b. 20% c. 10% d. 55% (Four @ O.5 pts each) l
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- 92.__9ENgB99,98gg$))Gg_gb36991g8]pTI,93 Page 27 QUESTION C.03 (1.00)
BRIEFLY EXPLAIN why the moderator temperature coef fi cient;is di f f icul t to measure in the TRIGA reactor. (***** CATEGORY C CONTINUED ON NEXT PAGE *****)
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Pcgo 28 ! . '9:. _9ENgg% ,gggggIJNg_g!ggggIgg}gI]gg QUESTION C.04 agynt,. - For the TRIGA reactor: ;
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- a. STATE the nominal power level above which f orced convective cooling is normally required. (0. 5 ) '.'j, * $^
- b. EXPLAIN H M CREASE, DECREASE MAIN THE SAME) and WHY the average and indicated temperat -.-mne when changing from natural to. forced convective cooli 1.5) J
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(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
,, ' 9 __9ENgggL_Q[ggg]JNg_gd@8991gB}@lJgg Pego 29 QUESTION C.05 (2.00) _m. .. MATCH the appropriate TRIGA reactor mode switch positiont (J )" thru (4) with the statements (a) thru (e). Mode switch positions,may be used more than once or not at all.* 17 MODE SWITCH POSITION (1) AUTOMATIC (2) STEADY STATE i (3) SQUARE WAVE (4) PULSE
- a. Used for initial startup each day below 15 watts. (0.4)
- b. The Fast Transient Rod must be UP to avoid a Limiting Condition in Technical Specifications. (0.4)
- c. Used to prevent excessive movement-of the Regulating rod while irradiating samples in the Lazy Susan. (0.4)
- d. This mode prevents manual control of the Regulating rod and includes a period scram safety feature. (0.4)
- e. Allows the use of compressed air for rod movement after a special peak power calibration check. (0.4) i i
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Page 30.
.- '9 __9ENE6@g_gPEg@llNG_gd@@@glEg1S11g5-F QUESTION C .' 06 - (1.50)
Complete the following statement: ry g $6f
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In_ general, the' manual rods of the TRIGA reactor.have ;__;:fa)^____ worth than the.Other rods because_they have a_ smaller _____ (b)_jQ iand hence, 1 more _____(c) _____ near the f uel . '(Three 9 0.5 pts each) 't
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Pcga 31 . 'g.__gENg@@(_g[gg@IlNg_gd@B@gIE61@Ilgg QUESTION C.07 (2.00) 1 With the TRIGA reactor operating steady state at 250 kw on natural circulation STATE:
- a. The expected observed power change when the f orced cooling system is started. (1.0)
- b. The reason for the observed power change. (1.0) ]
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' 9___9E9Eggg_gPE6@Ily@_gd@@@CIE@l@Ilg@ Pegg 32 QUESTION C.08 (2.00)
, Y Given the attached control rod motor control circuit: , .f'
? . ', s. l STATE the purpose of the bias resistor R901 in the "DOWN" ci rcui t . ( 1. 0) a.
- b. STATE the purpose of the 1MF capacitor C901 in the "UP"'~ circuit.li.0) 1 i
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(***** END OF CATEGORY C *****)
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Pago 34
, 'D. INSTRUMENTS AND CONTROLS.
QUESTION D.01 (1.00) 8 (/8(O STATE the type aD' tion of i n st al l ed d,ip IhNbentation . available to the reactor ~thatfovides early indlCatton of an ; approaching tornado.
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Page 35
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QUESTION D.02 (1.50) 4 i Regarding the count-rate channel , '[#jg
- a. STATE the purpose and function of the source interlock (0.5) 3 l
- b. STATE the automatic action that occurs (0.5) and the initiating < limit (0.5) that. protects the count rate channel fission counter from ,
excessive burnout at high power levels. l 1
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l
- 9:.__IN@lBUDENI@,99p,CgNIgg(@ Page 36 j
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QUESTION D.03 (1.50) 1
, ', e ' ,
I Describe how power 'is controlled in the AUTOMATIC mode. .I DE the rod used, the sequence of_ signals that cause both UP and rod motion, and any limits i n vol ved in these operations. .
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-4 !
Page 37 5- *Pr__IN@IBUDENIQ_ANQ_QQNIBQL@
' QUESTION D.04 (2.00) l ke y Regarding the Log-N channel: @ *g
^
x: a.. STATE the type of detector used. (O.B) j
')? '
+
t b. STATE the low' power indication limit of this channel . -(0.5) j i
- c. STATE the upper power indication limit of'this channel. (0.5)
- d. STATE the other panel indication obtained from a differentiation of the voltage signal from'the Log-N amplifier. ( 0. 5)' ,
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(***** CATEGORY D CONTINUED ON NEXT PAGE *****)
. i -i 2:.__IN@l@UDENI@_@NQ_CQNIggh@ Page 7,8 s
i QUESTION D.05. (1.00) l l STATE the two interlocks (other than mode switch position)g!4 initiation of the SQUARE-WAVE mode of operation. ' %2'" hat^ prevent
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(***** CATEGORY D CONTINUED ON NEXT PAGE *****)
v . - - . . - . _ . . . . . 9 D INSTRUMENTS AND CONTROLS Pcga 39 5 __.__________________________ e i QUESTION D.06 (1.00) STATE the TYPE and LOCATION of instruments used to monitok-the fuel temperature in the TRIGA reactor. il l l l
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__ . _ , _ . . _ _ . _ _ _ ~ . _ _ . . . _ _ _ . 4 Pego 40 i
- Er. 1DE199dEdlE_OUE_ggyIggLS QUESTION D.07 (2.00) 7egarding the Transient rods: , , .
e ETATE which rod has variable travel length. (0.5) b STATE the energy source that moves the transient rods. (0.5)
- c. STATE the type of device attached to the rods that provides position indication of the transient rods. (0.5)
- d. STATE the purpose of the low friction seal s in the Fast Transient Rod (0.5) l l
i 1 l l W (***** CATEGORY D CONTINUED ON NEXT PAGE *****) ! i
1
;s.
l Pcgs'41 1 ,. _D_.___N______________________I_STRUMENTS AND CONTROLS ~ ! 1 1 QUESTION D.08 (1.50) w;; ,. O,,, .; EXPLAIN the electro-mechanical actions that occur to sagas (the' rack-and- j pinion control rod drives. Identify the internal c ompoq;:-M .':af
' ected and f
the force that provides rod motion. W9 ; FMe l
-; A - -
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(***** CATEGORY D CONTINUED ON NEXT PAGE *****) i 1
4 4 Pcgo 42
- ' 9:.__IN@l6UtjgNI@,@NQ_CgNI6Q6@
QUESTION D.09 (2.00) STATE the FOUR locaticns WHERE the temperature sensors'are71ocated in the , heat removal system. ,' l s' I I l i c l i j 3 I i
?
(***** CATEGORY D CONTINUED ON NEXT PAGE *****) i
4 Paga 43
. _D_._ _ _I _N_S_T
_ R_U_M_EN_ _T _S_ AN_ _D_ _C ON_T _R_OL S QUESTION D.10 (1.00) l 4M STATE the reason for the h second time required for the. heat removal I system isolation ealves to close. l l l l l r i (***** END OF CATEGORY D *****)
E SAFETY AND EMERGENCY SYSTEMS Pego 44 l m
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Pcga 45 . ' E:.__!MEIY_6Np_gdgRggNCY_EYEIEU@ QUESTION E.01 (1.00) The Safety Analysis Report describes the Control Rod system'to be
" Fail Safe" upon a loss of electrical power or air pressure. Describe how the rods respond to a loss of air or electrical powerito make them -
4
" Fail Safe". ,
l l l l l 1 kA ._'I (***** CATEGORY E CONTINUED ON NEXT PAGE *** * * ) k
....-----...2..+-.-
E:.__!9EEIY_8Np,[dg@@gNCy_pypIED!' Paga 46 4 QUESTION E.02 (1.00)- a S Complete the following. statement: J.3 ' l Ndgy :, The Emergency Core Spray System shall be operated at least'_____(a)-- _____ to verify that it is capable of suppl yi ng a mi ni mum .of _____ (b ) _____ gallons per minute on the core. (Two items @ 0.5 pts each). i l 1 l I 1 4 l
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(***** CATEGORY E CONTINUED ON NEXT PAGE *****)
l
'E. SAFETY AND EME peg,47
. -----------------_R_G_EN_C_Y_S_YS_T_E_M_S _ _ _ _
. I QUESTION E.03 (3.00)
STATE SIX conditions (signals) that will cause an AUTOMATIC:. scram of the g TRIGA reactor. (Setpoints NOT required). . l I l 1 i j J l I l l l l l l l f (***** CATEGORY E CONTINUED ON NEXT PAGE *****)
E.,_gggly_8Np_ggggggNgy_gy@Igdp , P,c g m . 48 - DUESTION E.04 (1.00) Correct operation of the primary flow system is protec )hhhflow-switch. Should the flow switch fail STATE the two backup?a,natomatic trips that protect the system. [ , as +. +,..fh, i
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Pcge 49-
. 'E___29EEIY_8Np_gdggggNCy_@f!!gD!
QUESTION E.05 (1.50)
,r w Upon a loss of forced cooling the TRIGA reactor i s al sol.prptocted by an Engineering Safeguard feature that assures adequatec care cooling.
Identif y this design f eature and explain how core cooling}!!s. accomplished. 1 1 i l l l i
.,.3 s".*(
l i (***** CATEGORY E CONTINUED ON NEXT PAGE *****)
~
a E.__@@((Ty_@Np_gdg@pgNCY_E1EIEDE Pcga 50 QUESTION E.06 (3.00)
$L'%.~' . >
- o. SKETCH a flow diagram of the Emergency Core Spray Coo 11jng' ,,,y system.(2.0)
- b. STATE the component that actuates and the flow rate obt'ained from the-ECCS system when the emergency low water level signal ' fs received. (0.5)
- c. Should the automatic actions fail to occur or the demineralized becomes plugged, describe how the reactor operator can manually operate the system. (0.5) l l
1 4 d (***** CATEGORY E CONTINUED ON NEXT PAGE *****)
E. SAFETY AND EMERGENCY SYSTEMS Pcgs 51. i i QUESTION E.07 (1.50) M i y;;, Should a primary cooling l oop rup ture occur wi th the prima,ry pump ; nEYs < ~ . continuing to run at 99eCr~gpm: ; ~.- ,
- a. STATE the expected level drop in the~ Reactor Tank f orithis f ailure. (.75) )
- b. STATE the REASON for the level drop in part a. above. (0.75) 4 i
+
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(***** CATEGORY E CONTINUED ON NEXT PAGE *****)
Pogo 52
+ E1 _!8EEIX_809._EDE59509X_9X9IED9 i
i o'
\
q t QUESTION E.08 (1.50) ] al' 1 Describe how the Reactor Bui1 ding Venti 1ations system wi11$4 respond ] to'a fuel cladding f ail ure ' that rel eases 0. 2 curies of lioethe. .-
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- i E:.__99EEIY_eU9_EDEB9ES9Y_!!!IEd! Pega 53 ry QUESTION. E.09 (1~00)
STATE the basic-design feature of the Primary / Secondary (Ccioling Systems that prevent a release of radioactivity to the environmentfif a tube should rupture in the heat texchanger. ^*E
-1:: )
l 1 1 i l f 1 e (***** END OF CATEGORY E *****)
m , . . _ _ . - . . . . _ _ _ . . . . . _ . _ . _ _ - _ _ _ _ . _ . _ _ . _ _ _ _ _ _ . ~ , . _ _ _ , . ._ . . _ _ _ _ . Pug 3 54 . F_ _. _ _ S_ T_ AN_ D AR_ D _ A_ N_ D_ E_ _ __ _ _ __ , _ _ _ ___ MER_S_ E N_C Y _O___P E_ R _AT _I N_ G_P_ R_ OCE_DU_ RE_ S p # s-
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* * - EIOUE689_669_EtigR@gNCY_QPE861169_PR9CEQURES ----
Pcga 55-QUESTION F.01 (1.00)
%m t.
Standing Order No. 2 allows the reactor operator to rem;the period circuit f rom operation at his or her discretion. r why this is authorized by the technical evaluation. ' j.j State:TW[j'easons d P l 4 l Ag , I' 4
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(***** CATEGORY F CONTINUED ON NEXT PAGE *****)
_ - _ . . . _._._._..___x- _ ;. - - - q l
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,i Pege 56'
. F_ _. _ _ S_ T A_ N_ D A_ R_ D _ A_ N D _ E_M_ ER_ G_ E_N_ C Y_ _O_P_E_ R_ AT_ _I N_G_ _ P_R_OC_ E_ DUR_) QUESTION F.02 (1.50) Ag n The Senior Reactor Operator has requested that you put?ths/ reactor in l the " Reactor Secured" condition. State the THREE conditions'that must be satisfied as described in the Rules and Regulations f Operation. l i l I i s 'l ' l s ll :)% ,[?,__ g.. (***** CATEGORY F CONTINUED ON NEXT PAGE *****)
Pcge'57
- . F_ _. __S_ T A_ N_ D A_R_ D_ _ A_ N__D_E_M_E_R_G_E_N_ C_Y__O_P_ E_R_ A_T _I N_G__P_R_OCE l l l
QUESTION F.03 (1.50)
;y( ..
The Rules and Regulations, for Operation of the TRIGA react;or require the operator to shutdown the reactor if any one of five conditions occur. STATE THREE of these conditions. 8 E*C p l 4 4 i l i i l l
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. i
- E*- ElbdEbOE ON9_{DgRGgNCY_ OPERATING' PROCEDURES Pago 58 I
QUESTION F.04 (2.00)
;,gg ,
In the event of a major radioactive spill, high offgasf'eck{yit'y, or fuel damage the Radiation Emergency Plan identifies SIX initf41% actions that are the-responsibility of the licensed operator. STATE FDURTof these l actions. Assume the reactor is initially operating. #4 i l h i i l 1
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E __!I9Np33p_3Np_Ed[69ENgL QfgB3))Ng_f3ppgpgREE Pego 59
)
. QUESTION F.05 (2.00)
~
For each of the following items, STATE the required operator action to be taken by the DAILY CHECKLIST to verify proper statuf of the equipment: 8 1
- a. The reactor beam ports. (0.5)
- b. The reactor tank flapper valve. (0.5)
- c. Rod position and associ ated position indication. (0.5) f
- d. Linear recorder scram. (0.5) !
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- - - -----..___a-._____ . _ _ _ _ _ _ _
' E:.__9IONp33p,@Np_gDg695Ngy_gEEBSIJNQ_EBQQgggggg Pcg3-60 T
+
i 1 l QUESTION F.06 (1.50) l kp-qpy The Reactor Startup and Operation procedure requires three garameters to be recorded in intervals no greater than 30 minutesffo/icontinuous operations at a steady state power level withAuxiliaryok'NOcooling. Identify these THREE parameters. ?~ { 1 l i
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- E1__@]@yp@$9,@yp_gDEBQgygy_QEg8@l}$@_E89CgpURE@ Pago 61
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- DUESTION F.07 (1.50)
When shutting down the reactor for the'dav,' DESCRIBE tho' required-status of the. AUXILIARY COOLING System per the Reactor Shutdown procedure. i l I i
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s ! Pego 62' c- F. STANDARD AND EMERGENCY OPERATING PROCEDURES QUESTION .F.08 (1.50)
- -9 The procedure for Potential Malfunctions of Systems or Components provides.THREE actions-to be taken by the operator in the(event of an abnormal reactivity change. STATE these three actions.
4 h 1 f
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1
- l fr._ E190E989.999_gdg6EgNCy_OPg6@ LING PROCEDURES Pcgs 63 l~
QUESTION F.09 (2.00) 3 The procedure for Installation-and Removal of Items in tho' Core Region of the Reactor, General Guidelines requires the reactor operator t ci ; directly supervise all core changes and lists FOUR required responsibilities of the operator during core changes. STATE these FOUR responsibilities. l l 1 i I l l l T l t (***** END OF CATEGORY .F *****)
E2-~89919Il9N_C9U189k @NE SAFETY Pc90 64 I
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. 1
, g, G_. __- R_A_D_I A_T_I _ _ _ _ _ON__C_O_N_TR_OL_' _A_N_D_S_A_F_E_TY Pego 65 a I
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') .
-QUESTION G.01 (3.00) i
. . x - - .; .
i STATE SIX'of your responsibilities as an' individual r adi ati on _ . wor k er (us er ) ,- ' as stated in the. Radiation Safety Manual, Appendix 11.4 $; W lf 1 1 i 1 1 l l
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RADIATION CONTROL AND SAFETY Pcgo 66
> _G-------------------------------
1
'\
l QUESTION G.02 (2.00) 1Ap%id For each of the following radiation hazards (a) throughM 2 assign the appropriate order of importance'(1) through (4). d;; Igg,o a. b. External exposure to neutrons. (0.5) External exposure to Beta radiation. (0.5)
@']$Mih(r' g
- c. Ingesting radioactive materials- into the body. (0.5)
- d. External exposure to gamma radiation. (0.5)
.)
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h__B9919I19N_ggNJ$gh_gNp_SSEEJ,Y Page 67 L- -- l QUESTION G.03 (1.00) While working in radiation areas on campus, STATE the normal location that your dosimetry should be worn. 2
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Pcgs 68
- '9 __B8919I!9N,ggNIBpk gNp_pM EIY QUESTION G.04 ( 1. 00)- j d/ dI .J
. f;.- v4;4: 1 Using the guidance of the_ Radiation Safety Manual during f radiation l emergency with the reactor o
~
and people up in the~ reactor tank area, which one of the following actio e takeniflest: - A.
- a. Scram the reactor
- b. Order evacuation
- c. Shut the isol n val ves l
_L
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a.
' Pcgo.69
,.. G__.__R_A_D_IAT_IO_N_CO_N_TR_O_L__AN_D_'_S_A_F_E_T_Y. i i QUESTION G.05 (1.50) STATE the NRC quarterly exposure ~ limits of 10CFR 20 for's . .cy. ch of the following: c , m,z y
- a. Whol e body - (0.5)
$;i
- b. Hands, forearms, feet and ankles (0.5) l
- c. Skin of the whole body (0.5)
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~ ~ . . . - . . . - - _ , .. .____,.____._,_.,_,,m_.. _
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' Pego 70
, G_ _. _ _ R_ A__D_I
_ __ __ A_ T_I ON_CO_N_TR__O_L_ __ AN_D_ _S_A_F_E_T_Y J l
. d QUESTION G.06 (1.00) y!R , _
The NRC quarterly whole body exposure limits may be ex ,, "-d provided . l the accumulated dose shall not exceed 5 times N-18 rem. t'does the N stand for? $U 2 :24 d ! r$ l t 1 2 9 i
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9 9 - 6691eI19N.C9 NIB 9L_eN9_seggzy .Pago 71 i QUESTION G.07 (1.00) l 4 STATE the NRC quarterly whole body exposure limit for high-school students ages 15 and 16 vi si ting the TRIGA f acili ty. f d,.) - 't i I i > I l i i l l l l l 7
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(***** CATEGORY G CONTINUED ON NEXT PAGE *****) 1,
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s G_. __RA__D.I AT _ _ - -- I.O.N
--- . CONT.R.O.L. AND SAFETY OUESTION G.08 (1.50)
Complete the following statements y%j'p{ y
% DkW According to 10CFR 20 a " radiation area" is defined asian { area where the whole body exposure may exceed ____(a) _____ mrem in-__bE(b) ____ hour ( s ) ,
p whereas a "high radiation area" i s def ined as an area where ' the whol e-body exposure may exceed ____(c) _____ mrem in the same length of time. l l i l 1h i l
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4 1 9 __68919I19N,ggNIQg6_@Ng_S@[Ely Pego 73
+-
QUESTION G.09 (3.00)
,q. #
The area radiation monitors, the exhaust air moni tors, ;thgh continuous ! air particulate monitors, and the water monitor continuous ! constitute monitoring for radiation in the TRIGA laboratory. For each: l device STATE one location of the monitor (s), the type (s) of radiation detected, and the type of alarms received. i l l l I l i l l i i i l 1 l W l i 1 l l I + < }';;j (***** END OF CATEGORY G *****)
. (********** END OF EXAMINATION **********) q l
l _ _.--_-____-__--.._-.__.---____---._.________-.a
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" ' j SQUATION SHEET
. f = un v = s/t Bet Work (out) -
2 Cycle effi w = as e = v,t + hat E = aC a = (vg - v,)/t gMj ?", 2 A=2 EE = hev ,g , , + g j j yE = ash a = 4/t 1=la2/t{iej 093/tg W = v&P- . . . l
%(aff) = (t,,)(q)
- AE = 931Am -
(tg+t}b
- Es k " k ATp , ,
I = g ,.
,6= nut z = 2,. =
~
Pur = U g' 5 ~ , g = 1 ,10 "
. 8M(tl TTL = 1.3/u y=pl.to,= , t/T - -
m . .. ,us .
*SUR = 26.06/T '
s m = s/(1 - E ,,,) T = 1.44 Dr 2,=s/d1-refh) A*tt*h s n = 26 g,, 7=11*/o)+ [(i J,)/x ,] I I ~Ieff 1 " "2II Inff}'2 T = t*/ (, . f; M = 1/(1 - K,gg) = C1 3/cEn T = G - o)/1egg o M = (1 - E,gg)0 II ~ Inff}1 i 8" eff ~1)IIeff " #efflEaff SDM = (1 - E )/E p= [1*/Trygg.] + [I/(1 + 1,ggt )] g* = 1 x 10 -5 seconds
~
F = E(Y/(3 x 1010) 1,ggle 0.1 seconds E = Nr -
. Idgi=1d22 UATER PARAMETERS Idg =Idl 2
1 gal. = 8.345 1ha R/hr = (0.5 CE)/d g,,,,,,) 2 1/hr = 6 m/d gg,,t) 1 sal. = 3.78 liters 1 ft3 = 7.48 gal. MISCELIAICOUS CONVERSIONS . 3 Density = 62.4 lbe/ft 1 Curia =,3.7 a 10,I'dys Density = 1 se/cm 3 1kg=1.31 h m Nest of vaporization = 970 reu/lba 1by=2.54N103 BTU /hr 0 Heat of fusien = 144 Stu/lba 1 W = 3.41 x 10 stu/hr 1 Atm = 14.7 Psi = 29.9 in. I's. 1 St.u = 778 f t-lbf 1 ft. H 2O = 0.4333 lbf/in !' inch = 2.54 en
*F = 9/5'c + 32
. *3
- . [9 T - 32)
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Pcge 74
, ' e __E51NgJg6gS,gg,ggggIgg,ggggg}}gN ANSWER A.01 (1.00)
Bact is the fraction of delayed neutrons that resul ts frosjfission. (0.5) Beff is the fraction of delayed neutrons that reaches ther, mal energy (and hence cause a fission event). (0.5) g-l REFERENCE NE 390R notes page 2 ANSWER A.02 (2.00)
- a. Keff is maximized or almost maximized for a given moderator to fuel ratio. (1.0)
- 6. (1) Requires a minimum amount of fuel for a critical system. (0.5)
(2) Maximizes the flux 4for a given power level which is desirable for.a research reactor. (0.5) REFERENCE NE 390R notes pg 7 ANSWER A.03 (1.00) , I 1 l b.
' REFERENCE NE 390R notes page 4 l l
l ANSWER A.04 (1.50)
- a. The time it takes for reactor power to change by a factor of e. (0.5)
- b. Initially a transient period (prompt jump) occurs followed by a stable period made up essentially by the delayed neutron precursors. (1.0)
(Alternate wording accepted) REFERENCE NE 390R notes pg 11
} '
(***** CATEGORY A CONTINUED ON NEXT PAGE *****) I
r-
. )
A. PRINCIPLES-OF REACTOR OPERATION Pcgs 75 i 1 ANSWER A.05 (1.50) ] 4
- 1) Control rods or boron ) jg. 3,[ j
- 2) xenon e i
- 3) samarium (three @ O.5 pts each) 15b b;., qp'
, Y REFERENCE '
i NE 390R notes pg 13 ANSWER A.06 (1.00) The buildup of xenon provides sufficient negative reactivity to preclude reactor startup. (1.0) REFERENCE , NE 390R notes pg 14 and 15 l 1 ANSWER A.07 (2.00)
- a. The amount of reactivity that must be removed to obtain a critical condition OR the amount of negative reactivity present in a cold xenon-free reactor with:the highest worth rod fully withdrawn. (1.0)
- 6. 1) The reactor is xenon free on Mondays. (0.5)
- 2) At 15 watts there is no f uel temperature coefficient. (0.5) l REFERENCE ;
NE 390R notes page 16 ANSWER A.08 (2.00)
- a. This would add negative reactivity (1.0)
- b. This would add positive reactivity (due to enhanced moderation). (1.0)
REFERENCE t NE 390R notes pg 17
,3ggG x ;s- ;
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
9:._ _ E51NgJ ghgg,,gg_ ggggIgg_gggggIJgN Pcgs 76 ) , i I r ANSWER. A.09 (1.00) i, j i YM , rg~' The other chambers arm located outside the reactor core,m,2c region. r ; Y
* &, Lz .o 1
REFERENCE c ; ;N g ., NE 390R notes pg 17 ANSWER 4.10 (1.00) Reactor power is increasing with a positive period without additional rod movement. (Alternate wording accepted). (1.0)
. REFERENCE NE 390R notes pg B-11 f
1 1 Y pk , E (***** END OF CATEGORY A *****)
- x. . . _ . . ._. .
~a___FggIURgg_gE_E@CJLIIy_DggigN Pcga 77
' ANSWER B.01 (1.50)
A mixture of-U-235 uranium (l ess than. 20% enri chment) (O'.5)j$nd hydri ded zirconium (0.5) surrounded by a 304 stainless steel cladding.(0.5) (Alternate wording accepted) i REFERENCE Facility Design notes page 1-35 ANSWER B.02 (2.00) (1) hexagonal (2) fuel (3) Adjustable (4) Fast (4 @ O.5 pts each) REFERENCE Facility Design notes page 1-35 and 1-36 ANSWER B.03 (1.50)
- a. 1) Requires less fuel for reactor operation. (0.5)
- 2) The thermal flux is slightly enhanced in the rotary specimen assembly (or the Lazy Susan). (0.5)
- b. As a precaution against gamma heating of the surrounding concrete.(0.5)
REFERENCE Facility Design notes page 1-36 ANSWER B.04 (2.00) Figure 19, pg 1-109 of the System Design notes.(Copy attached.to the Master copy and Facility review copy). REFERENCE System Design notes Figure 19, page 1-109. 4 d i ; (***** CATEGORY B CONTINUED ON NEXT PAGE *****) -f
. _ . _ . . _ _ _ _ _ .._ _ _ _ . . _ _ _ _ ______._____.__i
E __FE@ LYRES _QE_[gg1(lly_ DESIGN Pegu 78 v. l l s l ANSWER B.05 (2.00) l eji , o 4 ..
- a. To prevent severe water hammer in the piping when fl,owgisjouddenl y stopped. (1.O) ;~iQiylf b..This avoids a sudden surge of water to the demineralized that may force some of the resin into the filters. (1.0) 4.g REFERENCE System Design notes pg 1-38 !
ANSWER B.06 (2.00)
- a. A throtcle valve (located near the pump). (0.5) f
- b. (1) A differential pressure (dp) transmitter (0.5) 1 (2) In the Control Room (0.5) and the Mechanical Equipment Room.(0.5)
REFERENCE System Design notes pg 1-39 ANSWER B.07 (1.50)
- a. The prefilter collects dust and extends the life time of the '
j (more expensive) absolute (HEPA) filters. (0.5)
- b. HEPA filters are designed to remove 99+% of small particles.(0.5)
- c. The charcoal filters are designed to remove iodine l
under accident conditions. (0.5) q I REFERENCE 1 i System Design notes page 1-41 and 1-42 ANSWER B.08 (1.00) l To collect all water on the lower level for sampling for radioactivity l (or contamination) prior to discharging to the City sewer. REFERENCE
^
System Design nsotes page 1-42 4:M/gp s ;p ' (***** CATEGORY B CONI 1NUED ON NEXT PAGE *****)
e SYMBOLS h PRESSURE
@ TEMPERATURE
( lPN ACTl PNEUMATIC ACTUATOR h FLOW SWITCH. F-- ----l PN ACT F------] ;; . I l NUCLEAR REACTOR l l FS twF0 d-T T '
?
PRIMARY PRIMARY ISOLATION ISOLATlON VALVE VALVE e O
'T BULK y 3 X n p TEMP. m PRO 8E 4 O
5 EMERGENCY ,_ ._ $ f COOLANT m SYSTEM E -- (DELAY ~ NK 3 OR 8 GPM' $
- 60*F W
( DELAY CIT Y TANK WATER $ l w l
, z - l l
h i
.]
k k a
..x ,
N PR RY W l P THROTTLE VALVE
!l S T R A IN E R OP PRIMARY "- 64 i '
PUMP
- FLOW DIAGRAM .
OF THE REACTOR COOLANT 5'Y5 TEM i ( (PRIMARY LOOP) Fry a M h? .
. .& 1
, _-- _ _ .._. _ _~. - - . .
q pC O 79 B. FEATURES OF FACILITY
------------------------------- DESIGN ANSWER B . 0 9.- (1.00)
_ . . . .2"
- a. The Boral curtain allows work in the. thermal c ol umn, . area; wi t h the reactor in operation (provides shielding) . (0.5) .j .e _- ~t! " ,
- b. It is moved (up or down) by. cables. (0.5) $[gf, ~ -
REFERENCE System Design notes page 1-44 l d 1 l l
$ M-g-
(***** END OF CATEGORY B *****)
Pcgo 80-
- '9___9ENgggL_ggggg]JNg,ggggggIggig))gg ANSWER C.01 (2.00)
- c. Causes positi ve reactivity (0.5) since' the space normally . filled with water is replaced with a void for a net loss of moderat'i on .
(Alternate wording accepted). (0.5) { 3
- b. In the outer area the void addition affects the neutron' leakage and this change is greater than the change i n moderati on (0. 5) for a loss of core reacti vi ty. (0.5) (Alternate wording accepted).
REFERENCE Operating Characteristics page 1-46 l \ l i ANSWER C.02 (2.00)
- 1. d
- 2. c
- 3. b
- 4. a (Four 9 0.5 pts each)
REFERENCE Operating Characteristics page 1-45 l ANSWER C.03 (1.00) Because any change in the moderator temperature also affects fuel temperature. REFERENCE Operating Characteristics page 1-46 ANSWER C.04 (2.00) N
- a. 240 kw (+ or - 10kw) (0.5) ( WILL UCf# /N #UN M U
- b. The average te rature remains the same (0.5) due to the small net heat input change (.25). Th 'ndicated temperature increases (0.5) since it measures peak te re in lieu of average temperature (.25).
(Alternate war ng acce ted) P-e i < Fep. g ,p ('***** CATEGORY C CONTINUED ON NEXT PAGE *****) 1
i
~
C .' GENERAL OPERATING CHARACTERISTICS Pcgo . B'1 ll REFERENCE H
/
Operating Characteristics page 1-46 -
< 'tr?gg e 1
,:jp Y ';- i
. p .x .-
ANSWER C.05 (2.00) fr$I ' ,. Op ' l l a. (2) steady state l
- b. (3) square wave !
- c. (2) steady state.
- d. (1) automatic
- e. (4) pulse (f i ve & O. 4 pts ' each)
REFERENCE ' I Operating Characteristics page 1-51 thru 54 ANSWER C.06 (1.50)
- a. greater or more
- b. diameter
- c. water or moderator REFERENCE Operating Characteristics , page 1-47 ')
ANSWER C.07 (2.00)
- a. Indicated power will increase. (1.0)
- b. Decreased fuel temperature (0.5) from increased flow (0. 5) .
REFERENCE NE 351 Experiment No. 1 Question No. 4 page 1-60 l ANSWER C.OB (2.00)
- a. To compensate for the weight of the rod or to prevent excessive' rod speed while driving "in". (1.0)
- b. To change the phase of the current.to cause " clockwise" rotation of-
.the motor. (1.0) ; 43
;glM%hpp- ;
-(***** CATEGORY C CONTINUED ON NEXT PAGE *****)'
6
v Pcgg 82 C. . - - -GENERAL
- - - - - - - - - OP ,,. . .E. R A-------------
T I N G C H A R A C T.E.------ RISTICS REFERENCE Operating Characteristics, pages 1-48 thru 50 l i i 1 l I l l T , (***** END OF CATEGORY C *****)
. _- .-~ .-.
9.__10SI59dEylS_999_ggyIgg6g Paga C3 s 1 ANSWER D.01 (1.00)
.p- 8 An anemometer readout (of wind speed and direction) locate [injthecontrol room. (Alternate description of " anemometer" accepted).y(g-f x
REFERENCE SAR amendment March 1968, page 3 ) l i ANSWER D.02 (1.50) I
- a. Prevents rod withdrawal unless the source level is above_a preset value. (0.5)
- b. The. fission counter is automatically withdrawn from the core (0.5)-
when the top of it's range is reached.(0.5) j l REFERENCE SAR page VII-5 and VII-7. Y ANSWER D.03 (1.50) 1 A voltage signal from the % demand potentiometer is compared to a signal I from the power recorder. (0. 25) If % de' mand is larger, an UP signal' is given to the regulating rod.(0.25) If a period of 5 seconds is reached (0.25), a negating signal comes from the period circuit to slow or stop the drive.(0.25). As the demand power is reached a signal from the linear recorder causes the rod to be inserted.(0.25) If % demand is smal l er than the power signal the rod drives in until the signals l become even. (0.25) (Alternate wording accepted). REFERENCE NE 351 exam 10/07/80 quest i on D.3 ANSWER D.04 (2.00)
- a. ion chamber
- b. one watt
- c. full power (or slightly above)
- d. reactor period ( four @ 0.5 pts eachb fM &
(***** CATEGORY D CONTINUED ON NEXT PAGE *****) ! i w___-____-_-_-.
Pcg9 04' l p- ' E1__1ggIBUygylg_80p_ggylB96S
??l1 i 4' ' REFERENCE SAR section VII.B.1.a (2), page VII-7
<4 W g Q,fec'l .f- 1 ANSWER D.05 (1.00) # ' kh - h t ;;
- 1. Range switch must be on the 1 megawatt setting. (0.5)
- 2. Initial power must be less than 250 kw. (0.5) {
i
~I REFERENCE l
l SAR section VII.B.1.b, page VII-8 1 ANSWER D.06 (1.00) ! Thermocouple (0.5) located in the instrumented fuel channels. ( 0. 5 ) I REFERENCE 1 l SAR section VII.B.2, page VII-10 l ANSWER D.07 (2.00)
- a. The Adjustable Transient Rod
- b. Compressed air
- c. Limit switches I
- d. To permit the rod to fall freely back into the core. (f our & O.5 pts l ea.)
REFERENCE l i SAR Section VII.B.3.a, page VII-11 ANSWER D.08 (1.50) 1 The control rod drive electromagnet is deenergized (by the scram signal) releasing the armature.(0.75) The armature, (connecting rod) and control rod drop by gravitational force. (0.75) f (***** CATEGORY D CONTINUED ON NEXT PAGE *****) l 2_--_ _ _.
9t_ IN@l@yt}ENI@,ANQ_C9N1696@ Pcg:2 C5. REFERENCE SAR Section VII.B.3.b, page VII-14
%D.;% ,
.s tw-
.- t-b ANSWER D.09 (2.00) 2 g>
- 1) Core entrance
- 2) Core exit
- 3) Secondary outlet of the heat exchanger
- 4) Return line from the cooling towers (4 9 0.5 pts each)
REFERENCE SAR Section VII.B.5.d, page VII-23 s i ANSWER D.10 (1.00) (Allows the momentum of the coolant to be dissipated) to prevent _ water ; hammer in the system. (1.0) 1 1 i l l
'1 i
r .%; [h r (***** END OF CATEGORY D *****)' 1
4 Pcgs 86 .c ~~E___!eFgly,@ND_gggRggNCX,gygIgdg ANSWER E.01, (1.00) Loss of electrical power or air causes the control rodhlte$ ;' scram. I REFERENCE SAR Section VII.B.7, page VII-24 ANSWER E.02 (1.00)
- a. weekly (0.5)
- b. three (0.5)
REFERENCE Technical Specification 4.4, page 24 ANSWER E.03 (3.00)
- 1. High power in the steady state mode.
- 2. High power in the square wave mode.
3, High power from the linear recorder.
- 4. High fuel temperature.
- 5. Low reactor tank water level. ;
- 6. High bulk reactor water temperature.
- 7. Peak power in pulse operation.
I 8. Loss of f orced coolant flow above one megawatt. l 9. Short period in steady state mode.
- 10. Loss of power to the ion chambers or fission counter.
11.. Loss of rod drive electrical power. (Any 6 0 0.5 pts each) REFERENCE SAR Section VII.B.10, page VII-30 and 31 l l ANSWER E.04 (1.00)
- 1. Cool an t exit temperature trip. (0.5)
- 2. Fuel temperature trip. (0.5) l l
7y; l;l: . (***** CATEGORY E CONTINUED ON NEXT PAGE *****)
e
)
v
) l MM a P P V .
y, x ' G G . 3 8 e k b c s g ( ( o e s r h j e e e P C i y l v vl ug y e
- a a a t n V. V G i o v h R d d e i p YET i i r t i o o u c S I' A n n s u -
CW e e s d i l l e n t o o r o n S S P C A 7 9 w 1 V 2 V. 1 V
- R E
A A P C C
^ T L
I F W gE .M R E T WE OT LE FM R R E s
,O M i
e c a M I A R G Mf . E A Pi 2 D I G r D M3 o V. W Q1 V. n
. A n T R
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C K N sAT Y A .B R l t l 8 A .. Cl~ E R 7a $9 - i O 4 l
E __E9Fgly_gND,gdgEggNCy_gy@lgd! Pcgs 87 i REFERENCE 1 l SAR Section VII.C.3, page VII-33 ) i
', 1 s%'
l ANSWER E.05 (1.50) ". lJ(E-v. - l Yp ) A natural circulatio, convective cooling l oop i s provi ded. "(O. 5) i, q A "J" tube extends from below the core to above the core. Water in the ] core is heated and rises to the top of the "J" tube. The upward flow ] through the-core sets up a natural circulation path down through the l "J" tube where the water i s cool ed by 'convecti on. (1.0) (Alternate j wording accepted). i I REFERENCE SAR Section VI.A.2, page VI-2 and 3 j i ANSWER E.06 (3.00) i
- a. SAR Figure VI-2 (2.0) .
l
- b. Val ve A. V. 2 i s opened (0.25)providing 5-8 gpm-(0.25)to the spray header. l
- c. Through val ves V-4 and V-2 (0.5)
REFERENCE SAR Figure VI-2, page VI-9 and Section VI.B.2, page VI-8 i I ANSWER E.07 (1.50)
- a. Approximately one foot. (O.75)
- b. Due to the inventory loss while the i sol ati on valves close; OR can be shown that 250 gals and with a tank diameter / eg#gpm 6.5 ft timese5' resd9ts seconds = approx in a 33 cu. ft loss per foot or 33x 7.48 gal /cu.ft.= approx 247 gallons. Therefore, approx. 1 ft.(0.75)
REFERENCE l SAR Section VI. C. 3, page VI-14 and Figure III-1 i (***** CATEGORY E CONTINUED ON NEXT PAGE *****)
E,__gMEIX_@Ng_EgggggNCy_@ygIEgg- Pago 83 .j ANSWER E.08 (1.50) e,1S ,* : , The damper in the main exhaust duct will close (A A!W r.d'typ,derp-- et M F-do-t ..i-l' y..i - O . L' forcing theJf&ow through in th @ n=1 ' the charcoal f i'l t er . (O AJ1 Mf' gj '4-
. REFERENCE SAR Secti on V. B. 2, page V-15b ANSWER E.09 (1.00)
The secondary side operates at a higher pressure than the primary side. REFERENCE SAR Section VI.E.1, page VI-19
,t *-k$
(***** END OF CATEGORY E *****) l I L___-__-_--____________-______-___________
3 E __!IONp389_9NQ_gdgg@gNgy_Qfg8@ LING _E899EpyBg! .Pago 89 g- - k ANSWER F.01 (1.00) r g
- 1. The period scram is not it".vired by Technical Specifications (0.5)
- 2. The period circuit is autr dtically bypassed when thefe"de'p switch is in the square wave or pulse position. (0.5) *y%pL
'6 REFERENCE-Standing Order No. 2 ANSWER F.02 (1.50)
- 1. Sufficient. control rods are inserted to assure that the reactor is subcritical by at least $1.00 worth of reactivity. (0.5)
- 2. Power to the control rod magnets. and actuating solenoids is of f and the key removed. (0.5)
- 3. No work is in progress involving fuel, in-core maintenance, or j control rods. (0.5)
REFERENCE Rules and Regulations for Operation of the Nuclear Reactor, May, 1988 page 3. ANSWER F.03 (1.50) l l l
- 1. When any Tech spec LCO cannot be met. l
- 2. Any condition that represents a hazard in the1 judgment of the Reactor Supervisor, Health Physicist, or. licensed operator.
- 3. Adverse weather that constitutes a threat to the' building.
- 4. Actual or threat of reactor building damage.
- 5. Any unplanned-radiation monitor alarm. (Any three G O.5 pts each) l REFERENCE Rules f or Operation, page 8
-h i.
4,
%}$h 4
(***** CATEGORY F CONTINUED ON NEXT PAGE *****)
j
'9 !
Pcgs 90 I E___!IONpggp_gNp_gDE5GENgy_ggg69I1NG_E899gggRgg
-f I
ANSWER F.04 (2.00) l N,' Oh b b I
- 1. Shutdown the reactor.
- 2. Initiate building evacuation #
- 3. Close the isol ation valves h ~~~ '
- 4. Turn off the circulation fan for t h e ai r c on d i t i on erl.*Eid'- i
~
- 5. If a leakage'of fission products or iodine is suspected, close the i diverting valve.
- 6. Turn off both water circulation systems. ( A'ny 4 @ 0.5 pts each)
REFERENCE j i Radiation Emergency Plan para. 4.4, page 10 l l l ANSWER F.05 (2.00)
- a. Check that beam ports are locked and check for water. leakage. (0.5)
- b. Verify valve is open. (0.5) ,
- c. Standard rods have down lights and position indicator shows rods ]
j inserted. (0.5)
- d. Place recorder switch in test and rotate test knob (clockwise) J until scram occurs (@ 110%). (0.5) l REFERENCE
{ Daily Checklist, pages 1-5 l i l ANSWER F.06 (1.50) l
- 1. Rod positions (0.5)
- 2. Fuel temperatures (0.5)
- 3. Bulk water temperature (0,5)
REFERENCE ( Reactor Startup and Operation procedure, page 3, step 5 I ANSWER F.07 (1.50) The primary of the Auxiliary Cooling System (purification) is on.(0.5) l The secondary side is off (0.J) unless addi ti onal ' coolinglis necessary l l and arrangements have been made for shutting off this part.of the system. (0.5) '"'Uf (***** CATEGORY F CONTINUED ON NEXT PAGE *****)
( 19 . Pcge 91 O E___!IedP8Rp,3Np,gMgB@gNgy_QPgB3IJNg_PBQ9gpyBE@ REFERENCE-Shutdown Procedure page 1, Step 3 H :;. . , I i.;f : ",fk; ANSWER F.08 (1.50)
' M&
c ?'
- 1. Shutdown the reactor
- 2. Notify the Senior Reactor Operator
- 3. Make an appraisal regarding the possible change in reactivity (Three @ 0.5 pts each).
2 REFERENCE Potential Malfunctions Procedure, page 4 f ANSWER F.09 (2.00)
- 1. Checking the proper approval of the core change.
- 2. Seeing that changes are made in accordance with written procedures j l
(if required). j
- 3. Assuring that the fuel-handling tool is properly used during fuel movements.
- 4. Assuring that later movement of the control rods will not be impaired by objects extending from the core region. ,
-(Four 9 0.5 pts each)
REFERENCE Installation and Removal of Items in the Core Region, page 1, step 4 I t
.i
- ( - -
(***** END OF CATEGORY F *****) l l 1
- 9 __68919Il9N,CQNIggy,@NQ,S@[EIy Pcgo 92
.s . ANSWER G.01 (3.00) Any six of the 14 items listed in Appendix II, page 40 of[the# Radiation Saf ety Manual . . . Parti al list as f oll ows. . . Compl ete list *st'tached to Master Copy... [
- P
(
- 1. Keep exposure as low as practical.
- 2. Wear assigned dosimetry in an approved manner.
- 3. Be familiar and comply with the Radiation Safety Manual.
- 4. Monitor work areas frequently for contamination.
- 5. Clean up minor spills immediately. *
- 6. Dispose of radioactive waste in an approved manner. ]
- 7. Notify your Supervisor and Health Physics Office of unexpected l difficulties. 1
( any six of the 14 items D O.5 pts each) i i REFERENCE ) 4 1 Radiation Safety Manual, Appendix II, page 40 i l , ANSWER G.02 (2.00)
- a. 2
- b. 4 {
- c. 1
- d. 3
\
REFERENCE Radiation Safety Manual page 1 ! l l ANSWER G.03 (1.00) Between the hip and shoulder level (0.5) outside the clothing (0.5) (Alternate wording accepted) REFERENCE i i Radiation Safety Manual Section 18, page 4, step 3 ANSWER G.04 (1.00) b g f s~ tg .:f - i f (***** CATEGORY G CONTINUED ON NEXT PAGE *****) l L
1 1. Pago 93
> 9:__B8918Il9N,CgNJggy,$Ng_pgFEIY l
l l
/
REFERENCE Radiation Saf ety Manual, Section I, page 11 .
% .1 %
t ..
.u w 1
'(
*, L'?b n :i ANSWER G.05 (1.50)
. hl. '
a. 1.25 rem l
- b. 18.75 rem (three @ O.5 pts'each) l
- c. 7.5 rem REFERENCE , f 10CFR 20.101a l
ANSWER G.06 (1.00)
# The person's age in years J I
REFERENCE \ i 10CFR 20.101 (b) 2
.l ANSWER G.07 (1.00) l W
Ten percent of the adult limit or 125 mrem. J l l l REFERENCE f 9 10CFR 20.104 (a) j ANSWER G.OB (1.50)
- a. 5
- b. one l
- c. 100 ( Three @ 0.5 pts each)
REFERENCE 10CF.R 20.202 (b) (2) and (3) i +
/, ,
N; [f: , ' ,I s [1hb. l (***** CATEGORY G CONTINUED ON NEXT PAGE *****) l 9
I
+
Pcg3 94 v G___59P18Il9N,ggNJ$g6,@Np_S3[EIY ., ANSWER G.09 (3.00) s;/4Wi:,sv4 I
- 1. Area monitors: near thermal column, above bulk shie(~(( f,acility, above reactor, lobby, and near domineralizer ( . :25 ) }'#(125) audible horn and red light. (.25) Nij ,[2i*
- 2. Continuous upper level in front of exhaust system #(72Blj beta-gamma l and alpha (.25), audible beep and red light. (.25) d^ ' '
- 3. Exhaust air: In the exhaust stack (.25), beta or gamma (.35),
j audible beep and red light. (.25)
- 4. Water monitor: In the primary water (.25), gamma (.25), buzzer and l red light. (.25) l REFERENCE I
l NE 331 exam 10/07/1980 question G.6 l l 1 1 l l l r h l ! 1 l I
,;; -7cy:q s.
?y, l
/ h! . Ni
[5 g 4 (***** END OF CATEGORY G *****) (********** END OF EXAMINATION **********)
r c__ . .
~
-r 69 -
40 h gg G . O I, Appendix II
' Respon*1btlities of the Individual User ,
Tne Individual user Is the one ultimately responsible for the safe , _c sse of the radiation sources to which he has access. He shall: V f'$,
' ~^
1 Keep his exposure as tw as practical. t. 2 Wear assigned Personnel Monitoring devices in an approved manner. 3 8b famillar with and comply with all sections of this manual applicable to his work. 4 Be famillar with the nature of his area's radiation sources, the extent of thier potential risk and use the proper means of coping with thern safely. -
- 5. Monitor his area frequently for contamination.
6 Clean up minor spills Ininediately. Dispose of radioactive waste in an' approved manner. 7 _ 8 See that sources, containers, and the area are properly I labeled and posted. .
~
9 Assist his supervisor in mainta1ning required records and Inventories. 10 Prevent unauthorized persons from having access to radiation sources In his area,
- 11. Protect service personnel, allwing no maintenance or repairs of area facilities or equipment unless approved by the area .
' supervisor and/or t,he Health Physics Office.
- 12. Notify his supervisor and the Health Physics Office of un-expected difficulties.
13 Be prepared to handle accidents or injuries with comon sense - and l~n the spirit of the Emergency Procedures, Section I, Part I. He shall notify and seek the assistance of his im-mediate supervisor and the Health Physics Office as soon as j possible in emergencies. , e 14 Take no action that would Interfere with the responsibilities of his ' laboratory supervisor ( see. Appendix II, Part C). -
.Aj, f, ,4 .
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