IR 05000057/1987002
| ML20235Z586 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 10/09/1987 |
| From: | Keller R, Norris B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20235Z577 | List: |
| References | |
| 50-057-87-02OL, 50-57-87-2OL, NUDOCS 8710210211 | |
| Download: ML20235Z586 (102) | |
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L I i i U.S. NUCLEAR REGULATORY COMMISSION REGION I ' OPERATOR. LICENSING EXAMINATION REPORT EXAMINATION REPORT N0.: 87-02(0L) 1 FACILITY DOCKET NO.: 50-057 FACILITY LICENSE NO.: R-77 LICENSEE: State University of New York at Buffalo
' Rotary Road Buffalo, New York 14214 l
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FACILITY: Buffalo Materials Research Center l EXAMINATION DATES: August 10-12, 1987 l CHIEF EXAMINER: Barri 7. ,tforris
$ ade/ 77 Date /
SeniorL0perations Engineer (Examiner) APPROVED BY: Rob'ert M. K &ler, Ch ef
.[/)1/[. /d-7"P7 Date Pressurized Water Reactor (PWR) Section Division of Reactor Safety SUMMARY: Written and operating examinations were administered to one Senior j Reactor Operator (SR0) and three Reactor Operator (RO) candidates. All four candidates passed their examinations and received their licenses j Two major generic. weaknesses were identified during the oral examination. Of the four candidates examined, no one could describe how to use a Scott Air-Pac for emergency entry into the containment building in the event of a fire; your emergency procedure requires the fire department personnel to be escorted into the containment. The second major generic weakness was that none of the candi-dates could describe how to locally start and load the emergency generator in ,
the event of a power failure. Both of these items were discussed at the exit meeting with the facility personnel.
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DETAILS TYPE OF EXAMINATIONS: Replacement I I EXAMINATION RESULTS: I i y l. R0- l SRO l l Pass / Fall l Pass / Fail l' I I I I I . I I l Written I 3/3 l 1/1 l .;' l l i 1 I I I . l
.l Operating l 3/3- l 1/1 l l' l- 1 I I I I I 1
'l Overall. l 3/3 l 1/1 l
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I I I l CHIEF EXAMINER AT-SITE: B. (USNRC) 1. The following is a summary of generic deficiencies noted on the operating examinations. This information is being provided to aid the licensee in upgrading ' license and requalification training programs. No licensee response is required, a. Of the four candidates, no one was able to describe the proper method for using a Scott Air-Pac (self contained breathing apparatus).
, b. Of the four candidates, no one was able to describe how to locally start l and load the emergency generator in the event of a power failure I coincident with a failure of the generator to start automatically, c. All of the candidates were weak on the proper methods for exiting a potentially contaminated environment.
d. Two of the four candidates did not know which portable monitor to use to detect neutron radiation e. Two of the four candidates stated that they would "run-in" the con- ! trol rods on a rod reversal that did not clear; the emergency pro- : cedure states to manually scram the reactor.
f. None of the candidates ' used any procedures during the operating examinations;' use of the procedures may have prevented the wrong action described above.
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'2. The following is a summary of. generic deficiencies noted from the grading of written examinations. This information ~ is being provided to aid the licensee in upgrading license and. requalification training programs. No licensee response is required.
a. Questions C.06 and J.03: three out of four candidates were unable.to explain what caused the . temperature coefficient to be negative.
b. . Questions C.08 and J 07: four out of four candidates were unable to I state the basis for limiting .the use of the fission plate to the outside face of the thermal column.
c. Question E.03: three out of three R0 candidates were unable-to state the engineered safety feature system at SUNYAB. ! d. Questions- F.06 and L'.04: four out of four candidates were. unable to correctly define' the condition of the reactor being secured.
e. Question G.07: .three out of three R0 candidates were unable to state the design features: that minimize the release of radioactivity from the thermal column.
3. Personnel Present at Exit Interview: NRC Personnel i 8. S. Norris, Senior Operations Engineer (Examiner) {
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Facility Personnel L. G. Henry, Director P. M. Orlosky, Operations Manager i 4. Summary of comments made at exit interview: l
a. The Examiner discussed the generic weaknesses identified during the . operating examinations:
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(1) Of the four candidates examined, no one could describe how to use a Scott Air-Pac for emergency entry into the containment building in the event of a fire and/or potentially high airborne i contamination. Emergency Procedure #6 requires the fire depart-ment personnel to be escorted into the containment. l The facility stated that the licensed operators do not need to know how to use the . Scott Air-Pac as they would let the fire continue to burn until someone arrived who had been trained in the use of a Scott Air-Pac. If the fire were allowed to burn ,
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until a trained individual were to arrive, the pressure increase inside the building could jeopardize the integrity of the containment. The facility needs to designate a position on shift who is responsible for the use of the Scott Air-Pac; if not the licensed operator, then another required position.
(2) All candidates were weak on the use of the five-minute emergency air supply (ELSA's). They admitted that they had received ( training on the use of the ELSA, but had never actually put one on.
(3) None of the candidates could describe how they would locally start and load the emergency generator in the event of a power failure. The emergency generator is the alternate power supply for the effluent monitoring system.
(4) All of the candidates were weak on the proper technique to be used when exiting a potentially contaminated area; specifically, checking a hand for contamination prior to picking up the probe.
Additionally, none of the candidates could state how many counts above background was considered contaminated when using a port-l able "frisker".
(5) Additional generic weaknesses as previously identified in Section 1 of this report.
I b. The facility stated that some of the questions on the written exam-l inations covered material and/or systems that had not been used for I many years. The Examiner stated that even though the facility had I elected not to use some of the materials and/or systems, the license still allowed their use and therefore the questions were valid.
Attachments: 1. Written Examination and Answer Key (RO) 2. Written Examination and Answer Key (SRO) . 3. Facility Comments on Written Examinations l 4. NRC Response to Facility Comments
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: <. m U. S.' NUCLEAR REGULATORY COMMISSION
yg,,- ' REACTOR OPERATOR LICENSE EXAMINATION FACILITY: STATE UNIV. OF NEW YORK
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REACTOR TYPE: TEST !- ' fa DATE ADMINISTERED: 87/08/ # EXAMINER: HUENEFELD i CANDIDATE: /71t d'r Y Mev -
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INSTRUCTIONS TO CANDIDATE: Use_ separate paaer for the answers. Write answers on one side only.
Staple question sleet on top of the answer sheets. . Points for each , j
- question are' indicated in parentheses after the question. The passing '
grade be picket recuires at. least 70% in each category. Examination papers will up six (6) hours after the examination starts,, '
% OF . CATEGORY % OF ' CANDIDATE'S CATEGORY-VALUE TOTAL SCORE VALUE l
CATEGORY 13.50 j 4+r6& 14.50 A. PRINCIPLES OF REACTOR OPERATION
.:14.00 14.00 B. FEATURES OF FACILITY DESIGN
_ 14.50 14.50 C. GENERAL OPERATING CHARACTERISTICS 14.00' 14.00 'D. I INSTRUMENTS AND CONTROLS 14.50 14.50 E.
_ SAFETY AND EMERGENCY SYSTEMS .j 14.00 14.00- F. STANDARD AND EMERGENCY OPERATING PROCEDURES 14.50 14.50- G. RADIATION CONTROL AND SAFETY
' .Rf.n00 % Totals Final Grade >
All work done on this exam'ination is my own. I have neither given nor received aid.. g .rf , . * Candidate's Signature
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, :. S ,$ ' -N3C RULES AND GUIDELINES FOR' LICENSE EXAMINATIONS , ,.- During the administration of this examination the fol. lowing rules' apply: l <1. Cheating on the examination means an automatic denial.of ycur application i and could result in more severe penalties.. j 2. 'Restroom trips are to be limited and only one candidate at a time may leave. You must-avoid'all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
3. Use black ink or dark pencil only to 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 pape'r provided for answers.
' 7. Print.your name in the upper right-hand corner of t% first page of each t 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 on 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.
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 OF THE l QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK. ! 16..If parts of the examination are not clear as to intent, ask questions of ;
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the examiner only.
17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
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.# ' !a. Assemble your examination as follows: ,
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[ l(1)' Exam questions on top, (2)' Exam' aids - figures, tables, etc.
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j (3) Answer.pages including figures which are part of the answer.
b. Turn'in our copy of the examination.and.all pages used to answer -1
:the examination questions. ]
c. ' Turn in all scrap paper and the. balance of the paper that you did . not use for answering the questions.- , d. . Lene the examination area, as defined by the examiner. If:after j ' lecting, you Are found in-this area while the examination is still Lin, progress, 'your license may be denied or revoked.
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~ QUESTION'A.01; (1.00) DM c . The reactor is' ex ctly critical with a trong' source relative to :the time scale.. ICH curve on the aph below is best.represen-tative of the resu tant-rate'of cha e of neutron population? (SELECT one.) (1.0)
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QUESTION 'A.02 (1.00).
~WHICH one of the following is a good approximation to the value of K effective if the value of reactivity is known? (SELECT'ne) o (1.0)
(A.)' Keff = 1 + rho (B.) Keff = rho - beta 1 (C.) Keff = 1 - rho i ,. (D.) Keff = rho + beta l QUESTION A.03 (2.00) ,
WHICH startup requires the MOST cautious approach to criticality, an approach made with a high residual power level or a low residual power level? WHY? (2.0)
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QUESTION A.04 (1.00) 3 A control rod's DIFFERENTIAL rod worth-varies with axial position 1 , in the core. This is mostly due to:- (SELECTone) (1.0)
(A.) the axial temperature gradient through the core.
-(B.) the axial neutron " wash out" effect caused by forced convection.
(C.) the " shape" of the axial neutron flux. !
(D.) the worth of the displaced water in the rod channel.
i QUESTION A.05 (2.'00) j i Fuel assemblies are shuffled to move some of the peripheral ; assemblies to the center and the central assemblies to the peri abery. Assuming that only original fuel elements remain i in t1e core, and no. net fuel addition or subtraction took place, WOULD it be safe to assume that no change in core excess reactivity took place? EXPLAIN.
(2.0) QUESTION A 06 (2.00) Drain lines exiting the containment buildina contain 24 inch
" dip legs" to maintain containment integrity. HOW much internal .
j pressure would be necessary to empty these dip legs? SHOW your work. (Density of water at 70 degrees F = 62.3 lb/ft cubed) {
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QUESTION A.07 (1.50) i WHAT is rod shadowing and WHAT is its significance? (1.5) j
l 1 QUESTION A.08 (2.00)
WHAT two (2) measures of reactor power, independent of neutron flux, are available to the reactor operator? (2.0) f l l
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. QUESTION .A.09' -(2.00)j :WHAT two'(2) thermal phenomenon cre: assumed to result.in.
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't; ;;4; .+- ' s c B. FEATURES OF FACILITY DESIGN PAGE E5 $,l])l
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! I QUESTION B.01 (1.00) L 4 L Your facility.'s SER concludes that damage to the reactor from wind or other storm damage is very unlikely. STATE one (1) of the two
.(2) design; features that support this conclusion. (1.0) .
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- -QUESTION. B.02 (2.00)-
Including the beam-tube ports there are six (6) types of penetrations of the reactor pool. liner. . STATE the remaining
. .;five (5) types of liner penetrations.. (2.0)
u -QUESTION. B.03 (1.50) WHAT is done to holes'in the core grid plate that are not required i for fuel assemblies or-incore experiments? WHY7 (1.5) J
- QUESTION B.04 (2.00)
a.- 'WHAT is the' purpose of the core " flapper" valve?
(1.0)
b. WHAT holds the flapper valve shut? (1.0) QUESTION B.05 (2.60) MAKE a sketch of. the primary cooling system showing: 1. the reactor tank and its isolation valves (0.6) 2. .the holdup tank (0.5) 3. the primary coolant pump, .its isolation valves, and (0.6) recirculation loop-4. the heat exchanger (0.5) 5; the purification loop supply and return taps (0.4)
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- ' QUESTION' B.0'6- (2.40).
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of the loads supplied by each subsystem.
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QUESTION B.07- (. 50)- -l
' ANSWER TRUE or FALSE.
All three of the compressed air subsystem:1may be cross connected. :(0.5) t
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QUESTION -B.08. (1.00).
-WHAT.NON-RADIOLOGICAL caution.must be applied when operating the 11ead.shuttersin the. dry chamber? WHY7- (1.0) QUESTION B.09' _(1.00) WHAT is the purpose of the " suction-valve-closed" interlock? (1.0) l
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y{ s > y yp > g. ' QUESTION;;C.01: ' (1.00) .-
, .AboutHOW long'should it'take from SCRAM initiation to full- ]
" ; insertion of'.the.scramable control-blades?
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QUESTION : C.02 (1.50)
' LHOW long does it' take' to drive'~one of the scramable control rods fullfstroke? (1.5) j i ~
LQUESTION: _C.03 '(1.00).
Approximately WH T is the. combined total worth of all six (6) control' blades?! (1.0).
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QUESTION L C.04.- (1.50)-
'a.. 'WHICH twoL (2) centrol blades'(by number) have' the greatest -
-integral rod worth? (1.0)-
-bi Dothetwo'(2)'rodsthathavethegreatestINTEGRAL. rod- d worth also have the greatest DIFFERENTIAL rod worth? (0.5) I
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l , QUESTION C.05 .(1.00) WHAT minimum number of fresh fuel assemblies will' result in an ,
' approximate critical mass? -(SELECT one.) (1.0)
l(A.) 9' {
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(C.) 22 l u. (D.)27
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! QUESTION: 'C.06 (l.00)_ , l' K :n 'WHAT phenomenon'is.most responsible for the prompt negative [
;. temperature coefficient'in the PULSTAR reactor? -(1.0)
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j l I QUESTION l-C.07 (1.00)'
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. Assuming. isothermal, xenon. free conditions, about how much,
: reactivity is needed to'go-from critical below the point of
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adding ~ heat up to 2 MW7 (1.0)-
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p ~QUESTI0'N.I C.08 -(1.50) WHAT is-the bases for limiting use of-the fission plate to the outside face of-the~ thermal column only? (1.5)-
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QUESTION C.09- :(2.00)
> A very small sample of low cross-section materials is to be
' exposed-in'an IF, positioned in an area of. maximum flux.
DESCRIBE the process by which the sample is' suspended in the
. area of peak flux. (2.0)
QUESTION C.10 (1.00) WHY is positioning an IF sample at low power more sensitive than doing so at high power? (1.0) i (***** CATEGORY C CONTINUEDONNEXTPAGE*****) h.__,,,,_ m , _ _ _ _ _ . _ _ _ . . _ - . _ _ _
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LTheNSTFfreactorbuildingis_ air'conditionedwithabout ' air ichanges:per hour.; . (SELECT. one.) (1.0) L(A.)LO.04-(B'. ) l 0. 4 ' ,
(C. ); 4
'(D.) 40
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' QUESTION C.12 (1s.00)
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.a.- DOES secondary coolant flow on the shell side or on the -
. tube side ~of the heat exchanger? :(0.4)- 1
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L b .- WHAT is the' problem when primary side pressure exceeds
. secondary side' pressure? ;
(0.6) ;
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et J, QUEST 18'.6 0.01. (c .50) .'
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; ANSWER TRUE;or FALSE.
I The control blade drives could, by design, be" positioned to cover l any of the spaces in the grid plate. (0.5)
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j l. . QUESTIONLD.02. (.50) f
l ANSWER TRUE or FALSE.
'According to the SUNY SER.the scramable control blades may'be
- activated either individually or in groups of two. three, four, or five. (0.5)
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- QUESTION-D.03 (3.00)' -l STATE six.(6) of.the seven (7) signals that can initiate an automatic. reactor scram. Exact setpoints are not required.. (3.0) l
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i QUESTION D . 04 .: (3.00) ; o
: STATE the five (5) types of nuclear instrumentation used to j monitor, control,.or automatically shutdown the reactor. Also -)
STATE the function that each type provides. (3.0) l- QUESTION D.05 (1.50) l
.WHY are some of the neutron detectors " compensated" while others Eare not? (1.5) i
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QUESTION D.06 (2.00) !
.The Reactor Saf(t System provides two (2) types of SCRAMS.
-STATE'these two (y) 2 types of SCRAMS, and HOW the safety circuit
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causes each type of SCRAM. (2.0)
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LQUESTION--0.07 (1.50) '
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LIST the two.(2) ". inhibit" signals that will prevent control
: blade withdrawal.. .,
(1.5) ;
QUESTION. 0.08 ..(1.00) HOW:is the effect of N**16 on the' primary coolant beta-g'amma
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: monitor: eliminated? -
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. QUESTION .D.09 (1.00)
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iSTATE the three (3) voltage ranges available at the distribution panels within the reactor facility. .
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E. SAFETY AND EMERGENCY SYSTEMS PAGE 12 ,. . . QUESTION E.01 (1.50) STATE the general locations of the fixed area radiation monitors. (1.5) QUESTION E.02 (1.50) WHAT signals are necessary to actuate the reactor building
. ventilation damper closure system? (1.5)
QUESTION E.03 (1.00)
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STATE the engineered safety features system (s) at SUNYAB NSTF. (1.0) QUESTION E.04 (.50) WilAT is the source of water used by the emergency pool-filling system?- _
(0.5)
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QUESTION E.05 (1.50) STATE the automatic actions that will occur upon actuation of the reactor building ventilation damner closure system. (1.5)
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QUESTION E.06 (1.50) a. WHAT design feature allows operation of ventilation system dampers under power failure conditions? (1.0) - b. HOW long will operation of the ventilation dampers be possible? (0.5) _
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1 , i y + ,, l QUESTION = E.07_ .(1.00) L ja, ,o, 'WHAT is the rated'. loa'd of the emergency' generator?. (1.0)- ! k . . QUEST' ION L E.08, (2.50).
a ' The emergency generator provides power t.o WHAT reactor facility
- . loads?; (2.5)
l l ~ QUESTION E.09- (1.00)- :) WHAT-is.the emergency power supply for the exhaust blower located at the base of the stack? (1.0) . l-QUESTION E.10. (2.50) STATE the location.of five (5)'of the eight (8). fire alarm ,
. boxes that will cause the alarm to sound within the building. (2.5)
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QUESTION F.01' '(.50) ANSWER TRUE or FALSE.
There is no limit 'for how much ne.getive reactivity an individual secured experiment may be worth. (0.5) QUESTION F.02 (1.00) f WHAT is the difference between " Control Blade" and a " Control-Safety Blade," as defined by Technical Specifications? (1.0)
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QUESTION F.03 (1.00) The fission plate must be maintained at least from any other fissile material. (SELECT one) (1.0)
. 16 cm . 16 inches . 1.6 feet . 1.6 meters QUESTION F.04 (1.00)
Reactor pool temperature is maintained at the desired value by: (SELECT one) ,
(1.0) (A.) adjusting the primary flow.
(B.) adjusting the s(condary flow.
(C.)' adjusting both the secondary and primary flows.
(D.) adjusting the demineralized flowrate.
QUESTION F 05 .
(1.00)
The quality of primary coolant is maintained by its attached purification system. HOW is the quality of the secondary coolant maintained? (1.0)
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LQUESJION.F.06~ ,'(2.00) g/,
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Q,.,% Jak : Reactor l Secured .(1.0)- b. ' Reactor Shutdown
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,p QUESTION?F.07.. (2.00)'
s t- ' o fl Special restrictions' allow..the irradiation of explosive mate-kd["d t
. rial; however,4 irradiation'of explosive material-is absolutely .o (prohibitedJin WHAT two,(2) general locations? (2.0)
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.0]4j;04QUESTION.F.08 . .
y , - (1.00)
- Assume' the reactor is at power and -the reactor SCRAM ,
annunciator. annunciated; WHAT two1(2) actions'is'the reactor operator required to do? .' (1. 0)
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o o 4, QUESTIONF.09 :( 50) During'a routine startup to full. power WHAT is the shortest
< reactor period permissible by your operating procedures? (0.5)
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QUESTI0ll E.10- -(- .50) s., y . , 7 ' ANSWER ^TRUE or FALSE. '
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The act of resetting an intrusion alarm cancels the automatic call
.toLPublic Safety. (0.5) .j %
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M (***** CATEGORY F CONTINUED ON NEXT PAGE *****) f, ' 'I:l _ ,da T,I i . r,h . ', ?. } !
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QUESTION F.11 (.50) ANSWER TRUE or FALSE.
In response to a fire alarm the reactor operator should SCRAM the Pratt dampers. (0.5) QUESTI0q F.12 (2.00) STATF five (5) of the eight (8) operator actions required
,
should a loss ,of primary flow occur without leakage. (2.0)
' / (
I, ) -
;
./
'
'
QUESTION F.13 (1.00)
'
An IF can hap been dropped into the reactor pool, and its exact gosition cannot be ascertained, WHAT must the reactor operator do? (1.0)
\
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.?
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) (***** END OF CATEGORY F *****)
__
_ _ - . .. _a au (.y , . . E l g ., _ , j 1
,
QUESTION-G.01) -(.50)
'
ANSWER;TRUE{or FALSE.
j
' '
For'more7 effective: lateral shielding, the lower section of the 'i reactor pool:is composed of.a different type'of material'than the- ( upper section.
-
'(0 5)
.
l
,
QUESTIONmG.02 '(1.50)
'
'
,WHY does thesirradiation iube'in the Becquerel irradiation
' facility have an off-set curve? (1.5)
:i a
' QUESTION G.03 (.50)
LWhen initially. removing' an;IF (isotope production facility sample) from the core, it should remain below HOW many feet of water for 30 minutes. (0.5) t .j
] . QUESTION: G.04 (1.00) i ' ...A sampleLca.n is being held with the tongs when it becomes ' suddenly. apparent.that.the sample is too active. WHAT should be done? (1.0)
' - QUESTION. G'.05 (2.00)
STATE.four (4). potential airborne radioactive wastu products that may exist at your facility.. (2.0) 1
,
(***** CATEGORY G CONTINUED ON NEXT PAGE *****) )
:
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b m__.___.__ __ _ - _ . _ _ _
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QUESTION G.06 -(2.50)
-a. DESCRIBEthethree(3)typesoftanksthatmakethe t " collect-hold-samp'le-analyze-release" philosophy of liquid waste control possible. (1.5)
b. HOW can you assure that samples from these tanks are representative? (1.0)
'
' QUESTION G.07 (1.50)
' WHA 1. design feature controls the release of Ar**41 from the Thermal Column? .
(1.5)
QUESTION G.08 .(1.50) WHAT design feature associated with the pneumatic transfer systems helps to' prevent inadvertent radiation exposure of the transfer system operator? (1.5) QUESTION G.09 (2.00) HHAT two (2) design features help to reduce radiation expo.c ; when entry into the dry irradiation chamber is required? (2.0)
,
QUESTION G.10 (1.50) i STATE the difference between the methods of particulate monitoring ! used by the building exhaust system and the stack exhaust system. (1.5) l l l (***** Eh'D OF CATEGORY G *****) .
(************* END OF EXAMINATION ***************)
1.. i
___
, . .
_______......__. ___............ .._________________.._.....___..._______...
.
EQUATION SHEET
......_____________.._______ ___________________________________ ..________ l . .
Where mi = m2 (density)1(velocity)1(area)1 = (density)2(velocity)2(area)2 ________________ .._________________.___________________...______.____..____ KE=*{2- PE = mgh PE + KE +P V i 1 1 1 = PE +KE2 2+P Y22 where V = specific volume P = Pressure
.........___.__________.......__...____.....________________________ .___.__ . . 1 Q = mcp(Tout -T j n) .
Q = UA (T ave -Tstm) Q = m(hi -h2 ) ;
._____________.._____________...._____________________.. ____ .._____.______
P = Pg10(SUR)(t)' P = Po et /T SUR = 26.06 T = (B-p)t T p
..__.____________....____.__.__.... ____.._______.._-___...___..__.._______.
delta K = (K,ff-1) CR1 (1-Keff1) = CR2 (1~Keff2) CR = S/(1-Keff)
(1-Keffi) SDM =
(1-Keff) x 100%-
M = (1-Keff2) K eff _______...___. ____________ ...... ________.......___.______________________ decay constant = in (2J * 0.693 A l " S o*-(decay constant)x(t) t t 1/2 1/2 _____.___......__________..___.... ________ ...____ . ____________._________ Water Parameters Miscellaneous Conversions I gallon = 8.345 lbs 1 Curie = 3.7 x 10 10 dps , 1 gallon = 3.78 liters 1 kg = 2.21 lbs l 1 ft 3= 7.48 gallons 1 hp = 2.54 x 103 Btu /hr 3 6 Density = 62.4 lbg/ft 1 MW = 3.41 x 10 btu /hr Density = 1 gm/cm 1 Btu = 778 ft-lbf
'
Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters 2 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft_lbm/lbf-sec l __.._____ ... ___________..____ ...________________......__________________ - _ _ . _ _ _ .__ _ _ _ . _ _ . . _ _ .
---
% .I ' >. ' ' ~ A.- PRINCIPLES OF REACTOR OPERATION- PAGE 19 -
ANSWERS - cSTATE UNIV.'0F NEW YORK -87/08/11-HUENEFELD, J.
i p ANSWER A.01. (1.00)
(B.) [+1.
REFERENCE' 1. Y: ANL- 01'." Approach to Critical," p. 18.
,
-ANSWER-' - A.02 - ( 1.00) -(A.) [+1.0]-
REFERENCE-
'
1. .SUNY: Interoffice Memorandum dated 6/18/85.
ANSWER 'A.03 (2.00) An approach made under, high residual power conditions [+0.5]. This
.is because of the relative increase in sensitivity of countrate for a given change.in. reactivity,.i.e., suberitical multiplication affects. 'The'high residual power causes the reactor to behave as though it had a very strong source, and will therefore experience a proportionally stronger prompt neutron effect caused by subcritical multiplication [+1.5].-
REFERENCE 1. SUNY: OP No. 5, pp. 1 and 2.
2.- SUNY: ANL-6701, pp. 17 through 19.
ANSWER' A.01' (1.00)
(C.) [+1.0] -REFERENCE-1.- SUNY: Reactivity Summary Loading No. 140.
I
_ _ _ _ _ __ _ _
.~m -
I.' ' ANSWERS'-- STATE UNIV. OF.NEW YORK -87/08/11-HUENEFELD, J.
- .
-
ANSWER A.05 (2.00) !
- '
No. [+0.5]. Moving the fuel: elements around might significantly I
' affect core excess reactivity. This is because there may have been .a net' change in the macroscopic crossection for uranium, that is-- . net fuel may have been. shifted toward or away from regions of higher potential neutron flux -[+1.5] . )i REFERENCE -i ' 1. SUNY: OP No. 4, p. 5.
ANSWER A.06- (2.00) Pressure = (Density)(height) = (62.3 lb/ft cubed)(2 ft)
= 124.6 lb/ft squared =
0.87 psi A pressure of < 1 psid would' result in breaking the loop seals in the drains.
[+2.0] REFERENCE 1. SUNY: OP 81, Containment Building Leak Test. Qual Card
'IV.10d, p. 6.
! ANSWER A.07 (1.50) It is a local suppression of neutron flux [+0.75] causing one of the ion chambers to read low relative to the true value of thermal power [+0.75]. REFERENCE 1. SUNY: Technical Specifications, p. 21.
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' Y' ' D[dNSWERSI--'STATEUNIV.0FNEWYORK -87/08/11-HUENEFELD, J.- r, .
, . . 'A.08 -
iANSWER- ~ (2.00) '
'The N**16 power indicato'r The core delta T or primary. temperature systems (one'of these two) . ~ .[+1.0] each-q ; REFERENCE.
'1' . SUNY: Technical Specifications, p. 11.
JL ,
-ANSW'R E A.09 '(2.00) .
1.. departure from nucleate boiling i
.
2.- fuel centerline melting
.[+1.0] each -
REFERENCE' 1. SUNY: SER, NUREG-0982, p. 4-5.
, w
M' ' ANSWERS - " STATE. UNIV. OF NEW YORK -87/08/11-HUENEFELD, J.
,
) --. > :,-
D ANSWER ,B~01.
. ,
(1.00)'
l '. -. reactor containment'. ! 2. - ' reactor pool. is mostly below grade level.
. ! Any one (1)' [+1.0],' maximum +1' 0.
. .
. REFERENCE'
1. : :SUNY: .SER,'NUREG-0982, p. 3-1.
ANSWER- -B.02 (2.00)
. ~1.. . pneumatic conveyor system 2. -primary coolant exit 3. primary coolant supply 4. passthrough canal .5. emergency pool fill nozzles i [+0.4]each REFERENCE 1.- SUNY: SER,-NUREG-0982, pp. 4-3 and 4-4.
ANSWER B.03~ (1.50) l They are plugged [+0.5] to confine coolant flow to core assemblies d and experiment positions [+1.0]. REFERENCE 1. SUNY: SER, NUREG-0982, p. 4-4.
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_ _ _ _ _ _ --- om w I*U .' ANSWERS.--; STATE UN OF NEW YORK' -87/08/11-HUENEFELD, J.
, ... # , j 7, ,
' ' : ANSWER LB.04' 2.00)
a.s It gravity opens upon loss of forced flow to allowing heat ' transfer from the core to the pool heater by natural j1
.~ convection. [+1.0]-
-b.. The" differential pressure across the core during forced l convection'(alternative 1 coolant. pump suction).=u+y,1.0]it is held closed by primary
"
REFERENCE
1.- SUNY: SER, NUREG-0982,' p. 5-1.
c
.
.
ANSWER B.05 (2.60)
-See the attached drawing.
REFERENCE ' 1. SUNY:'SER, NUREG-0982, p. 5-3, figure 5.1. 1 I
. ANSWER B.06 (2.40)
A large compressor [+0.4] supplies air to [+0.4 for any one of the following loads) the air lock, and truck door inflatable seals, the demineralizers, the fume hoods, and laboratory benches.
A second subsystem supplies air to the reactor building ventilation controls.[+0.8).
A third subsystem consists of a small compressor dedicated to
- supply air to the primary coolant flow transmitter [+0.8]. [+1.0] each . REFERENCE 1. . SUNY: SER, NUREG-0982, p. 9-1.
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' 'INSWERS--STATEUNIV.'0FfNEWYORK -87/08/11-HUENEFELD, J.
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dNSWER B.07.1 (.50)
.True . [+0. 5] ' .
JREFERENCE: 11. - SUNY: SER,'NUREG-0982, p.~9-1.
.
-l JANSWER- lB.08: (1;00).
- The're.'are no motor control limit switches '[+0.5], -therefore the shutter 3 . winch must be manually., started and stopped to. prevent over-travel [+0.5].- 1
! ' REFERENCE -
l-1. SUNY: OP No. 48, p. 3.
. AhSWER - B.09 (1.00)' It prevents implosion of the N-16 delay tank [+0.5] that could be caused if a vacuum were allowed to form in the tank [+0.5]. REFERENCE 1. SUNY: Technical Specifications, p. 11.
__.__. --
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--_. _ ...
ams se
* ;.. - ' ANSWERS ~-- STATE UNIV. OF NEW YORK -87/08/11-HUENEFELD,J.
.-
" ; ,
LANSWER C.01' 't (1.00) less than one second (0.65.secionds)- [+1.0] REFERENCE-
.
I 1. SUNY:'SER,'NUREG-0982, p.- 4-3.-
, ' ANSWER C . 02. (1.50) "(Rod speed'is 3 in/ min, full stroke distance is 26. inches. Full stroke travel time is 8,.7 minutes.) Accept 9 +/-1 minute [+1.5] - ' REFERENCE-1. SUNY: Technical Specifications, p. 27.
- . ANSWER. .. C . 03 (1.00) .10% delta k/k (9.932 delta k/k) [+1.0]
REFERENCE 1.: SUNY: Reactivity loading report, No. 140.
. ANSWER C.04 (1.50) a. blades 3 and 4 [+1.0] b. -- yes [+0.5] l REFERENCE 1. - SUNY: Reactivity loading report, No. 140.
'
' ANSWER C.05 (1.00) (B.) [+1.0]
1 i l l'
:
____-__u.m_ ---- - - -
. :. .' ' , ' ANSWER $' STATE UNIV; 0F NEW YORK -87/08/11-HUENEFELD, J.
~ \
*
, . REFERENCE'
' '1.
-
:SUNY:'SER, NUREG-0982,-p. 4-2.
l!
-ANSWER, 'C.06.
o (1.00) Doppler l broadening.of U**238 [+1.0]
,
REFERENCE
!
l 1. - SUNY: 'SER, NUREG-0982, p. 4-5. !
!
i
~ ANSWER. C.07 (1.'00) . . .
i
. .
The value of, power defect is about 0.35% delta k/k. [+1.0] !
' REFERENCE-l 1. SUNY: SER, NUREG-0982, p. 4-8.
! I
-. ANSWER C.08 (1.50):
This ensures that the fission plate will be used only in a very. low
, . neutron flux [+0.5] therefore limiting the power generated in the plate to a level where temperature increase will be limited and will-occur slowly [+1.0] .
REFERENCE' 1.- SUNY:LTechnical Specifications,-p. 18.
i ANSWER C.09 (2,00) i The sample will exhibit positive reac.tivit Reactor power should
.be lowered by about 20% before insertion [y.+0.5]. During insertion the power will increase, being compensated for by doppler, so no rod motion should be necessary [+0.5]. As the IF presses through the peak-flux, power will start to dro) [+0.5]. The IF is then pulled back through and suspended at_tle position corresponding to
.. the highest power level on the chart recorder [+0.5].
I
-
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p.
j ..:' ANSWERS --' STATE. UNIV.LOF.NEW YORK' -87/08/11-HUENEFELD, J.. );f .
,
f .
' REFERENCE- -
L 1.: -SUNY: OP.No. 49, p.-3.
<
. ANSWER :C.10; .(1.00) '
There will be.little, if any,: prompt negative feedback from doppler to compensateLfor the reactivity effects of the IF. [+1.0].
. REFERENCE '1. .SUNY: OP No. 49, p.-4..- . .
ANSWER 'C.11 (1.00)
.(C.) [+1.0] : REFERENCE ,
1. - .SUNY: SER,.NUREG-0982, p. 4-1._ ANSWER ' C.12: '(l'.00) a.. tubeside.[+0.4]. b.- potential for rimar to atmosphere +0.3]y to secondary leak [+0.3] and therefore
! REFERENCE'
I l'. - lSUNY: SER,.NUREG-0982,.p. 5-2. ;
-
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.; ANSWER- D.01- .
(' 50)
'.
True [+0.5] $
;.
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ANSWER D.02 --(' 50)-
.
,
.True [+0.5]
.
.
REFERENCE
' 1. : SUNY: SER, NUREG-0982, p. 4-9.
. ANSWER D.03 (3.00)-
:1.- high reactor. power 2.- low coolant flow i 3. low pool water level 4. flasper valve open 5. .hig i pool / core coolant inlet temperature 6. -dry. chamber door not fully closed -
7.- loss of safety chamber high voltage Any six (6) [+0.5] sach, +3.0 maximum.- REFERENCE 1.- SUNY: SER, NUREG-0982, p. 4-10.
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. / t , ANSWERS -- STATE' UNIV...OF.NEW YORKL .-87/08/11-HVENEFELD, J.
.
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-
ANSWER :D.04 -(3.00)
'
1. .. log countrate or'startup channel . [+0.25] - for monitoring reactor power during startup _[+0.25] 2. . linear-N power or linear power channel [+0.25] - for monitoring power'[+0.25]L(from 1- W to 2 MW),L and provides signal..for ! automatic. servo control .[+0.25] ' 3. log-N power channel [+0.25] - for monitoring power [+0.25]
(from a few watts to greater than 2 MWs), and provides the 1 signal input for displaying reactor period [+0.25]
4. - . safety channels [+0.25] - provides input to two independent channels
,
-
which give the. redundancy to SCRAM the reactor in response to highpower[+0.'25] 5.: N**16 power channel-[+0.25] - for monitoring power [+0.25] (frcm about 50 KW to 2 MW) l REFERENCE 1. SUNY: SER, NUREG-0982, p. 7-2.
ANSWER _ D.05 (1.50) Those detectors that supply input to channels that must be accurate
.at relatively low power levels must be compensated for gamma radiation.. Gamma radiation is not proportional to thermal power at
-
. low power levels. At _high power levels gamma radiation is more representative of thermal power; furthermore, it is overshadowed by i the neutron flux. [+1.5] i REFERENCE !
1. SUNY: SER, NUREG-0982, p. 7-2. ) i
, 2. SUNY: OP 71, p. 1. ' .(These two references show that the conce)t is relevant to NSTF.)
Answer given is very basic and is common (nowledge.
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> ?. * LANSWERS:--STATE-l UNIV'.:OFNEWYORK -87/08/11-HUENEFELD, J.
t
'.
ANSWER; ,D.06' .(2.00)
.. < :1.: . Fast-SCRAM - by decreasing'the DC holding current '2. Slow SCRAM - by-turning off the AC power supply- , . [+1.0] each . .
l REFERENCE
._
1. SUNY:1SER, NUREG-0982s p. 7-2.
,
: ANSWER D.07 '(1.50)
1. low neutron countrate in'the startup channel
.
- 2. inoperable chart recorders log countrate, log-N or linear-N-channels- .
h.,hish,smVrd ilAlU o . ~2 ~ n ( gg, . -g REFERENCE 1. SUNY: SER, NUREG-0982, p. 7-2.
ANSWER. D.08 (1.00) By locating the' detector on the core exit line downstream of the holdup tank. :[+1.0] REFERENCE- < 1. SUNY: SER, NUREG-0982, p. 7-3.
' ANSWER D.09 (1.00) i 1.- 440 V 2.- -220 V
.3. - '110 V
[+0.33] each t
,
'I
_ . _ _ _ _ _ . _ _ _ . _ _ _ _ - - - - - - - - - -
- - -
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*
- ANSWERS -- STATE UNIV. 0F NEW YORK- .
87/08/11-HUENEFELD, J.
. REFERENCE l
!
1. SUNY: SER, NUREG-0982, p. 8-1.
l
! .
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. - - - _ _ _
,
vuess exs t y ,, W4 ;A*NSWERS - STATE UNIV. OF NEW YORK -87/08/11-HUENEFELD,J.
l<p*
p,- -
: <
\
l s LANSWER E.01 .(1.50) L . .. .
!
h (Three) are' on the neutron deck, '(one)- is under the bridge, and (one) H is' in the. hot- cell'. . -[+1.5]
,
REFERENCE.. I
' 1. ' SUNY: SER,'NUREG-0982, p. 7-3.
[:. ANSWER, E.02 (1.50)' .. Coincident Lalarms:from .the reactor bridge fixed area monitor [+0.75] ' and~the building air exhaust effluent monitor [+0.75]. REFERENCE '
.
1. SUNY: SER, NUREG-0982, p. 7-3. t I ANSWER- E.03 .(1.00) l
'(Emergency coolant replacement no longer in TS)
Building ventilation- [+1.0] REFERENCE-1. SUNY: Technical Specifications, p. 13.
ANSWER E.04 (.50) ! city water [+0.5] REFERENCE 1. SUNY: SER, NUREG-0982, p. 6-1.
_ _ _ _ ._ _ am. ; U' -dNSWERS--STATEUNIV.OF'NEWYORK -87/08/11-HUENEFELD,J.
r
. 4 .- : ANSWER. E.05; '(1.50)
1; exhaust. ducts are closed 2.
the (two) inlet. 4tnb'btwl'l'f
.
ducts and the(two)QA the (two) exhaust blowers 4stop (the 6000 ft cubed per minute-blower at the base of the stack remains in operation) i 3. 'the damper in the 6" emergency exhaust duct opens
- [+0.5]. each . REFERENCE 1. SUNY:.SER, NUREG-0.982, p. 6-2. ;
OP-28,p43 ANSWER E.06 (1.50) a.. Ajr bladders in the h'draulic system accumulators {:1.0l fo d i /w W N ( p n c % yc 4,w W [o67 b.- 10-15 minutes [+0.5] REFERENCE 1. SUNY: SER, NUREG-0982,-p. 9-1.
ANSWER E.07 (1.00)- I 5 kVA :[+1.0]
-REFERENCE 1. -SUNY: SER, NUREG-0982, p. 8-1. ;
, i
..' E. SAFETY AND EMERGENCY' SYSTEMS PAGE 34
* .. ^ ' ANSWERS -- STATE UNIV. OF NEW YORK -87/08/11-HUENEFELD, J.
i
.'
ANSWER E.08 (2.50) fire alarm systemfo 43 building exit signsEad2
' ' building evacuation alarmc 2 $ ""g '"#"4.a radiation monitors reactor building,ip!for effluent streams, tercommunication system hot to.egcell, bridgeco.r3 WrnfW dpf8//p//.C CO.'L7 --[10.S) ceCh REFERENCE 1. SUNY: SER, NUREG-0982, p. 8-1.
. ANSWER E.09 (1.00) A separate emergency generator located in the pnwer plant. [+1.0] REFERENCE 1. SUNY: SER, NUREG-0982, p. 8-1.
ANSWER E.10 (2.50) 1. control room (behind console) 2. control deck (near airlock) 3. gamma deck (near airlock) 4. neutron deck (at base of stairs) , 5. office wing 10wer hall (near machine shop) 6. office wing upper hall (near conference room) 7. fan room (basement) 8. general building evacuation (in elec equip room) Any five [+0.5], +2.5 maximum.
REFERENCE 1. SUNY: EP No. 6, p. 1.
. _ _ _ _ - _ ._ _.
__ _ _._
- om *~ ' , + .TANSWERS---STATEUNIV.OFNEWYORK -87/08/11-HUENEFELD,J.
Fp
-'%s a,.
iANSWER' F.01' .(.50)
m , False -[+0.5] ~'
. REFERENCE ,
1.' SUNY: Technical Specifications, p~. 8.. !
'ANSWERL F.02 (1.00)' .
A Control-Safety Blade-is magnetically coupled to.its drive, a Control Blade.is not.. ,[+1.0]
.
REFERENCE 1. SUNY: Technical Specifications, p. 1.
t' , t ANSWER F.03. (1.00) 1
,(B.); ' [+1.0] . ~ REFERENCE.
.1. SUNY: Technical Specifications, p._ 27.
.. ANSWER ' F.04- (1.00) j
'(B.) - [+1.0] l REFERENCE 1. SUNY: SER, NUREG-0982, p. 5-1.
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' ANSWER F.05 (1.00)
Periodic bleeding treatment solution. of[+1.0 the sy] stem and replacing some of the chemical i REFERENCE 1 i 1. 'SUNY: SER, NUREG-0982, p. 5-2.
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. .L' iNSWERS--STATEUNIV.OF-NEWYORK -87/08/11-HUENEFELD, J.
p
- . . ' ANSWER F.06 (2.00)
a. The reactor _is secured when a shutdown checklist has.been completed. -.
'
b.. The reactor is considered shutdown if.all' control-safety blades are fully. inserted, the console key is removed, and no manipulations are being conducted in the pool that could affect core reactivity.
[+1.0] each
~
REFERENCE-1. - .SUNY: Technical Sp'ecifications, p. 3.
ANSWER _F.07 (2.00) 1. in the reactor tank 2. in a beam tube
[+1.0] each REFERENCE i
1. SUNY: Technical Specifications, p. 17.
ANSWER F.08 .(1.00) Immediately backup the automatic SCRAM by pressing the console SCRAM button [+0.5]' and verify -that all rods have dropped [+0.5]. REFERENCE I 1. SUNY: OPNo.6,p.2.
ANSWER F.09 (.50) 20 seconds [+0. 5]
. REFERENCE 1. SUNY: OP No. 5, p. 2.
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ANSWER, 4F.10- (.50)
" . .True~ [+0.5]
REFERENCE'
'1. SUNY: OP No..57, p.13.-
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JANSWER: :F.11 (.50) J , L False - [+0. 5] -
. ' REFERENCE.
1. .SUNY: EP 6, p. 2.
-- ANSWER- F.12 ~(2.00)- - .
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1.- 'back'up the flow' scram, remove the key l 2. _ turn off the primary pump i
:3. turn 'off the secondary pump 4. turn off the demineralized pump 5.: verify the plenum flapper 'alve v has opened 6.. verify the rods are seated 7.- inspect the-reactor core 8.. notify the shift supervisor or senior operato'r on call '[+0;4] each REFERENCE: , 1. SUNY: EP 4, p. 3.
- ANSWER F.13 (1.00)
, Shutdown the reactor and stop the primary pump. .[+1.0)
1 ' REFERENCE i 1. SUNY:,0P No. 49, p. 6.
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m ,) ANSWER. : G.01 .'(.50) True [+0.5] ~
' REFERENCE' '1. SUNY: SER, NUREG-0982, p. 4-4.
. ANSWER l G.02 -(1.50)
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To prevent neutron streaming during irradiation. [+1.5]
' -REFERENCE 1.' SUNY: OP No. 50, Figure 1, p. 5.
ANSWER G.03 (.50) 10 ft +/- 2 ft.
REFERENCE 1. SUNY: OP No. 49,'p. 5.
ANSWER .G.04 (1.00) The tongs should be clamped and the can lowered into the water, suspending'them by the attached cord. [+1.0] REFERENCE 1. SUNY: OP No. 49, p. 5.
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' ' ANSWER' :G.05) (2.00) ' .1. . 'N**16-2. Ar**41 3.- . tramp' uranium fission products j :e '4. neutron activated duft parjiculates C :caofcv d u ay p ivd' a c & frem daiYdy va f [^0 M3 e d g g g c, f m e d ;
I '(Others accepted on a case-by-case basis.)
i REFERENCE 1. SUNY:.SER, N_UREG-0.982, p.- 11-1.
c'f-V/, y2 .- .. ANSWER -G.06 (2.50) r a. Two 250 gal SS tanks from hot cell and hot labs Two _600 gal SS tanks for LL radioactive waste One 10,000 gal mild steel tank
[+0.5] each b. they can-all be stirred [+1.0]-
REFERENCE 1. SUNY: SER, NUREG-0982, p. 11-3.
ANSWER G.07 .(1.50) The ventilation system maintains the thermal column under a slight negative pressure exhausting through a filter to the exhaust stack.
.[+1.5] REFERENCE-1. SUNY: SER, NUREG-0982, p. 10-2.
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The transfer systems are equipped with shielded containers'for
"
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@ qIne receiving be%irradiated ved'd' s m'N'
Aw&id ./urVW '
,
T . REFERENCE gfg g,,g , 1. SUNY: SER,.NUREG-0982,.p. 10-1.
,.
' ANSWER G.09 .(7.00) ,
A v$idable (floodable) .n'sepijc'e o {+he} an a thick lead shutterJ+1.0].
&. ( +de sea &.Zo pj,a mr^<dW**
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-
REFERENCE [q M N '# # -
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ANSWER' G.10 (1.50)- g W The building exhaust yses an in ine fixed filter that Sdarst be
' removed for laboratory evalu lon . [+0.75] . The'stackexhaust system uses a' fixed filter 7 (on inuous beta-gamma monitor $0.75].
i REFERENCE-
:1. --0'JNYi SER, NdRE0$s02, p. 7-3.
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U.:S. NUCLEAR REGULATORY COMMISSION
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' SENIOR REACTOR OPERATOR LICENSE EXAMINATION-
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to-DATE ADMINISTERED: 87/08/.4+ *C - EXAMINER: HUENEFELD w
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' CANDIDATE: /Ma rife VMei/ -
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ifl$@ ~ INSTRUCTIONS.TO CANDIDATE:
h- ;Use separate: paper.for the answers. Write answers on one side only.
Staple. question sheet on. top of the answer sheets. Points for each M j question are indicated.in' parentheses after the question. The passing-14y grade recuires at least 70% in each category. Examination papers will
.
4 6 bickec up six:(6) hcurs after the examination starts.
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'VALUE TOTAL ^ SCORE VALUE CATEGORY " /sno' t ;
iMhe9- 20.00.- H. REACTOR THEORY n 20.00- 20.00' I.
T .'" s RADI0 ACTIVE MATERIALS HANDLING
.qq ,
DISPOSAL AND HAZARDS 20.00: 20.f~0 J. SPECIFIC OPERATING <
,
CHARACTERISTICS I
h'H L A.9c, ik ,
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20.00' 20.00 - .
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K. FUEL HANDLING AND CORE PARAMETERS
' j
20.00 20.00 L. _ ADMINISTRATIVE PROCEDURES,
- n yy. ,y .,pgc)';jro CONDITIONS.AND LIMITATIONS
.vv.vv
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% Totals.
, Final. Grade
~; .- IAll~ work'doneonthisexamination-ismyown. I have neither given nor received aid, s
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b 2. f NRC RULES AND GUIDELINES FOR LICENSE EXAMINATION l During:the. administration of this examination the following rules apply: 1, Cheating on the' examination means an automatic denial of your application and could result.in more severe penalties. '
'
,. 2., Restroom trips are to be limited and.only one candidate at a time may-leave. You must avoid all t.ontacts with anyone outside the examination-room to avoid even-the appearance or possibility' of cheating.
3. juse black ink or dark pencil only to facilitate legible reproductions.
' ' ,
'41 ' Print your name in the blank provided on the cover sheet of the j examination. '
[ 5. ' Fill in the date on.the cover sheet of the examination (if necessary). '
,
f. Use only the. paper provided for answers. ! i l 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 oniv SLn 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.
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 OF THE VJESTION 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.
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 completin the examination.
been comp eted. This must be done after the examination has _= : _ _.
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(1) Exam' questions on top.
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.(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are part of the answer.
b. - Turniin your copy of the examination and all pages used to answer the examination questions, i c.- Turn in all scrap paper and the baler.ce of the paper that you did-not use for answering the questions.
~ . d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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H. REACTOR THEORY'-
.PAGE 2
~ , ' .. QUESTION.H.01 (1.00).
The_ solution to the inhour equation predicts that: (SELECTone) (1.0)
(A.) the STABLE' periods rcsulting from positive reactivity, ' ' compared with that resulting from an equal magnitude of negative reactivity, are equal'in magnitude M opposite in , si gn_.
(B.) the STABLE negative period 'resulting from negative reactivity is -80 seconds for all~ values of negative reactivity. !
(C.) positive values.of reactivity less than beta result in a '
unique and specific STABLE positive period.
(D.)'theresultantSTABLEperiodisdependentupontheamountof
' incremental reactivity added or subtracted rather.than on the absolute value of the reactivity in the core. i l
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QUESTION.'H.02'- (4.00)- Refer to the plot shown below. The solid line is countrate versus i
.
Ltime. The dotted line is reactor period versus tiine. Assume that the reactor. is initially critical, far above source effects and far below the point of adding heat. The times marked T1 and T2 ,
, correspond to instantaneous changes in core reactivity. Answer the
. questions below: (CONSIDER'each part separate _ly)
,
a. .The reactivity changes made at T1 and T2 are obviously of ! different signs (i.e., one positive and one negative). WHAT can you say about their relative magnitudes? l
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b '.. Assuming.that.the beta fraction was exactl would.you expect to see power (countrate) y zero, WHATdo if a small amount of negative reactivity were inserted at Time T17 (1.5) c. INSTEAD of the instan'taneous reactivity changes at T1 and- I T2 in the plot below,JASSUME that a source with a strength significant in comparison with the countrate is instantaneously positioned into the core at time T1 and instantaneously removed from the core at time T2. If the source does not' affect core reactivity, MAKE a sketch of j countrate vershs time showing the response of the reactor to the introduction and removal of the source. (l'. 5) Linear ,1 Countrate
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('Dotteditne '
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'.QUE$YION_ H.03 (1.00)
STATE two (2) reasons why pool depth is an important operational arameter when the reactor is bein p(neglect-radiological shieldinoi. g cooled by natural convection (1.0)
(*****' CATEGORY H CONTINUED ON NEXT PAGE *****)
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b: H. -REACTOR THEORY- '
PAGE 4
..'
QUESTIONEH.04' (2.00)-
: .WHAT happens to DNB' ratio (i.e., increases, decreases or remains the same) as each of the following two (2) parameters vary?
7 .a. reactor pool temperature (1.0)-
.b. reactor coolant flow- '(1.0)
QUESTION H.05.
(1.00) -
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,
luring ~ forced convection operation, grid plate holes not occupied by fuel must.be blocked by plugs, reflector elements, or experiments. WHY?
'
(1.0)
. QUESTION H.06- .
(1.50)
-WHICH startup requires the MOST cautious approach to' criticality, an approach made with a high residual power level OR a low residual'
power level? .WHY?.
(1.5)
QUESTION' H.07 (1.00)
'
WHICH one of-the following is a good approximation to the value of K effective if the value of reactivity is known: (SELECTone) (1.0) q (A.)_Keff=1+ rho.
(B.) Keff = rho - beta j (C.) Keff = 1 - rho I
(D.) .Keff = rho + beta
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QUESTI0k H.08
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The reacto -is exactly critical ith a strong source relative to ! the time se le.- WHICH curve on the graph below is best.represen . :(
.tative of th resultant rate o change of neutron population?
.
(SELECT one.)
(1.0)
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-QUESTION H.03 (2.00)
WHATtwo(2
. flux, are av)ailable to the reactor operator 7 measures of reactor power, in (2.0)
!
QUESTION H.10 (1.50) I WHAT is rod shadowing and WHAT is its significance' (1.5)
~. ' . QUESTION it.11 (2.00)
Drain lines exiting the containment building contain 24 inch
" dip legs"'to maintein conta:nment integrity. HOW much internal ;
pressure would be necessary to empty these dip legs? SHOW your ' work. (Density of water at 70 degrees F = 62.3 lb/ft cubed) (2.0) i
.(*****CATEGORYH MNTINUED ON NEXT PAGE *****)
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' REACTOR THEOR'Y- , PAGE _6.
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, .QUESTI'ON.H.12' .(2.00)L '
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. WHAT.two (2) thermal phenomenon are; assumed to result in compromising.the.. integrity of the fuel cladding?
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' QUESTION 'I 01 - (1.50)
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WHAT signals are necessary to actuate the reactor. building ventilation damper; closure = system 7. (1.5)
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QUESTION I.02 (1.50)'
-a.. WHAT. design feature allows operation of ventilation system Ldampers under power-failure conditions? (1.0)
? ' J b' HOW long will-operation of the ventilation dampers be possible?: (0.5) i
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QUESTION lI.03- ~ (2.50)
' In order to determine whether a liquid effluent may be released to: .' . the-sanitary sewer, your. Technical- Specifications require .that the -
following' relationship.be demonstrated:
,
,T '[(C +' MPC ) ~ + (C + MPC )] s 1
'
i=1 i. i .u- u < EXPLAIN this. relationship in words. (2.5) i f - QUESTION I.04 (1.00) WHY;does the irradiation tube in the Becquerel irradiation
, facility have an off-set curve? (1.0)
l QUESTION -I.05' (.50) k When initially removing an IF (isotope production facility sample) from the' core, it should remain below HOW many feet' of water for 30 minutes' . . (0,5) , J'
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< _ . QUESTION :I.06- (1.00)
A-sanyletcca 10 Wing hcid with' the tongs when it becomes i suddenly apparent that the sample is too active. WHAT should {'
'be done?,
(1.0) 1 (QUESTION' I.07~ (1.00)
,
WHAT are the two (2) Iargest sources (i.e., most ' volume) of
.
contaminated water.f, rom the reactor systems?
,
(1.0)
i
) ' QUESTION 1.08 (2.00) '
STATE iour:(4)' potential airborne radioactive waste products that may exist at your. facility.
(2.0) QUESTION I.09 (2.50)- a. ' DESCRIBE the'three (3) types of tanks that make the.
" collect-hold-sample-analyze-release" philosophy of liquid waste control possible.
(1.5) b. - HOW can you assure that samples from these tanks are representative?
(1.0)
QUESTION 'I.10 (1.50)
'
.WHAT design feature controls the release of Ar**41 from the Thermal Column?
(1.5) >
?
QUESTION 1.11 (1.50) WHAT design feature associated with the pneumatic transfer systems helps to prevent inadvertent radiation exposure of the transfer system. operator?
(1.5)
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L ' e . QUESTION. I.12 (2.00).
WHkTtwo'(2)designfeatureshelptoreduceradiationexposure when entry into the dry irradiation chamber is requirod? (2.0)
- .
QUESTION.I.13 (1.50) STATE the difference between the methods of partics. late monitoring used by the building exhaust system and the stack axhaust. system.
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(1.5) .
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- -QUESTION J.01. (1.00)
.Approximately WHAT is the combined total worth of all six (6)
control, blades?
,
(1.0)
(
. QUESTION J.02 ~(1.50)-
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a.- WHICH two (2) ~ control blades (by number) have.the greatest
'
integral rod _ worth?
(1.0) , ?b. 'Do the two (2) rods that'have the greatest INTEGRAL rod - worth also have the greatest DIFFERENTIAL rod worth? (0,5)
QUESTIONJ.03 -
-(1.00)-
- WHAT phenomenon is most responsible for the prompt negative temperature coefficient in the PULSTAR reactor?
<(1.0)
L
. QUESTION'J.04 (1.00)
Assuming isothermal, xteon fee conditions, about how much
- . reactivity is needed to go from critical below the point of adding heat up.to 2 MW7 (1.0)
QUESTION 'J.05 '(1.50)
.
The reactor is shutdown, cold, and xenon free. All rods are
-
inserted with the exception of the most reactive rod. Exper- ! iments have been loaded such that their worth is at the { maximum positive reactivity limit. Neglecting the NEGATIVE reactivity that may be inserted by the nonscramming rod or
'any experiments, and assuming your current core configuration: '
a. WHAT is the shutdown margin?
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(0.75) l b. WHAT shutdown margin is required by Technical -l Specifications? j (0.75) !
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The SUNY Safety Evaluation Report states a limit of 1.7% delta
, k/k on the combined worth of movable and unsecured experiments.
WHAT is the basis for this-limit? (1.5) i ,
!
c QUESTION J.07 (2.00) WHAT is the bases for limiting use of the fission plate,to the ! outside face of the. thermal column only? (2.0) ,
' QUESTION J.08' (2.00)
STATE four (4) of the six (6) accidents that are analyzed in SUNY's accident analysis (SER Chapter 14). (2.0)
!
QUESTION J.09 '(2.00) A very small sample of low cross-section materials is to be exposed in an'IF, positioned in an area of maximum flux.
DESCRIBE the process by which the sample is suspended in the area of peak flux. (2.0)
-
QUESTION J.10- (1.00)
'
WHY is-positioning'an IF' sample at low power more sensitive than doing so at high power?- (1.0) QUESTION J.11 (1.00) When filling the voidable tank, HOW far will pool level drop? (1.0)
, (***** . CATEGORY v CONTINUED ON NEXT PAGE *****)
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-QUESTION J.12 '(1.00)
.Should the. core become uncovered,'for whatever the reason, WHICH
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c .of.the following most closely represents the potential resultant radiation field at the. top of the tank? (SELECTone) (1.0)
-
-(A.) 10 R/hr
'i I
'(Bi).100 R/hr .
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(C.)'1000 R/hr (D.) 10,000. R/hr . -
-QUESTION. J.13- ( l' . 50)'-
STATE the automatic actions that will occur upon actuation of.the . reactor building ventilation damper closure system.
~ _
(1.5) .l QUESTION J.14' (1.00) !
Reactor pool temperature is maintained at the desired value by:
.(SELECT,one) (1,0) (A.) adjusting the ' primary-flow.
'(B.) adjusting the secondary flow.
..
-(C.) adjusting both the secondary and primary flows.
(0.) adjusting the demineralized flowrate.
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'-QUESTION J.15 (1.00) ;
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The quality of primary coolant is maintained by its attached
'
purification system. HOW is the quality of the secondary coolant ! maintained? (1.0)
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"' *' .K. IFUEL HANDLING AND CORE PARAMETERS '
PAGE 13
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QUESTION. K.01_ (1.00) lThe' uranium in'the fuel pellets is enriched in U**235 to WHAT ! percent?-(SELECTone) (1.0) , i
'(A.) 0.06%. i
:(B.)~0.6% '
!
i (C.) 6% l (D.) 60%
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QUESTION K.02 (1.00)
.The fission plate is composed of: (SELECTone) (1.0) (A.') a' zirconium-uranium alloy with no. cladding.
(B).auranium.aluminumalloywithno. cladding. .
(C.) a zirconium-uranium alloy with aluminum cladding.
(0.) a. uranium-aluminum alloy with aluminum cladding.
QUESTION. K.03 (2.00)
.
.
Fuel assemblies-are individually identifiable in two (2) ways. I STATE these two (2) wayr.. (2.0) QUESTION K.04 (.50)
~ ANSWER TRUE or-FALSE. !
!
The control' blade drives could, by design, be positioned to cover any of the spaces in the grid plate. (0.5) i i
!
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K. FUEL HANDLING AND CORE PARAMETERS
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PAGE 14
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s QUESTION K.05 (.50) ANSWER TRUE or FALSE.
'j According to the SUNY SER the scramable control blades may b'e l activated either individually or in groups of two, three, four, or five.
(0.5)- QUESTION K.06 (1.00)
'
WHAT is the maximum allowed total worth for all experiments in the core?.
(1.0)
.
QUESTION K.07 (.50) I ANSWER TRUE or FALSE.
Limiting the maximum value of reactivity of all experiments in the core absolutely guarantees that the shutdown margin and maximum excess. reactivity limits will not be exceeded.
(0.5) i QUESTION K.08 (1.50) WHAT is the bases for the Technical Specification limit of no more ! than 0.6% delta k/k for individual unsecured experiments? (1.5) {
!
QUESTION K.09 (1.50) ! i i ANSWER TRUE or FALSE.
tihere is no ~iimit for how much negative reactivity an individual secured experiment may be worth. EXPLAIN. )
(1.5) i l (***** CATEGORY K CONTINUED ON NEXT PAGE *****)
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' :K.t~ FUEL HA'NDLING'AND CORE PARAMETERS'- ;PAGE 15L !. m,
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QUESTION 7K.10 .(1.00) The reactor is shut'down'an'd:an unsecured experiment worth 0.5% delta k/kiis to be removed. . AccordingLto. Technical Specifications s the reactor must be greater than- suberitical prior- to
. performing.this. operation. . '(SELECT ~one)..
'
(1.0)-
L(A.) 2.5% t' elta k/k
,
i
!(B.).3.0%deltak/k i '(C.).3'5%. delta'k/k
.
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;y . (D.)L4.0% delta'k/kI
~:p
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[ QUESTION K.11' (1.00)
.WHAT'is the' difference:between'" Control Blade" and a " Control-
/ Safety. Blade,":as defined by Technical Specifications? (1.0)'
!
!
QUESTION! K.12 (1.00) ,
" ,
The: fission plate must be maintained at least from any
.other fissile material. (SELECT:one) (1.0) l ~ . 16 cm . 16 inches. ' . 1.6~ feet- . 1.6 meters w
QUESTION K.13 . (2.00) .
,
Fuel assemblies are shuffled to move some of the peripheral , assemblies to the center and the central-assemblies to the peri)hery. '. Assuming' that only original fuel elements remain L i in t1e core, and no net fuel addition or subtraction took
. place,.WOULD it be. safe'to assume that no. change'in core excess L reactivity took place?. EXPLAIN.
(2.0)- (
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.K.=? FUEL HANDLING AN6 CORE-PARAMETERS PAGE- 16- .s.
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-QUESTION LK.14' (1.00)
'
A control rod's DIFFERENTIAL rod worth. varies with axial posit'on in the core. This'is mostly due to:' (SELECT one) (1.0)
(A.)Lthel axial temperature gradient through the core.
(B.)lthe axial' neutron." wash out" effect caused by forced convection.
'
, (C.):the." shape" of the axial neutron flux.
(D.)'the worth of the displaced water in the rod channel.
QUESTION K.15- (1.00)
~ WHAT'is the pu'rpose of the cadmium (Cd) shield associated with i~
the Becquerel irradiation facility? (1.0)
, -QUESTION K.16' (2.00)
STATE-two'(2) of the three (3) conditions given in Technical ! Specifications Definitions that constitute " Reactor Operations." (2.0) QUESTION. K.17 (.50) ! ANSWER TRUE or FALSE. I l For more effective lateral shielding, the lower section of the reactor pool is composed of a different type of material than the upper section. (0.5) . i
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, QUESTION: K.18. (1.00)
'WHAT minimum number of' fresh' fuel assemblies will result-in an 1- " approximate critical mass? (SELECTone.)-
(1.0).
(A.) 9
~(B.) 17' l i
.(C.) 22 (D.) .27 i
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Le ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 18
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-QUESTION L.01' (1.00)
.
!
WHICH one of the following operations is performed the most. '
. frequently: a channel calibration, a channel check, or a . ~ channel test? WHY7 (1.0)-
QUESTION L.02- (.50)
. ANSWER TRUE or FALSE.
A reactor system surveillance, such as an ion chamber calibration, is classified as an " experiment" by Technical Specifications. (0.5)
-QUESTION L.03 (1.50)-
GIVE one example of a reportable occurrence as defined by Technical Specifications. (1.5) QUESTION L.04 (2.50)
. DEFINE in accordance with Technical Specifications:
a. Reactor Secured (1.0) b. Reactor Shutdown (1.5) QUESTION L.05 (1.00) When an individual is "readily available" he/she should be within i a reasonable driving time from the reactor building, i.e.,:
-(SELECTone.) (1.0) ' (A.) 15 minutes (B.) 1 hour _
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(C.-)I' hour,45 minutes (D.)'2 hours i
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' f ADMINISTRATE"fE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 19 QUESTION L.06 (1.50) ' STATE two (2) of the three (3) Technical Specification criterion 4 requiring double encapsulation of samples or experiments. (1.5) QUESTION L.07 (2.00) Special restrictions allow the irradiation of explosive mate-rial; however, irradiation of explosive material is absolutely prohibited in WHAT two (2) general locations?
(2.0)
'!
QUESTION L.08 (1.50) In accordance with Technical Specifications WHAT is the minimum staffing requirements when the reactor is operating? Include type of license required (R0/SRO) end where the individual must/ may be available.
(1.5)
,
QUESTION L.09 (3.00) STATE three (3) of the five (5) specific operations that Technical Specifications directs that shall be supervised by a senior , reactor operator. i (3.0) j i i i QUESTION L.10 (1.00) 1 Assume the reactor is at power and the reactor CCRAM annunciator annunciated, WHAT two (2) actions is the reactor operator required to do?
(1.0)
QUESTION L.11 (.50) l During a routine startup to full power WHAT is the shortest ' reactor period permissible by your operating procedures? (0.5) l (*****CATEGORYL CONTINUED ON NEXT PAGE *****) i _ _ _ . _ _ _ _ _ _ _
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L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 20
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\ l QUESTION L.12 (.50) l ANSWER TRUE or FALSE.
) The act of resetting an intrusion alarm cancels the automatic call to Public Safety. (0.5) QUESTION L.13 (1.00) According to the Emergency Plan, dilution of the building air effluents is generally conservatively estimated at greater than . (SELECT one) (1.0)
(A.) fifty fold (B.) five hundred fold (C.) one thousand fold (D.) five thousand fold QUESTION L.14 (.50)
ANSWER TRUE or FALSE.
In response to a fire alarm the reactor operator sh7ould SCRAM the Pratt dampers. (0.5)
l QUESTION L.15 (2.00) The reactor bridge radiation monitor must be taken out of service, WHAT two (2) restrictions apply to continued reactor operation? (2.0)
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___...___.....__...............___.....___........___....................___. i Et)UATION SHEET !
._.....__................................. ............_...._........._.__.. . .
'
.Where mi = m2 (density)1(velocity)3(area)3 = (density)2(velocity)2(area)2 ......... __ ................... __.______..............___......_____...... ;
KE="{2 PE = mgh PEy + KE +P V 3 3 1 = PE 2+KE2+P v22 where V = specific volume < P = Pressure
....... ____..... __.......... _ ..._................................. _____
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Q = mcp (Tout-Tin)
-
Q = UA (T ave -Tstm) Q = m(hi -h2 ) _..... ........._____............_..._...... ._............_............._.. P = Po10(SUR)(t) P = Po et /T SUR = 26.06 T = (B-p)t 1 p
....._................... ......__.........___.......____...______..........
delta K = (K,ff-1) CR3 (1.Keff1) = CR 2 (1-Keff2) CR = S/(1.Keff) !
= (1.Keffi) (1.Keff) x 100%
1-K SDM = eff2 K eff
.....................____....................__....______.__................
decay constant = in (2) = 0.693 A 1 = Ao e.(decay constant)x(t) l t t 1/2 1/2
. ......._. .............._......_..._....._............_.._._..._.........
Water Parameters Miscellaneous Conversions ! 1 gallon - 8.345 lbs 1 Curie = 3.7 x 10 10 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 1 ft 3= 7.48 gallons 1 hp = 2.54 x 103 Btu /hr 3 6 Density = 62.4 lbg/ft 1 MW = 3.41 x 10 Btu /hr - Density = 1 gm/cm 1 Btu = 778 ft-lbf I Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 l Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 f t-lbm/lbf-sec 2
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ANSWERS -- STATE UNIV. OF NEW YORK ~ -87/08/11-HUENEFELD, J.
. ANSWER, H.01. (1.00)
(C.) . [+1.0] . !
REFERENCE-1. SUNY:-NTO-T-8026, p. III-20 and Figure III-6. i ANSWER H.02- .(4.00) i a. 'The curves indicate that the reactor is critical, or nearly so,'both prior to.T1 and after T2; therefore, the magnitude of . i the reactivity changes must have been equal. [+1.0] b.. Power would almost instantly-(depending upon the number of neutron' generations) fall. to the subcritical multiplication level corresponding to the. amount of reactivity inserted.
[+1.5] c.
. Linear Countrate (Dottedline '. * 1
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is reactor .. I period) , , , , , , , , , ,
.
......~....-.....
:
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.,
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REFERENCE " 1. -SUNY: ANL-7291, pp. 391 through 394 and ANL-6701, pp. 17 i through 22.
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H. REACTOR THEORY PAGE 22
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' ANSWERS -- STATE UNIV. OF NEW YORK -87/08/11-HUENEFELD, J.
ANSWER H.03 (1.00) 1. pool height affects core pressure which in turn affects critical heat flux 2. total water volume for heat transfer i'
[+0.5] each REFERENCE ~
1. SUNY: SER, NUREG-0982, p. 4-6.
ANSWER. H.04 (2.00) a. ) emperature increases, DNBR decreases b.$flowdecreases,DNBRdecreases
[:0.5] ca:h D.ere ecaAJ j REFERENCE 1. Technical Specifications, p. 11.
ANSWER H.05 (1.00) Either one of the following accepted for full credit: [+1.0] l i 1. Not blocking the grid plate holes would allow flow to bypass
'
the fuel elements. l l 2. This would increase the relative bulk enthalpy and thus l lower the critical heat flux. ! REFERENCE 1. Technical Specifications, p. 15. ! l
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ANSWERS -- STATE UNIV. OF NEW YORK -87/08/11-HUENEFELD,J.
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p ANSWER- H.06 (1.50) An ' approach made under high residual power conditions [+0.5]. This is because of the relative increase in sensitivity of countrate for a given change in reactivity, i.e., suberitical multiplication
.affects. The high residual power causes the reactor to behave as
.
>
' though it had a very strong source, and will therefore experience a proportionally stronger prompt neutron effect caused by subcritical multiplication [+1.0].
W.d:/ amJ .;/tn- p.wW & [ed REFERENCE - gg g ga gg 1. SUNY: OP No. 5, pp. I and 2. m W/ /M y d4W A , 2. SUNY: ANL-6701, pp. 17 through 19. h I L ANSWER H.07 (1.00)
( A.) . [+1.0]
REFERENCE 1. SUNY: Interoffice Memorandum dated 6/18/85.
ANSWER H.08 (1.00)
(B.) [+10] .
I REFERENCE 1.- SU : A -6701, " Approach to Critical," p. 18.
ANSWER H.09 (2.00) 1. the N**16 power indicator 2. the core delta T or primary temperature systems (one of thesetwo)
[+1.0] each I
. , [/ p> gl b m_ __ _ _ _ _ _ _
, - , -
[ y vs.
,!: :H. REACTOR THEORY PAGE 24
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ANSWERS -- STATE UNIV. OF NEW YORK -87/08/11-HUENEFELD,J.
' REFERENCE
.
1. .SUNY: Technical Specifications, p. 11.
ANSWER H.10 (1.50)
< It is a local . suppression of neutron flux [+0.75] causing one of the ion thennal chambers power [+0.75].to read low relative to the true value of REFERENCE .
1. SUNY:. Technical Specifications, p. 21.
, ANSWER- H.11 (2.00) Pressure _ = (Density)(height) = (62.3 lb/ft cubed)(2 ft)
= 124.6 lb/ft squared = 0.87 psi A
thepressure drains. of < 1 psid would result in breaking the loop seals in
-[+2.0]
i REFERENCE 1.
SUNY: OP 81, Containment Building Leak Test. Qual Card IV.10d, p. 6. ) ANSWER H.12 (2.00) 1. departure from nucleate boiling 2. fuel centerline melting
[+1.0] each
!
REFERENCE 1. SUNY: SER, NUREG-0982, p. 4-5.
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.=
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RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 25 L* ANSWERS -- STATE UNIV. OF NEW' YORK
. -87/08/11-HUENEFELD, J.
l ANSWER I.01' (1.50) Coincident alarms from the reactor bridge fixed area monitor [+0.75]
.and the building air exhaust effluent monitor [+0.75].
REFERENCE.
1. . SUNY:'SER, NUREG-0982, p. 7-3.
ANSWER I.02 '(1.50) a. Air bladders in the hydraulic system accumulators 0' b.
& y T& th M q w 10-15 minutes h[ 1.$'u()0.5]J_7 a co
[+0.5]
REFERENCE 1. SUNY: SER, NUREG-0982, p. 9-1.
Of-7 7, pyf~ ANSWER I.03 (2.50) For each nuclide, the ratio of its concentration in the mixture to its maximum permissible concentration (Appendix B, 10CFR20) independent of the mixture is calculated [+0.75]. A similar ratio is computed for the. conglomerate of all unidentified beta-gamma emittersIAW10CFR20,AppendixB{ 5] . The sum of all of these ratios must be less than 1 [:0.75;. t should be noted that the equation as noted in Technical Specif cations is in error. The equation as written requires the concentration ratio of uniden-tified emitters to be added for each nuclide identified. 10CFR20 requires that it only be added oncef [t0.25]. REFERENCE 1. SUNY: Technical Specifications, p. 16.
ANSWER I.04 (1.00) To prevent neutron streaming during irradiation. [+1.0]
>
REFERENCE 1. SUNY: OP No. 50, Figure 1, p. 5.
_ _ __ j:p . =; l; ^
'I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE '26
. ANSWERS --' STATE. UNIV. OF NEW YORK' -87/08/11-HUENEFELD,J. -l
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l l' l ANSWER- !.05 (.50) l' 10 ft +/-'2 ft
~
REFERENCE
.1. SUNY: OP No. 49, p. 5.
. ANSWER I.06 .(1.00) The tongs should be clamped and the can lowered into the water, suspending them by the attached cord. [+1.0) REFERENCE' 1. SUNY: OP No. 49, p. 5. E ANSWER I.07 (1.00) 1. regeneration of the demineralized 2.- pump cooling
'i [+0.5] each REFERENCE 1. SUNY: SER, NUREG-0982, p. 11-3. ..
ANSWER I.08. (2.00) 1. N**16 2. Ar**41 3. tramp uranium fission products 4. neutronactivateddidtparticulates Sn.n v p ~h Sc~~y pWipm n
$
y 4 ggy (Others accepted on a case-by-case basis.)
REFERENCE 1. SUNY: SER, NUREG-0982, p. 11-1.
OP-%I sts _____._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ -
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I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 27
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ANSWERS -- STATE UNIV. OF NEW YORK -87/08/11-HUENEFELD, J.
ANSWER I.09 (2.50) a. Two 250 gal SS tanks from hot cell and hot labs Two 600 gal SS tanks for LL radioactive waste One 10,000 gal mild steel tank
[+0.5] each b. they can all be stirred -
REFERENCE 1. SUNY: SER, NUREG-0982, p. 11-3. i
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ANSWER I.10 (1.50) The ventilation system maintains the thermal column under a slight negative pressure exhausting through a filter to the exhaust stack.
[+1.5] REFERENCE 1. SUNY: SER, NUREG-0982, p. 10-2.
ANSWER I.11 (1.50) The transfer systems are equipped with shielded containers for receiving irradiated specimens. [+1.5] REFERENCE 1. SUNY: SER, NUREG-0982, p. 10-1. , ANSWER I.12 (2.00) , A voidable (floodable) nosepiece {;1.0] an thick lead shutter 0 1.0]. Q fA Auw2in h cys@j, n m rN & , REFERENCE CWJ # /. # M2 1. SUNY: SER, NUREG-0982, p. 10-1. ( py 4-/o i l l
!
)
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RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS * PAGE '28
[ ~ ANSWERS -- STATE UNIV. OF NEW YORK -87/08/11-HUENEFELD, J.
m ANSWER' I.'13 (1.50) w The building exhaust ses an i ine fixed filter that must be-T removed for laboratory v system uses a fixed tion [+0.75] . The' stack exhaust continuousbeta-gammamonitor'[+0.75]. REFERENCE'
, .1. - S'J NY; SEPs, N'JP,00 0002, p. 7 3.
OP.268, pg 2 , i i
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... .. .c 'J.- SPECIFIC OPERATING CHARACTERISTICS PAGE 29
ANSWERS'-- STATE UNIV. OF-NEW YORK -87/08/11-HUENEFELD, J.
ANSWER J.01 (1.00)
.10% delta'k/k (9.932 delta k/k) [+1.0]-
REFERENCE 1. SUNY: Reactivity loading' report, No. 140.
,
' ANSWER J.02 '(1,50) .
a.- blades 3 and 4 [+1.0] i b. yes [+0.5] REFERENCE 1. SUNY: Reactivity. loading report, No. 140.
ANSWER J.03 (1.00) j Doppler broadening of U**238 [+1.0] REFERENCE
, 1. SUNY: SER, NUREG-0982, p. 4-5.
.l l ANSWER 'J.04 (1.00) l The value of power defect is about 0.35% delta k/k. [+1.0] REFERENCE ' 1. SUNY: SER, NUREG-0982, p. 4-8.
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[" ANSWERS -- STATE UNIV. OF NEW YORK -87/08/11-HUENEFELO, J.
- - ANSWER J.05 (1.50) I a. Currently the reactor would be shutdown by about l
*h% delta k/k (8.75 - 2.63 - 2 92,- 3.0) [+0.75]. i 0.9t *7. 8 b. Tech Specs requires at least 0.5% delta k/k [+0.75].
i i
(* Note: value may change depending upon configuration.)
i
REFERENCE l
~
1. SUNY: SER, NUREG-0982, p. 4-7. -
!
2. SUNY: Reactivity Summary, Loading 140. I
!
!
ANSWER J.06 (1.50) A positive reactivity insertion of 1.7% delta k/k corresponds to the licensed maximum energy release.
REFERENCE 1. SUNY: SER, NUREG-0982, p. 4-9.
! ANSWER J.07 (2.00) This ensures that the fission plate will be used only in a very low neutron flux [+1.0) therefore limiting the power generated in the plate to a level where temperature increase will be limited and will occur slowly [+1.0]. REFERENCE I 1. SUNY: Technical Specifications, p. 18.
- ** p.,
, J. SPECIFIC OPERATING CHARACTERISTICS PAGE 31 L- ANSWERS -- S1 ATE UNIV. OF NEW YORK -87/08/11-HUENEFELD,J. I I
l l ANSWER J.08 (2.00) Any four of the below for +0.5 each.
1. rapid insertion of reactivity 2. loss of coolant 3. loss of coolant flow 4. maximum startup accident 5. fuel cladding rupture accident ; 6. experimental facility accidents
~
REFERENCE 1. SUNY: SER, NUREG-0982, p. 14-6.
i ANSWER J.09 (2.00) The sample will exhibit positive reactivity. Reactor power should be lowered by about 20% [+0.5]. During insertion the power will increase, bein be necessary [+g compensated 0.5]. for by doppler, As the IF passes throughsothenopeak rod motion flux, should power will start to drop [+0.5]. The IF is then pulled back through and suspended at the position corresponding to the highest power level on the chart recorder [+0.5]. REFERENCE 1. SUNY: OP No. 49, p. 3.
> ANSWER J.10 (1.00) There will be little, if any, prompt negative feedback from doppler to compensate for the reactivity effects of the IF. [+1.0] REFERENCE 1. SUNY: OP No. 49, p. 4.
ANSWER J.11 (1.00) about two inches [+1.0]
! - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
7m;. ,
,. .y *-
J. SPECIFIC OPERATING CHARACTERISTICS' , PAGE 32 ANSWERS'-- STATE UNIV. OF NEW YORK -87/08/11-HUENEFELD,J.
, REFERENCE 1. . SUNY: OP.48, p. 2.
I ANSWER. J.12 .(1.00)
(D. ) ' - [+1.0]
REFERENCE-
-
1. 'SUNY; EP 4, p. 2.-
. ,
ANSWER J.13 (1.50) 1. the(two)'inletductsandthe(twolexhaustductsareclosed 2.
and l osk SM the(two)exhaustblowerss>f,op[the6000ftcubedperminute
.
.
u blower at the base of the stack' remains in operation) 3. .the damper in the 6" emergency exhaust duct opens l- [+0.5]each REFERENCE 1. SUNY: SER, NUREG-0982, p. 6-2.
. ANSWER' J.14_ (1.00)
(B.) [+1.0]'
REFERENCE 1. SUNY: SER, NUREG-0982, p. 5-1.
-, ANSWER' .J.15 (1.00) Periodic bleeding of the system and replacing some of the chemical treatment solution. [+1.0] REFERENCE 1.. SUNY: SER, NUREG-0982, p. 5-2.
. _ - - - - _ _ _ _ _ - _ - - _ _ - _ _ _ _ _
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K. F0EL HANDLING AND CORE PARAMETERS PAGE 33 ;
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i ANSWERS -- STATE UNIV. OF NEW YORK -87/08/11-HUENEFELD, J.
[ ANSWER K.01 (1.00)
(C.) - [+1.0]
REFERENCE 1. SUNY: SER, NUREG-0982, p. 4-2.
j ANSWER K.02 ,(1.00) i (0.) [+1.0]
' REFERENCE 1. SUNY: SER, NUREG-0982, p. 10-2.
ANSWER K.03 (2.00) le the assembly number is engraved (in 2" high figures) on the 1 sides of the box ! l 2. notches are located on the top of the box i
[+1.0]'each REFERENCE 1. SUNY: OP No. 9, p. 2.
ANSWER K.04 (.50) True [+0.S] 4 k REFERENCE 1. SUNY: SER, NUREG-0982, p. 4-9. j i
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C ., K.= FUEL HANDLING AND CORE PARAMETERS. PAGE 34
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l , ANSWER ~ K.05 (.50).
True [+0.5] , REFERENCE
'1. SUNY: SER, NUREG-0982, p. 4-9.
I ANSWER K.06- .(1.00) ' - 3% delta k/k- [+1.0] REFERENCE 1. SUNY: SER, NUREG-0982, p. 4-8.
2. SUNY:-Technical Specifications.
ANSWER K.07 (.50)
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False. [+0.S] (The SER' states that in the event that either the shutdown margin or the maximum excess reactivity authorization ' would be exceeded by a proposed loading of experiments, these limits'would prevail..., explanation not required.)
REFERENCE 1. SUNY: SER, NUREG-0982, p. 4-8.
ANSWER. K.08 .(1.50) i The value of 0.6% for unsecured experiments was chosen to be slightly less than the value of beta effective. [+1.5) REFERENCE 1. SUNY: Technical Specifications, p. 8.
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j ANSWER' K.09 (1.50) False [+0.5]. If an experiment of very large~ negative reactivity were to be removed from the core for some reason, the result would , ' be a very large positive increase in reactivity .[+1.0]. REFERENCE l '. SUNY: Technical Specifications, p. 8.
< 2. SUNY: ANL-7291,.p. 381.
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ANSWER K.10 (1.00)
(C.) [+1.0] i REFERENCE 1. SUNY: Technical Specifications, p. 8.
ANSWER K.11 (1.00) A Control-Safety Blade is magnetically coupled to its drive, a Control Blade is not. [+1.0] REFERENCE 1. -SUNY: Technical Specifications, p. 1.
ANSWER K.12 (1.00)
(B.) [+1.0) !
REFERENCE 1.- SUNY: Technical Specifications, p. 27.
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l ANSWERS -- STATE UNIV. OF NEW YORK -87/08/11-HUENEFELD, J.
i ANSWER K.13 (2.00) No [+0.5]. Moving the fuel elements around might significantly affect core excess reactivity. This is because there may have been a net change in the macroscopic crossection for uranium, that is-- ! net fuel may have been shifted toward or away from cegions of higher potential neutron flux [+1.5]. REFERENCE 1. SUNY: OP No. 4,.p. 5.
ANSWER K.14 (1.00) ,
(C.) [+1.0]
REFERENCE 1. SUNY: Reactivity Summary Loading No.140.
ANSWER K.15 (1.00) 6 To select either thermal or full spectrum neutrons as the irradiating source. [+1.0] ' REFERENCE i 1. SUNY: OP 50, p. 2.
i ANSWER K.16 (2.00) 1. control blades installed in the core are not fully inserted 2. the console key is in the keyswitch 3. l manipulations are being conducted in the pool that could affect core react:vity Any two (2) [+1.0] cach, +2.0 maximum.
REFERENCE l
1. Technical Specifications, p. 2.
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4-L K..' FUEL HANDLING'AND CORE PARAMETERS PAGE 37 ANSWERS --fSTATE UNIV. OF NEW YORK -87/08/11-HUENEFELD, J.
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. ANSWER K.17-Q True [+0.5] ,
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REFERENCE' 1. SUNY: SER, NUREG-0982, p. 4-4.
l ANSWER K.18 -(1.00)
'(B.) [+1.0]
REFERENCE
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1. SUNY: SER, NUREG-0982, p. 4-2.
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o ,k ANSWER- L.01 (1.00) a channel check [+0.5] because it is performed every log reading [+0.5] ..
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REFERENCE 1., Technical Specifications, p. 1.
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., ANSWER L.02 (.50)
i' True [+0. 5] i
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REFERENCE 1. Technical Specifications, p. 1.
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ANSWERS -- STATE UNIV. OF NEW YORK -87/08/11-HUENEFELD, J.
! ANSWER L.03 (1.50) 1. operation in excess of a safety limit as set forth in Section 2.1 2. discovery cf a safety system setting less conservative than t the limiting setting established in the Technical l Specifications j 3. operation in violation of any condition for operation established in the Technical Specifications i 4. a safety system compor,ent malfunction or other component or system malfunction that could, or threatens to, render the 1 safety system incapable of performing its intended safety functions 5. release of fission products from a leaking fuel element 6. an uncontrolled or unplanned release of radioactive material from the restricted area of the facility in excess of applicable limits 7. an uncontrolled or unplanned release of radioactive material that results in concentrations of radioactive materials within the restricted area in excess of the limits specified in Section 3.6 8. conditions arising from natural or man-made events that affect or threaten to affect the safe operation of the facility 9. an observed inadequacy in the implementation of administrative or procedural controls that causes or threatens to cause the ) existence or development of an unsafe condition in connection with the operation of the facility Any one (1) [+1.5], +1.5 maximum.
REFERENCE ! 1. Technical Specifications 6.4, p. 34, Amendment 20.
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ANSWF" " S9TE "?.'. V Ffr 10E -87/08/11-HUENEFELD, J. !
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i i ANSWER L.04 (2.50)
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a. The reactor is secured when a shutdown checklist has been completed [+1.0]. b. The reactor is considered shutdown if all control-safety blades are fully inserted [+0.5], the console key is removed,
[+0.51 and no manipulations are being conducted in the pool that could affect core reactivity [+0.5].
REFERENCE . 1, SUNY: Technical Specifications, p. 3.
ANSWER L.05 (1.00)
(B.) [+1.0]
REFERENCE 1. SUNY: Technical Specifications, p. 3.
ANSWER L.06 (1.50) 1. excessive corrosion potential 2. sxcessive contamination potential 3. violent chemical reaction potential Any two (2) [+0.75] each, +1.5 maximum. I REFERENCE 1. SUNY: Technical Specifications, p. 17.
ANSWER L.07 (2.00) 1. in the reactor tank 2. in a beam tube
[+1.0] each
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i REFERENCE f 1. SUNY: Technical Specifications, p. 17. l
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ANSWER' L.08 -(1.50)
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1. A licensed reactor operator (RO) or a licensed senior reactor operator (SRO) shall be present in the control room.
2. Two persons must'be present, the operator in the control room and one additional person who can be reached from the control - room by telephone or intercom. ; 3. 'A licensed SR0 must be present or readily available. !
[+0.5] each REFERENCE 1. SUNY: Technical Specifications, pp. 29 and 32.
ANSWER L.09 (3.00) : i 1. fuel manipulations with > 15 fuel assemblies on the grid plate 2. experiments > 0.6 delta k/k being manipulated i 3. removal of a control blade (s) with >/- 10 fuel assemblies on the grid plate
'4. removal of shielding plugs from a beam tube 5. resumption of operation following an unscheduled shutdown ;
Any three (3) [+1.0] each, +3.0 maximum.
! REFERENCE 1. SUNY: Technical Specifications, p. 32.
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ANSWER L.10 (1.00)
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'Immediately
. SCRAM button backup]the automatic
[+0.5 and verify that all SCRAM rods haveby pressing the console dropped. [+0. 5]
REFERENCE.
1. SUNY:~OP No. 6, p. 2.
.l ANSWER L.11 '(.50) 20 seconds (+0.5) REFERENCE
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1.- :SUNY: OP No. 5, p. 2.
i ANSWER L.12 (.50) - l True [+0.5] REFERENCE i 1. SUNY: OP No. 57, p. 3. ' ANSWER L 13 (1.00)
(A.) [+1.0]
REFERENCE 1. ,SUNY: NSTF Emergency Plan, p. 13.
ANSWER L.14 (.50) False [+0.5] REFERENCE 1. SUNY: EP 6, p. 2.
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l~ r ANSWER. L.15. (2.00) The total' outage duration' must not exceed 4 hours .[+1.0]. Reactor power level may not be increased during the outage [+1.0]. REFERENCE l
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3M%- ' o o BUFFALO MATERIALS RESEARCH CENTER
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August 14, 1987 t..
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Mr. Barry Norris U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Norris:
Submission of comments on the exams of 8/10-12/87 Attached are our commen'ts on the questions / answers of the examinations
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administered at our facility on 8/10/87. There should be nothing new that was not discussed and resolved in our meeting following the exam.
There are no classes at the University from Christmas until January 25.
Is it possible to schedule an exam in the latter part of January 1988? If so, it would be for two reactor operators.
If you have any questions or problems with our comments, please do not hesitate to call us. It was pleasant working with you, and we look forward to seeing you again.
, j Yours truly, f- h Philip M. Orlosky Operations Manager amf attach.
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SUNY BUFFALO, ROTARY ROAD, BUFFALO, NEW Yt,RK 14214-TELEPHONE (716) 8312826 * EasyLink 62910144
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29 l M+' -* COMMENTS - REACTOR OPERATOR EXAMINATION A.01 If it is assumed that the source is a fixed part of the reactor system, then
.there is no~ time dependent change in reactivity. The question states that the reactor is just critical. Therefore the correct answer is C and not B as in the answer key.
A.07 The answer is correct, but may be too limited. The concept of rod shadowing could be applied to perturbation to other rod worths, flux in experiments, etc., as well as effects on ion chamber signals.
C.10 The use of the word " sensitive" is questioned. At low power, the reactivity change due to the sample loading may not be opposed by the Doppler effect.
" Hazardous" may be a better choice of word.
D.04 Use of the word " types" may cause the students to lump the channels into groups according to sensor type or other common characteristic. You could argue that the linear and log channels are of the same type.
D.07 Add to answer.that a high count rate will also cause an inhibit.
D.08 The primary water monitor does not have a significant beta sensitivity, dui., to the heavy wall thickness of the primary pipe.
E.03 According to tech-specs, the only engineered safety fixture at BMRC is the ventilation system. However, it can be argued that the containment,EPF system, waste water system, etc. are also engineered safety features.
l E.05 A number of auxiliary fans in containment shut down automatically under emergency conditions. It is better to say that all fans in containment plus the equipment room stack fan shut down under emergency conditions. l E 06 Add to answer the fact that the damper control solenoids are powered by the emergency generator during a power outage.
! E.08 Add to list: damper solenoids, monitor recorders.
F.04 Of the choices, B is the best. However, it is not a good answer. Secondary flow to the heat exchanger is constant. Flow to the cooling tower is variable, j In addition, further control can be instituted by using cooling tower fan speed. I I C.05 At our facility, N-16 in the air has never been detected. The students may l L list Cs-138 as an answer, since this is the most prevalent fission product to become airborne.
G.06a Again, the word " types" may cause a problem. The 5 tanks are all of the .:. me type and vary only in size and what drains into them.
t l 1 G.06b The word " stirred" implies some kind of paddle. " Circulated" better describes our way of mixing the contents of our tanks.
( l l l SUNY BUFFALO, ROTARY ROAD, BUFFALO, NEW YORK 14214-TELEPHONE (716) 8312826 e EasyLirA 62910144 I
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G.08 In addition to the shielded receiver box, a built-in and continuously operating radiation monitor helps ensure that the operator is not inadvertently exposed, G.10 Our present air monitoring system is more stringent than the one described i
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in the SER. Both air streams are continuously monitored and are essentially identical.
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BMRC COMMENTS ON SENIOR REACTOR OPERATOR EXAM - 8/10/87 Section H Reactor Theory 1. Question H.03, answer 2: total water volume for heat transfer.' This' answer is correct, but it should be noted that only a drastic decrease in the total water volume will have a significant effect. _In natural convection mode, the ultimate heat sink is the tank wall and biological shield and exchange with the air at the pool air interface. Small decreases in pool water volume will cause higher temperatures which to a large extent will be offset by increased convective flow.
2. Question H.06 The answer is only partially correct. The predominant factor which makes a " hot startup" more challenging is the existence of high residual gamma radiation
. levels. Even when properly adjusted, no compensated ion chamber filters out all gamma radiation response. Therefore, when performing a hot startup the neutronic signal is partially masked by a decaying and initially larger gamma signal. This makes it more difficult to perceive neutron multiplication.
3. Question H.08.
.This question is ambiguous. It is not clear whether the reactor is " exactly critical" with the source or if the reactor is critical and the source is providing additional neutrons. The candidate inquired regarding this and was told that the reactor is critical with the source. Within this context the correct answer is C, not B as indicated by the answer key. The question is also poorly worded in that the candidate is requ sted to select the correct " resultant rate of change of neutron population". As a result of what? Also, the graphs provided are of the neutron population, not the rate of change of the neutron population.
4. Question H.12.
The question and answer are based upon a statement in the SER regarding the establishment of the reactor safety limits. There are other phenomena which could compromise cladding integrity such as a waterlogging accident, dropping a heavy object on the core, severe corrosive attack, or the production of ; missiles within the core, such as by failure of an experiment. A better wording of this question would have been "in establishing the safety limits for the BMRC reactor, what two phenomena were considered to result in the loss of cladding integrity? It should also be pointed out that the two phenomena were identified by the licensee as the initial premise on which to evaluate potential cladding failures.
The subsequent calculations indicated that only the first phenomenon was significant in that it would be the first to be achieved in an accident; 1.e., we do not expect to experience centerline fuel melting at heat fluxes below the critical heat flux. The concept of fuel centerline melt is therefore somewhat of a moot point.
SUNY BUFFALO, ROTARY ROAD, BUFFALO, NEW YORK 14214-TELEPHONE (716) 8312826 * EasyLink 62910144 _ - _-____--
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-2-Section I:. . Radioactive Materials Handling, Disposal, and Hazards 1. -Question I.02.
'The answer.is not complete. There.are two design features which allow operation of the ventilargon dampers in the event of a power failure. Besides the existence of tLe accumulator / bladder system, of equal importance is the fact that the. solenoids which are used'to activate the damper are on the emergency
. generator circuit. Without this feature, we would_have hydraulic pressure but
.no way to utilize it.
~2. Question I.04.
The Becquerel irradiation tube has a bend in it to mitigate gamma as well as neutron streaming up the tube (although it is predominantly neutron).
3.. Question 1.08.
BMRC does not feel that Nitrogen 16 is a credible airborne contaminant (unlike many.Triga' reactors). A better choice for the fourth contaminant would be radon decay products, which are routinely detected. The building leak test procedure specifically addresses the existence of the radon.
! With regard to the other. contaminants, the word " duct" should be changed to " dust".
The primary detectable fission product is Cesium-138, which should be considered an acceptable alternative to " tramp Uranium Fission Products".
=4. Question I.09.
This question should have been more directly stated, such as " Describe the radioactive waste tank system, including number of tanks, purpose, size, and composition." Please note that there are no administrative restrictions which differentiate how we treat " hot" vs. " warm" waste streams. This terminology was established many years ago, and is somewhat misleading. All liquid wastes are transferred promptly'to the 10,000 gallon tank.
5. Question I.12.
An additional feature of the dry chamber which helps prevent excessive exposure to personnel is the Dry Chamber Scram. If the dry chamber door is opened while the reactor is operating. a limit switch on top of the door will initiate a slow
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scram, thus preventing inadvertent entry into the chamber while the control blades are withdrawn.
6. Question I.13.
Since-the SER was written, additional particulate monitoring capability was added to the building air exhaust monitoring system. At this time, there is no difference between the stack and building air monitors.
Section J: Specific Operating Characteristics 1. Question J.06.
BMRC feels that this is an obscure fact.
2. Question J.14.
The answer B is the best answer of those provided, but could have been better stated. One might interpret the phrase " adjusting flow" to mean to adjust the total flow rate. A better answer would be: "by partially diverting secondary cooling flow from the cooling tower via an auto-bypass valve".
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..' -3-Section K: Fuel Handling and Core Parameters 1. Question K.02.
The question and answer are legitimate and correct. However, from the standpoint of future exams, BMRC would like to point out that the fission plate has not been utilized for several years, and there are currently no procedures or approved experiments which utilize it.
2. Question K.05.
The word activated is ambiguous, and could imply " scrammed".
3. Question K.15.
We consider this to be a reasonably simple but not valid question. The purpose of the cadmium shield is of importance to the experimenter, but not the operator, to whom it is irrelevant. A better question might have addressed the safety issues relating to the shield, such as its reactivity worth or the administrative controls placed on its use or manipulation.
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! . . . .. i # Attachment 4 NRC RESOLUTION'TO FACILITY COMMENTS Question i Number Resol ut i on l BEACTOR OPERATOR EXAMINATION <
A.01 Duestion deleted since an assumption could have been made ! that the source was inserted either before~or after f criticality,'the correct answer could be B or C.
A.07 Comment accepted, will be considered in grading. )
C.10 Comment noted.
i D.04 Comment accepted, will be considered in grading.
D.07 Comment accepted, answer key modified to accept any two of the three answers. ]
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D.00 Comment not accepted, the question specifically asked'why N-16 did not affect the monitor.
E.03 Comment not accepted, the Engineered Safety Features are defined by the Technical Specifications for each facility. 1
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E.05 Comment accepted, answer key modified to require also the exhaust booster fans. Allowad as an alternate answer "all fans stop".
E.06 Comment accepted, modi f i ed answer key to require control j solenoids f or full credit.
E.08 Comment accepted, modified answer key and redistributed points. 1 F.04 Comment noted. ; G.05 Comment accepted; note that the answer key already states g that other answers would be accepted on a case-by-case basin.
G.06a Comment noted. J G.06b Comment accepted, will be considered in grading.
G.08 Comment accepted, answer key modi fied to require survey g
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meter; al so, from the examination review, an addi ti onal required answer is that the glove box is vented.
G.10 Comment accepted, answer key modified.
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NRC RESOLUTION TO FACILITY COMMENTS Question > I Number . Resol u t i on SENIOR REACTOR OPERATOR _ EXAMINATION H.03 Comment noted.
H.06 Comment noted, wila accept for' partial credit a discussion on the affects of gammas on the nuclear' instrumentation.
H.08- Question deleted since an assumption could havesbeen made that-the source was inserted either,before or after criticality, the correct answer.could be B or C.
H.12 Comment not accepted, the question specifically asked for the thermal phenomena that could compromise cladding integrity.
I.02 Comment accepted, answer key modified to require control solenoids f or full credit.
I.04 Comment accepted, will be considered in grading.
I.08 Comment accepted, answer key modified to allow radon as an i
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acceptable response. Other comment noted, will be considered in grading.
I.09 Comment noted, will be considered in grading.
I.12 Comment accepted, answer' key modified to allow any two for I full credit.
i I.13 ' Comment accepted, answer key modified.
J.06 Comment noted, the basis for limitations is required knowledge for SRO candidater.
J.14 Comment noted.
K.02 Comment noted.
K.05 Comment noted; as stated at the review, the question was clarified during the administration of the examination.
K.15 Comment noted; the SRO candidate is expected to know the af+ect of any activity within the vicinity of the reactor core, including whether or not that activity will affect the reactivity of the core.
NOTE: Many of the questions on the SRO and RO written ex ami nati on s were identical; therefore, if a comment was made about a question on one examination, the other examination was automatically modified.
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