ML20198J000
| ML20198J000 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 05/02/1986 |
| From: | Whittemore W GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | Elin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20198H967 | List: |
| References | |
| NUDOCS 8605300622 | |
| Download: ML20198J000 (80) | |
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GA Technologies Inc. P O BOX 81608 SAN DIEGO. CAUFORNI A 92138 ."' m': 9 , '! l.! I - m t 91455-3000 May 2, 1986 Mr. John ELIN U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596
Dear Mr. Elin,
During your recent visit to GA Technologies on the occasion of the R0 examination of our three Candidates, Mr. Morrill and Mr. Zwetzig asked me to offer in writing any comments I feel appropriate on the recent RO examina-tion questions and answers. Attached hereto are my com-ments which I hope will be useful. I trust you will dias tribute this material to Mr. Morrill and Mr. Zwetzig. Should you or your staff desire to discuss these or other points further, please feel free to contact me. I particularly want to thank you for this opportunity to respond. Yours since ly, d W. L. Whittemore Manager TRIGA Facility WLW/bb Attachment 8605300622 860514 PDR ADOCK 05000089 y PDR
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5/01/86 COMMENTS ON RO EXAMINATION O D l: ' ' Administered on 4/29/86 by Examiner G. Zwetzig U f " '.' l r General Comments:
- 1. The questions and expected answers are generally excellent.
- 2. Where the examiner either misunderstood or misinterpreted the intent of sections of the Training Manual or other material, I endeavored to clarify the situation.
3 In several cases, I felt the examiner expects too close a read-ing of a given procedure. For instance, when three methods to accomplish a task are listed in the Written Procedures, it should not be surprising that the operators may know several additional, also acceptable methods. In listing three as asked for, he may include one or more of these additional methods and should not be penalized.
- 4. In more than one case, a question is stated generally yet the examiner has a specific type of answer in mind -
such as from the Written Procedures. Yet the question may be answered quite correctly from knowledge of other legitimate sources such as 10CFR20, or the Training Manual. Another typical source of l this confusion is that a legitimate question is frequently 4 posed with no reference to which reactor the examiner has in mind or whether in fact the examiner intends a completely , general answer without reference to a specific TRIGA reactor. 1 The key answers, of course, indicate what source he had in mind (Mark I, Mark F. Written Procedures, Tech Specs, Training Manual, etc). However, the examinee quite properly can answer i auch a question using alternative data bases. I am concerned in such cases that the examinee may lose credit by not correctly guessing the information source he should use for his answer. In future exams, it would help all concerned if the question identifies the information source being probed by mentioning j the exact reactor, or whether the source is in an established Written Frocedure or a Training Manual. I make a major poin't of this because I was informed that the key answer and the key answer only will be accepted as correct. i No credit would be given for alternative, equally correct an-sWerS. Page 1 of 9
Question Comments A 01 (1) The official answer ignores an important additional consideration; namely, that the 19.2 cent reactivity in-sertion will lead to a steady state power level of only about 19 kilowatts from the 1-cent /kw rule of thumb. I would expect most RO candidates to include this as part of their response and label it as one of the two regions commonly experienced. Thus: b b SQ stag" d /v 1%KM S 3 <_ v t.A.b. ffW M n h l*
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( r~rtd' Y I n , , e t % 10'1 tc'* to~' la ' Is' If 5 (2) The two regions of interest in the lower power range from our training would be (1) transient period includ-ing the prompt increase, and (2) asymtotic period (or stable period), h0,6, Under (b)(3), it may be useful to the examinor to note that the description of core leakage can use words paral-1eling that for cell (inhomogeneities). In other words, the whole core can be considered a " macro" cell from which ._. -_ . neutrons. leak for. the same reason they leak from the
" micro" cell in (b)(1).
Page 2 of 9
l i , - l j Question Comments I ! B.01 Answer (c) should also accommodate the fact that an
; equally correct reason we use Erbium as the burnable
- poison in FLIP fuel is to create a large prompt negative I temperature coefficient of reactivity, a. Otherwise, the
[ two answers under (c) could apply as well to boron as a j burnable poison. I l C.02 The use in question (b) of the word " avoided" seems to us i to place undue emphasis on the effect of flux (or power) j peaking due to water filled voids. The RO candidates were told i n' lectures about in-core experiments that actually !'. need the flux peaking provided by the extra water in the { void (s). We quite well agree that strict caution and surm veillance is needed if such waterfilled holes are used
! (see Tech Specs). But to ask why they should be avoided may place more importance than required on this point. We :
I recommend that future questions on this point might be I l worded to reflect our comments on the need for concern. : C.03 Answer (a) as given does not reflect the fact that a 1/4-inch zirconium rod is inserted into the center of the ! U-ZrHx matrix. (See Page I-11 of Training Manual). Al- } though we have not actually measured the temperature in j this zirconium rod in steady state operation, it seems j reasonable that the temperature profile in the central i 1/4-inch may be a little less than in the uranium bearing j U4ZrHx matrix immediately beyond the 1/8 inch radius. , I We suggest that an equally acceptable answer would bei i ! "Along or near the fuel centerline." l ! C.07
~~
We suggest that the correct location in the Training ! Manual for this answer is p. VI-22, not p. VI-54. l D.02 We recognize that the information on (a) and.(b) are con- ' tained in the Instrumentation and Controls section of the NRC examination and that your answers are directly out of our Training Manual section on Instrumentation. But we l } hope you will recognize that another important condition required for the successful firing of the transient rod is j the availability _ o f _ t h,e a i r,s u,gply . With that in mind, I j believe you will agree that availability of transient rod : l air pressure is indeed a required condition to fire the ~ transient rod and as such can be one of the answers t (a)
; or (b). Otherwise, the question should' have been worded i something like:
"I.lsL two inte g o_ck,_ conditions..that..
Page.3.of 9
Question Comments _ _ _ _ __ _ _ _ , t D.03 Question (a). I cannot find any reference in our Training j Manual to use of a BF, counter for the Wide Range Channel input. On the contrary, there are several examples where [ reference. is . clearly made to use of a Fission Counter. ' Furthermore, a BF, detector would not work with the Camp- l belling circuit in the Wide Range Channel. Consequently, I hope you realize that the correct answer g to (a) is Fission Counter. Question (b). I regret that the Training Manual does not ; account for the present special condition in effect for i the Thermionic runs. Since 1960, and still in errect to- I day, the K1 Disable switch is active. However, for the present special experiment steady state runs at full power it has been far more important to have redundancy in the % ! Power Scrams (3 Keithley channels) than to set K1 for in-creased sensitivity and Disable at about 400 KW. When the present Thermionic test is completed we will almost cer- , tainly go back to the 400 KW Disable for K1. Meanwhile, all of the trainees are well aware that all three Keithley Channels (2 UCIC, 1 CIC) are calibrated and set to read ! 100% full power and scram at 110% full power. ! I regret this misinformation conveyed by the Training ; Manual and hope that allowance can.be made for long term but special experiments in the answers you accept. This will accommodate the actual present operation on which the examinees were trained. On this point, I might add that many special operating conditions are also in effect for special tests and are not covered in the Training Manual.- Admittedly, most of ' these are of short duration.Whereas the Thermionic test s (though they are special tests) are of. longer duration. In the future, you could improve. this question by asking the detector arrangement. for normal usual operations of Mark F. As Worded, it seems to me that the trainee has no option but to answer based on the actual present console , setup even though the key answer will penalize him. ! E . 0,1, The answer (5) is troublesome because it does not recog-nize that changing the Range Switch on Mark I will not induce a scram. Further, placing in ZERO or CALIBRATE Mode (not TEST) automatically scrams the Mark I reactor whether -you reset the SCRAM or not. (The latter is a safety feature. to assure that no one can operate the l 1-
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Page 4 of 9
Question __ Comments _ _ _ _ _ _ f E.01 (cont) An additional legitimate means to interrupt magnet power is to unplug the cable located at the drive unit on the reactor bridge. E.03 -In judging the adequacy of the answers, the examiners should be aware that the TRIGA Criticality Safeguards Committee has required far more scrams than set forth in the Technical Specifications. Trainees . Rieke and Moore j likely know at this point in time mainly those required in j the Technical Specifications. On tne other hand, Mr. Carlsness (Thermionic Engineer) is aware of many more re-quired Scrams such as those associated with: current flow, voltages, capsule pressures in several locations, gas gap pressure, etc. Since the question clearly does not specify that the an-swer must be quoted from the Technical Specifications, I suggest that the graater awareness of the actual safety l instrumentation by one candidate should not serve to pe-nalize him. i E.04 The official answer to (b) is only partly correct. All candidates know that if the reactor had been and still is in AUTOMATIC Mode when the loss of power was experienced, the regulating rod drive will not drive down automatically when the power is restored. The answer as stated is correct for MANUAL Mode, but al-lowance must be made for an answer that accommodates AUTO-MATIC operation. F.0J The official answer may not a.dequately recognize the con-fusion introduced by the word " apparent" as applied to the electrical transient scram. It is perfectly true that the RO' must seek SRO approval before restart. But another very important (maybe even more important) consideration is whether the scram is " explained" or " unexplained." Your use of the word " apparent" may have triggered consid, eration of the required action in the event of an "unexd plained" scram. F.03 The answer for (a) is exactly as presented in the Written Procedure. However, since the start of the Thermionic Test, we. have a Mark F stack monitor on line. It is
--likely-.tb u.one..or-more traince.will have. listed it as one o f.. t he.... ins t r ume n t s .. to. c he c k even though it is not. listed in.the.. Written ~ Procedures.
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Question _ __ Comments , _ F.03 (Cont) The official answer (c) confuses me. Would a completely correct answer be only " Release of Radioactivity Pro-cedure," or would it not be required to list some of the steps in this Procedure? I am well aware that theTable referenced lists as corrective action " Release of Radio-activity Procedures." But it seems a little excessive to expect a trainee to distinguish between the cases when he lists only the name of the Procedure and when he must list the components of the procedure itself. Since most of our trainees probably listed many of these steps, the credit of (0.5) points seems a little low. The next time this question (or one like it) is asked, a simple clarification could help the examinee. F.04 The question does not fit very well with the information referenced in the official answer. The referenced text discusses alternative means to shut the reactor down. ~ The exam asks a different question; nameTy, what are the available indications that the reactor has not_ shut down. This is a perfectly legitimate question, but the answer must also allow for visual inspection since the Mark I operator has only to stand and look to see that the rods have not fallen. This seems to us one of t1e perfectly legitimate indications that the rods failed to drop!!! F.05 We have a problem with the official ' answer because we train that there are several methods to interrupt the maga net current, not just the three in the Written Procedures. D o w n_s,c a l i ng,t h e Keithlel power channels and tr_igging the seismic circuit are examples of two more. It is incon-ceivable that the only correct answer is restricted to just those listed in the Written Procedures, since the Written Procedures are nowhere mentioned in the question. Clearly prudent intelligence on the part of the RO should be encouraged. F.06
~~
From the tone of the expected official answer, it is ap* parent to us that this is more properly an SRO question. You will also note with reference to the official answer _ --. . ~ ~ ~~ (c) that the Written Procedures do not exclude removal of DJrTn g ' FL I P ' ' f ue l-- t he y only , exhort the operator to
- - ~ ~ .. .. exercise, caution with respect to the flux and power peaking.
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Question Comments _ F.06 (cont). Now back to the R0 level of examination. You have postu-lated in (b) a serious operational problem in that there appears to be no normal way to shut down the reactor. Of course an emergency condition now exists even though core overheat is not a pronlem due the large Mark F reactor tank heat capacity. Surely, the first consideration would seem to be to remove the smallest number of fuel elements to effect the shut down. Thus, removal of 2 D-ring ele-ments to reduce the excess by 2 x 1.20 = $2.40 would more than shut the reactor down because the power swing of re-activity is about $2.00. (Note: Removal of the first D-ring element shuts the power level down to about 500 KW so r.o power or flux peaking is possible.) If you start removing G-ring fuel (periphery) it would require removal
~
of about 10 fuel elements (10 x 20 cents $2.00) for the shutdown.
Conclusion:
The considerations and discussion here seems much more to be,at the SRO level. Do you agree? As an RO question, you should permit removal of D-ring Mark F fuel. G.05 The official answer (b) does not recognize the equally valid limitation that prevents its use for fissionable materials. The source for this is the same reference; namely. Training Manual p. V*6. G.07 The official answer for question (a) is peculiar in that it assumes (without j ustification) that only fast neutrons emerge from the straight beam port. I insist that the examinee has proper j ustification to assume a flux of either: (1) all fast neutrons (18 nv/2.5 millirem /hr), (ii) , half fast and half thermal 25 (25/18 x 2.5 x gg3 x 2.50) millirem /hr (iii) any other energies including all thermal. g . . moat'ilkely experimentally ~13 something like
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. . .. mbu . t.' I...w.o u l.d n ' t expect an RO to know this.
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Page 7 of 9
Question _ _ _ Comments _ G.08 The wording of the question (since it mentions specifi-cally 10CFR20) is such as to trigger an answer that in-cludes~what the R0 also knows about 10CFR20 requirements, not only on what he remembers from the Written Procecures. Thus I believe one of the three immediate actions can properly be based on the requirement to notify NRC im-mediately. Of course this depends upon the magnitude of the release (but the question says "signigicant radiation release"). G.09 This is a reasonable question and the key answer is ac-ceptable except that (b)(3) should permit notification of DPIC or above. There is no reason to eliminate the APIC. G.10 The question fails to identify the Mark I reactor as the locale of the NR being examined. The key answers given are correct for Mark I. However, the exam?.ner should realize that RO candidate, Mr. Carlaness, has been per-forming NR on the Thermionic cells for the past 18 months (every 6 weeks) using the Mark F reactor. The only entry in the Mark F Written Procedures for NR is that for NR with the potentially very dangerous cryogenic (cold neutron) source. This type of cold NR work can no longer be done because all the cryogenic equipment has been decommissioned. No entry was made for NR for Ther-mionics with the Mark F reactor because of the following reasons: (1) all the NR beams are underwater as are all compon-nents of the NR rig; (ii) no need exists to cope off any areas as at Mark I because there is no external neutron beam. On the other hand, the cassettes are more radioactive than the Mark I NR cassettes. Thus Mr. Carlsness needs finger rings and must handle the cassettes (in the dark room as well as in rest of facility) with greater care to reduce personal done. Since neither the Mark F nor the Mark I reactors were men-sonable answer could also
~ ~ -
. . . logical precautib'n~s for NR~onselect ~
'Thermionic three important radio-devices in the Mark F.
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Page 8 of 9
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Typical precautions are: (1) wear finger rings, (ii) - let cassettes cool radioactively for a few minutes prior to handling, (ii) handle with care cassettes which are still signi-ficantly radioactive. (iv) warn the reactor operators and other personnel when it is necessary to carry the radioactive cassettes to the dark room. (v) reduce the purge air flow to the NR rig so as to minimize tne production and release of A. WLW/bb
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ATTACEMENT 2 RESOLUTION OF FACILITY COMMENTS ON WRITTEN EXAMINATION QUESTION RESOLUTION A.01 Based on facility terminology will accept term " transient period" as equivalent to " prompt jump". Based on Mark 1 TRIGA characteristic of "one cent per kilowatt, will also accept " steady state power at 19 kw" as a region of the curve. A.06(b) We conclude the alternate answer proposed by the licensee is equivalent to the originally proposed answer (which was based on l the facility training material) and therefore is also acceptable. B.01(c) We conclude the additional answer proposed by the licensee is l technically correct and is acceptable. l C.02(b) Based on the provisions of the facility technical specifications j (9.2.2(d)) which permit empty fuel positions in the FLIP-fueled Mark l F core under restricted conditions, we agree that some word other ! than " avoided" might have been a better choice. In the context of part (a) of the question, however, it does not appear use of the word " avoided" would significantly affect the correct answer or expected response. Since the question does not ask whether empty fuel positions are permitted, no revision to the answer key is needed. C.03(a) To reflect the fact some fuel at the facility contains a zirconium rod'along the axial centerline, the answer key will be revised to reflect the fact the maximum fuel temperature will occur along or near the fuel centerline. C.07 As discussed with the facility staff following the written examination, the correct reference is p. VI-22. D.02 As acknowledged by the licensee, this is an I&C question, drawn i from the Instrumentation section of the facility Training Manual, and the answer is taken directly from the Training Manual. If one is to argue that air is needed to fire the Transient Rod, one might as well argue electricity is also needed. We conclude the answer given in the training material is appropriate for the question and should not be revised. D.03(a) The answer key will be revised to reflect the only correct answer is Fission Counter. D.03(b) Inasmuch as the Training Manual is incorrect with respect to the current mcde of operation at the Mark F, and because the candidates i have been trained in the current mode of operation, the answer key I will be revised to reflect the current mode, i I i
t
/ s 2 ,
ATTACHMENT 2 QUESTION RESOLUTION E.01(5) Although not made clear by the ac111ty Training Manual, the answer will be revised to reflect the specific characteristics of the Mark 1 Control Console described by the licensee. The additional means for interrupting magnet power suggested by the licensee will also be included as an acceptable answer. E.03 Inasmuch as the question did not explicitly reference the Technical Specifications, half credit will be assigned,for installed Scrams not required by the Technical Specifications. E.04(b) Although not addressed in the Training Ma'nual, the answer key will be revised to reflect the action of the drive unit for the Regulating Rod when the rector is in the AUTOMATIC mode. F.01 We conclude the comment does not change the fact that the RO needs approval to restart and needs the approval from an SRO. Regarding whether the electrical transient was actual or " apparent" does not change the. answer - because this judgement must be made by the SRO. s , F.03(a) The question specifically references the 1,acility procedure and inquires regarding the immediate actions of the RO. If checking the Mark F stack monitor was an acceptable action, it should be
' included in the procedure. Inasmuch as the present answer is consistent with the question and with the written procedure, we conclude no revision to the answer key is needed.
i F.03(b) Although the facility procedurd specifically states the operator should notify the DPIC, we agree it also acceptable ~if the operator notifies a higher icvel of facility supervision and the key will be revised accordingly. 3 F.03(c) The question is designed to explore the candidates' knowledge of the procedure he should refer to in responding to 1 credible alarm condition. Therefore, merely giving ghe name of the praccJure is sufficient. However, if the candidate listed steps in that procedure, credit will be given in proportion to the completeness of the response. F.04 Contrary to the licensee's_statenent, the referenced text, in the opening sentence, gives the indications of failure of rods to Scram; and this was the basis for the question and the answer. However, we agree visual. inspection is also an acceptable indication andtheanswerwillberevisedaccording1f
4 e . 1 3 ATTACHMENT 2 4
' QUESTION RESOLUTION F.05 One of the objects of the examination is to test the candidates' i knowledge of.the immediate actions required for various upset conditions as specified in the facility procedures. On this basis, we believe the question and proposed answer are both fully acceptable. Further, even though the word " procedure" was not specifically mentioned, the intent was clear from the phrase i " List the three steps you should take". It does not state " list three steps you could take. Based on these considerations, no revision will be made to the answer. 1 i
- F.06 Based on discussions with the licensee, and consideration of the
; core characteristics of the Mark F reactor with FLIP fuel, the 1
answer will be revised to give full credit in part (b) for an answer
; stating the D-Ring, and in part (c) for an associated answer stating fuel in the D-Ring has the greatest reactivity worth.
G.05(b) Inasmuch as the question did not explicity request limitations based on the physical properties of plastic, credit will also be granted for limitations imposed by facility practices and procedures. G.07(a) The answer in the key is based en a 100% fast neutron spectrum. Full credit will also be given for other assumed spectra which include a reasonable proportion of fast neutrons and where the
- calculations are performed correctly. '
l G.08 Again, the question asks for three immediate actions to be taken in response to an emergency condition which is addressed by a , facility procedure. The procedure specifically states "if limits j of 10 CFR 20 are likely to be exceeded". The proposed answer j consists of the actions listed by the facility procedure. 1 Notification of the NRC would. clearly occur after the immediate l actions were taken to protect life and property. Accordingly, we conclude there is no basis for revising the response to this question. G.09(b) Based on the substantial equivalence of the various levels of facility supervision, the answer will be revised to also allow notification of the-APIC, as well as the PIC and DPIC. G.10 Because the proposed answer was based on the Mark 1 TRICA but this was not made clear by the question, full credit will also be allowed for correct answers based on the licensee's list of. Neutron Radiography practices for the Mark F_TRIGA. h { l
._________________s______________.
f I e U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: GA Technologies Reactor Type: TRIGA MARK I AND TRIGA MARK F Date Administered: APRIL 29, 1986 Examiner: G. ZWETZIG Candidate: A k) S W M R KEY . INSTRUCTIONS TO CANDIDATE Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at - least 70% in each category. Examination papers will be picked up six (6) hours after the examination starts.
~. Category I of Candidate's % of Value Total Score Cat. Value Category 13.5 13.5 A. Principles of Reactor Operation 15.0 15.0 B. Features of Facility Design 14.5 14.5 C. General Operating ~
., Characteristics 15.5 15.5 D. Instruments and Controls ,
12.0 12.0 E. Safety and Emergency Systems 14.5 14.5 F .' Standard & Emergency Operating Procedures 15.0 15.0 G. Radiation Control and Safety 100 TOTALS Final Grade % All work done on this examination is my own; I have neither given nor received aid. Candidate's Signature O
w un . . v.. .ic c i 3' ~_- . f = ma v = s/t Cycle efficiency = (Networr out)/(Energy in) w = mg s = Vot + 1/2 *a t 2 2, , E = mc KE = 1/2 my a = (Vf - V,)/t A = AN A = A,e' PE = agh .. yf = Y,' + a t - w = e/t ~~ 1= in2/t1/2 = 0.693/t1/2 t1/2'II*EI*1/2)I*hU ((t 1/2I*I*b)) AE = 931 am I = I ,e Q = mCpat Q = UA4 T I = I ,e-"* Pwr = W an 7 I = I,10-x/TR , 5 TYL = t.3/d P = P,10 ""(I) HVL = -0.693/u _- P=Pe* o SUR = 26.06/T SCR = 5/(1 - K,7f)' CR, = 5/(1 - K,77x) SUR = 26e/t* + (s - p)T CRj (1 - K,77)) = CR2(1 # eff2} ' T = (i*/p) & [(8 - p)/lo) M'= 1/(1 - K f7)*= CR)/CR, T = 1/(p - 8) ' ' M = (1 - K,77,)/(1 - K,77)) T = (s - p)/(19) p= 50tt = (1 - K ,ff)/K 77 ,, (Kef(-1)/Keff = gef/Kerf 1* = 10 seconds I = 0.1 seconds-I p = [(t*/(T K,77)] + [T,77 /(1 + AT)) Idjg=Id P = (reV)/(3'x 1010) , I)d; 2 =21d 2 I = oN 22 2 R/hr = (0.5 CE)/d (ceters) Water Parameters
. Miscellaneous Converifons I gal. = 8.345 lbm. -
1 gal. = 3.78 liters
- I curie = 3.7 x 1010 dps 1 kg = 2.21 lbm 1 ft3 = 7.48 gal.
Density = 62.4 lbm/f t3' I hp = 2.54 x 10 Btu /hr Density = 1 gm/cm3 1 mw = 3.41 x 10 Stu/hr Heat of vaporization = 970 8tu/lom lin = 2.54 cm Heat of fusion = 144 Stu/lbm 'F = 9/5'C + 32 I Atm = 14.7 psi = 29.9 in. Hg. *C = 5/9 (*F-32)
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= l f . j A. PRINCIPLES OF REACTOR OPERATION.
QUESTION A.01 (3.0) Given below is a recorder trace of Log N Power versus time. At time = t , there was a step increase in reactivity amounting to 0.0014 delta-k/k. (a) Sketch the recorder trace that will occur after this reactivity addition. (1.0) (b) Label the curve with the common names of two regions of the trace that occur after the reactivity change. (1.0)
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F 4 - ANSWER A.01 j ta) - Sta ble Pes-iod (0 5) ; i a t, - . - . I FRonpr Jun e (o.s) w i 4 ); - b . i. i i i i
, t0~J 10~4 10~' too got yn1 Loc Powcrt c e , c , w ,. r 3)
I i t i I (b) Prompt jump or transient period, [ stable) period, or steady state power Iat about 19 kw).
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(c) [0.0014/0.0073 = 19.2 cents. From Figure, 19.2 cents =) 30 (1 2) seconds. Ref.: Training Manual, p VI-12 and Fig. 6.4. Stephenson, pp 264 to 270 l 1 1 ~ l l 1 Page A-2 ag ,,,y'- , ,,y e- -.w- - , yy- - - , -- -y.m ,,,,,w,.,,-y w.- ,,-~w,- .,e-,ye-, .- p p -,,.v r - , < .- ---epw
l QUESTION A.02 (1.5) The figure below shows the radial neutron flux distribution for a reactor core without a reflector. Show with a dotted line on the figure how the neutron flux distribution would change if a reflector was added. Renector Core. Renector
' Without Renector 'g -~
ANSWER A.02 Renector Core. Renector D 19 (0.5)_ 9EAl ; (0,
~
,/ % .,_ / % _ s # " _
\
/ g
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\ With' i
f Renector
/ Without \
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,/
GoF.S To 2 Elio (0,5) Ref.: Training Manual, p VI-7 Page A-3 i
- l. __ .- . . . , _ _ , . . _ _ . . , _ - . - _ . . _ _ . . . . . _- . - . - - - - - - -
I e QUESTION A.03 (1.0) The figure on the lef t telow shows the radial heutron flux distribution for an un-reflected reactor alth a central control rod fully withdrawn. Usinc the figure en the right below, draw the radial neutron flux distribution icr thh condition with the central centrol rod inserted as shcwn.
}
l 11 4 Rod out Rod in . 1 ANSWER A.03
~ ,
) a P'6AA (. 0 33') !
Rod in Z E40 (0 33) BOTTOM OF ROD ( O.33) Ref.: Training Manual p VI-8 . l Page A-4
I . QUESTION A.04_ (2.0) Assene you need a beat flux at full power of 1x10 Btus/(hrft 1. , (a) in which heet transfer region in attached Figure A.04 should the reactor cptrate? (0.5) , (b) Which region should be avoided? (0,5) 4 (c) Explain y:ur answers to (a) and (b) (1.0) , .... --------,e---------,----.--------,--------------------------------------- AjijWER A.Qi (al Nucleate bo.ilar.g region, or Region II. (b) Film bciting region, er Region IV. (c) 2t 15 tapprtant to stay in the Nucleate Boiling Region to limit fuel clad temperatures which are cuch higher in the Film Boiling Region. Ref.: Trainir.g Manual, pp V!-27 to VI-29 E e 4 I fage A-5 l l
v , 9.- i . I I 'n- 1 Jn 1 Jy SINGLE PHASE 1 l PARnAl- 1 FI LM go'- CoNUECno#J l, u m45'toluNG N lRo}UNG I , I i i I .l. I wo's. I I 1 Qsr{QA , j l 1 l 5 *l g_ l l l I I T l l u . l l l l I i id- - . l I i
.l . .
i i , l I i
!.. I l 3 l l i fi l l I 10' .
I ; I . l 10 g 100 1000 { AT between the cladding and the coolant i l FtG. A.oy . Variation of heat flux with surface liquid temp. differences in a boiling system
. o O o .
'F i . I f QUESTION A.05 (1.0) (a) Why is a prompt negative temperature coef ficient of reactivity important t to the safety of reactor operations? (0.5) (b) Name two coefficients of reactivity other than the prompt temperature coefficient. (0.5) t ANSWER A.05 i (a) A prompt negative temperature coefficient of reactivity acts alaust immediately [within milliseconds) to reduce reactivity or power and thus limit the temperature developed in the fuel during reactivity excursions. (b) Bath [ Moderator) [ Delayed] temperature coefficient, and Void coefficient. Ref.: Training Manual p I-1 and pp VI-21 and VI-22 1 i i i i 1 i Page A-6
I QUESTION A.05 (1.0) (a) Why is a prompt negative temperature coefficient of reactivity important to the safety of reactor operations? (0.5) (b) Name two coefficients of reactivity other than the prompt temperature coefficient. (0.5) (a) A prompt negative t 7erature coef ficient of reactivity acts almost iamediately [within williseconds3 to reduce reactivity and thus limit the temperature developed in the fuel during reactivity excursions. (b) Bath [ Moderator) [ Delayed) temperature coefficient, and Void coefficient. t Ref.: Training Manual p I-l and pp VI-21 and VI-22 Page A-6
QUESTION A.06 (3.0) (a) Name the three effects comprising the prompt negative temperature coefficient of react vity for a Triga reactor. (0.9) (b) For each of the above effects, describe the processes which cause the reactivity change. (2.1) ANSWER A.06 (a) Cell [ Inhomogeneities), Doppler, Core Leakage. (0.33 each) (b) (1) Cell [Inhomogeneitiesl. [ Increased fuel temperature) Neutrons speeded up. Fewer thermal neutrons - therefore reduced number of
- More neutrons escape from fuel. Neutrons that escape fissions.
from fuel to surrounding water are rapidly thermalized and likely to . be captured in the water or cladding. (0.7) (2) Doppler Effect. [ Increased fuel temperature) Increased neutron spee4 gauses [ Doppler) broadening of the neutron capture resonances
~
in U'3 . Because more neutrons are captured in these resonances, fewer are available to produce fission. (0.7) (3) Core Leakage. Because more neutrons escape from the fuel because of l the Cell effect, more are available to escape from the core and diffuse into the reflector where they can be captured by the reflector or other materials. OR Core is like a large. individual cell and same processes apply to. core as a whole as to single cells. (0.7) Ref.: Training Manual, pp VI-20 and VI-21 Page A-7
OVESTION A.07 (2.0) (a) Which of the following conditions will cause Xe to have the most significant effect on reactivity? (1.0) (1) Long-term reactor operation at low power. (2) Pulse operation at a rate of one pulse a week. (3) Short-term reactor operation at high power. (4) Long-term reattor operation at high power. (b) TRUE OR FALSE. The higher the preceding operating flux, the greater will be the Xenon
- buildup following shutdown. (0.51 (c) The maximum Xenon poison effect following shutdown occurs at which of the following times: (0.5)
(1) One to two hours. _- (2) Five to seven hours. (3) Forty to sixty hours. (4) Immediately. ANSWER A.07 (a) (4) Long-term reactor operation at high power. (b) TRUE. . l l (c) (2) Five to seven hours. ' 1 Ref.: Training Manual, pp VI-23 to VI-24 1 END OF CATEGORY A PROCEED TO CATEGORY B Page A-B
1 B. FEATURES OF FACILITY DESIGN QUESTION B.01_ (3.0) . (a) Fill in the following table for the indicated types of.TRIGA fuel. (1.0) Characteristic SSHH Fuel FLIP Fuel ] Uranium Enrichment j Burnable Poison (Type) ! (b) Why is a higher Uranium enrichment used in one of these types of fuel ? 1 (1.0) (c) State at least one reason for using a burnable poison. (1.0) s (a) Characteristic SSHH Fuel FLIP Fuel e Uranium Enrichment 20% [18-22%) 70% [68-72%)
-' Burnable Poison (Type) None Erbium (b) For longer core life [about BMw-years).
(c) To keep core as large as standard Mark III reactors, OR To reduce number of poison rods needed for reactivity control. ] Ref.: Training Manual, pp I-11 and I-12, VI-45 to VI-48; Appendix B. l I I i I t Page B-1 _ . , ..~.___ .. - . , . . - . _ _ _ . _ _ . . _ _ _ . _ _ . - . _ _ _ . . _ ._ _
( QUESTION B.02 (4.0) Figure B.02 is a sketch of the Forced Pool-Water Cooling Systems (a) Identify on the sketch the components labeled C2, C4 and C9. (0.9) (b) Using the designations "NO" for normally open and "NC" for normally closed, mark the sketch to indicate the normal positions for the valves designated VI, V4, V7, V10, V13, V16, Vl9, V24 and V27. If the normal alignment is different from that shown in the Training Manual, explain. (2.7) (c) Mark the sketch to show the inlet and outlet pipes for the pool cooling water for the Mark I and Mark F TRIGAs. (0.4) ANSWER B.02 (a), (b) and (c) See attached Figure 1.20 from facility Training Manual. i Page B-2 i
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OUESTION B.03 (2.0) , (a) What is the normal air differential pressure (underpressure) specification for the Mark F reactor room ? (1.0) (b) According to the Mark F procedure, the absolute filters in the ventilation system are tiegged when the pressure difference across the fi.lters is: , (1.0) (1) 1.1 inches of water. (2) 0.5 inches of water. (3) 2.0 pounds per square inch.
^
(4) 5.0 inches of water. ANSWER B.03 (a) 0.1 to 0.2 inch of water negative pressure. I I (b) (1) 1.1 inches of water. Ref.: Written Procedures XIX, Ventilation Procedures for Mark F.
.eum.
Page B-3
QUESTION B.04 (2.0) (a) Describe the provisions for detecting water leakage from the Mark I TRIGA reactor pit. (1.0) (b) Describe the provisions f or detecting water leakage f rom the Mark F TRIGA reactor pit. (1.0) ANSWER B.04 (a) Sump is located outside bottom of reactor pit. Sump level is measured manually. Sump is also equipped with a float switch which will sound an alarm on excessive level. Can also detect level changes from level gauge on side of pit. (b) Two sump tubes are located outside reactor pit. Sump levels are sampled manually. Sumps are also equipped with float switches which will annunciate on excessive level. Can also detect level changes from level gauge on side of pit. ~ Ref.: Training Manual pp I-4 to I-7, 2-26 and 3-38; Written Procedures for Mark F, p IV-6; and Mark I, p IV-6. l Page B-4
T e QUESTION B 05 (2.0) (a) What is the source of makeup water for the Mark F TRIGA ? (1.0) (b) How is water supplied to the reactor pit from that source ? (1.0) ANSWER B.05 (a) Storage tank buried underground. (b) By portable pump and hoses. Ref.: Training Manual, p I-35. v Page B-5
f 4
. I OVESTION B.06 (1.0)
.i i Give two reasons why special care is needed when using mercury and copper in ' the vicinity of the reactor pit. 1 ANSWER ^B.06 1
'l These materials are corrosive (0.5) and they are not removed by the water treatment system (0.5). .
1 I } Ref. : Training Planual, p 1-31 , i t i 1 ( 1 1 4 I ,t i 4 1 i 4 l r j r
- \
k 4 i 1 1 1 1 Page B-6 l i
QUESTION B 07 (1.0) 1 When using the fuel handling tool to move fuel elements, why is it important l to not pull the lanyard ? ! ANSWER B.07 Pulling the lanyard can release the fuel element. Ref.: Training Manual, p I-43 END OF CATEGORY B PROCEED TO CATEGORY C Page B-7
C. GENERAL OPERATING CHARACTERISTICS DUESTION C.01 (0.5) TRUE OR FALSE: For NORMAL operation, the minimum size of the Mark F TRIGA core loaded with FLIP fuel is 100 fuel elements NOT including fuel-follower control rods. ] ANSWER C.01 } FALSE. [ Minimum size is 100 fuel elements igglydigg fuel-follower control rods. Or minimum size is 60 elements per facility management.) Ref. : Training Manual, p VI-51 Page C-1
QUESTION C.02 (2.0) (a) What is the effect on the neutrcn flux distribution of an empty fuel position within the core of the Mark F TRIGA loaded with FLIP fuel ? (1.0) (b) Give one reason why this effect should be avoided ? (1.0) ANSWER C.02 (a) A neutron flux peak occurs in the [ water-filled region) empty fuel position. (b) [The neutron flux peak causes high power to be generated in the adjoining fuel elements and this] may cause excessive fuel temperatures OR a departure from nucleate boiling. [ Note: Empty fuel positions are permittea by Technical Specifications when appropriate precautions are taken.) Ref.: Training manual, pp VI-51 to VI-54. _. \ l Page C-2
y , QUESTION C.03 (2.0) (a) During steady state operation in a uniformly loaded core with no water holes or flux traps, at what point within a f uel element (in the radial direction) will the highest fuel temperature occur? (1.0) (b) During pulse operation in a uniformly loaded core with no water holes or flux traps, at what point within a fuel element (in the radial direction) will the highest fuel. temperature occur? (1.0) ANSWER C.03 (a) Along or near the fuel centerline.
, (b) At the surface of the fuel meat, just inside the clad.
Ref.: Training Manual, Fig. 6.18 i - i i l Page C-3
T i QUESTION C.04 (1.0) What is the value of the prompt temperature coefficient of reactivity for the Mark I TRIGA ? ANSWER C.04
-9.6[110%3x10~ delta-k/k per degree C.
Ref. Training Manual, Appendix 3 s M Page C-4 L.
t QUESTION C.05 (3.0) (a) With respect te changes in fuel temperature, describe how the prompt ; temperature ccefficient of reactivtty for FLJP fuel differs from that of standard TF.lG9 fuel. (1.5) i (b) Describe the effect of this difference on the centrol cf the Mark F reactor. (1 5) t
------------- --------.--n------- .-~- .------------e ---------.-------.-s.-- ,
AWSWER C.05 (a) Pr6tpt temperature coefficient of reactivity fe' standard fuel varses , only slightly with temperature; coef ficient f or FLtP f uel is smaller at ,
; low tamperatures and increases significtntly n'th i ingreesing fuel temperature. teverage coef ficient f or f L'IP fuel over the operati;nal core temperatere range (20$C to 700'C) is coEparable tb the velte for g ,
standard core.1 (b) Mark F reactor is more responsive [less 3)cggish3 during startup with FLIP fuel be aute of tf.e lower valoe of prompt teeperature coefficient of
,. reactivity at low f uel temperatures.
Ref.: Trainity Maxasl, p VI-59 and Iest. Nc. 2, puestian 57. 4 Page C-5
1 QUESTION C.06 (2.0) , (a) for Pulse Operation, describe the relationship between prompt excess reactivity and peak power as predicted by the simple Fuchs-Nordheim Model. (0.5) i (b) Fot' Pelse Optration, describe the relationship between prompt excess reactivity and total energy release as predicted by the simple " Fuchs-Nerdheim Model. (0.51 (c) Based on the simple Fuchs-Nordhste hedel .with constant heat tapacity and ; co.nsts.7t proept temperature coefficient of reastavity: (1) What is the valus cf the prospt reactivity at the peak of a pulse? (0.5) . (2) What traction of the total fuel temperature rite has bker, achieved st the time of peak power? {0.$) ' ____________,___ ,_____..__,__ .____.____.__..________a__ m.... __________.__ , 4 ARSWER C,0A (a) Pest power is propertic6al to the square of the prompt excess reactivity. (b) Total energy release is propertiensi to ths prompt ercees reactivity. - (c) (1) Zero. (2) Abcut 501 , Ref. Tr aining Manual, pp V!+31 and 'JI-32 4 I i I 1
. . \
i 1 Page C-6 , 1
f QUESTION C,07 (1.0) (a) In what Ring (B - F) in the core of the Meck I TRIGA does a fuel element have the greatest reactivity worth compared to water ? (0,5) (b) In what Ring (B - 6) in the core of the Mark F TRIGA loaded with FLIP fuel does a fuel element have the greatest reactivity worth compared to water ? (0.5) ANSWER C.07 (a) Ring B
* (b) Ring D j
Ref.: Training Manual, p VI-54 i l l i l
- Page C-7 '
O O QUESTION C.08 (1.0) An air-filled Void Tank is positioned next to the Mark F TRIGA core. If the tank begins to leak and fills with water, the core reactivity will: (a) Decrease. (b) Initially increase, then decrease to a value less than the initial value. (c) Increase. (d) Stay the same. ANSWER C.08 (c) Increase. j Ref.: Training Manual, p VI-23 l .,i r. i , i l Page C-8
QUESTION C.09 (2.0) (a) Does the one-cent-per-kilowatt rule of thumb apply to the Mark F TRIGA loaded with FLIP fuel ? (0.5) (b) Explain your answer to (a). (1.5) ANSWER C.09 (a) No. (b) [One-cent per-kilowatt rule of thumb is based on the prompt temperature coefficient of reactivity (or alpha) of the Mark I TRIGA, which stays approximately constant with fuel temperature.] The coefficient for the i Mark F TRIGA loaded with FLIP fuel is [not constant with temperature) relatively low at low fuel temperatures, and increases [approximately linearly] with increasing fuel temperatures. Therefore, +he reactivity addition needed to increase power level is not constant over the power range, but increases with power level. Ref.: TRIGA Training Program, Test 1, Duestion 32 1 END OF CATEGORY C PROCEED TO CATEGORY D Page C-9
e ' D. INSTRUMENTS AND CONTROL 5 QUESTION D.01 (3.0) (a) For each of the three sets of Control Rod Drive light indicatiDos given below, enter a check mark to indicate whether it is a Normal or Abnor: mal indication. (0.3 each) (b) For each case, describe the Position of the DRIVE 3cq the RUD whefe possible. For Abnormal indications, 31st at least one pessible cause of the Abnormal indicatipn. (0.7 each) Part (a) l Part (b) LIGHTS - -- UP DDWN CONT /UN. NORMAL ABNORMAL > ROD & DRIVE POSIT!DNS AND/OR CAUSE - DN OFF ON l
\
0FF OFF 0FF (lamediauely after Scram) OFF: OFF ON (10 seconds after Scram) ANSWER D.01 LIGHTS l UP D0kN CONT /0M Nn9 MAL ABMORMAL POD L LRIVE FOSITE0N9 04Dff3 CAUEF ~ _ ~ ON OFF ON X- 'Drivs full'up. #cd fril 5pl t 0FF' 0FF OFF X Drive fooving dowewar.d] + betwasn upper and (Imaediately lower limits, after Scras) Rod -down. l
-._____m__.________.
OFF CFF ON X Rod stuck Abcve tvuer .Itait OR ! (to seconds Rod Drive down seit ;u nat woe kit.g.. j after Scram) , i l Training Manual, Table 2.1 ,J l i l Page 0-1 ; - . - . - - --, - ~~
-- - A
4 4 4 00ESTION D.02 (3.0) ( .a ) List two conditions that must be satisfied in order to " fire" the transient rod when the MODE switch of the Mark i TRISA is set in the Steady State or Automatic Modes. (1.0) i (b) List three conditions that must be satisfied in order to " fire
- the transient rod when the MODE switch of the Mark I TRIGA is set in the Transient Mode. (1.0) '
(c) List two conditions that aust be satisfied in order to " fire" the l transient rod when the MDDE switch of the Mark F TRIGA is set in the Steady State Mode. (1.0) 4 AWSWER D,02 l (g) Transient Rad cylinder doun. , Msgnet power to re'd drives. i (b) Magnet power to red drivaB. l -' Range Switch at 30S kw, Reactor Power below 1 kw, { i i (c) All reds and the CTR cylinder cust be down. , Th Pulse permissive switch must be an CTR position.. , + l kef.: Trainano Mace.al, pp 2+15 & 2-163 pp 2-35 & 2-36 h 1 l I I i l l 4 I l Pbgt D-2 ' _ - . . . . _ _.- . . . . . - - . . , . _ ... --,_. - ,, . . - - - -. . , , - _ - - , . - ~ - - ,
QUESTION D.03 (1.5) (a) For the Mark I TRIGA, what type of neutron detector provides the input signal to the Period Meter ? (0.5) (b) For the Mark F TRIGA, of the four neutron detector channels in the Console, which detector channels provide reliable readings (i .e. - ar e on-scale) at 100% Power ? (1.0)
. ANSWER D.03 (a) Fission Counter 3~
(b) Per the Training Material: the Fission Counter channel and the two channels using Uncompensated Ion Chambers; or the Wide Range Channel and Keithley Channels K2 and K3; or equivalent (0.33 each). Per facility management, all four channels are on-scale at full power at present time in conjunction due to irradiation of Direct Conversion Devices. Full credit for either answer. Ref.: Training Manual, pp 2-8 to 2-20; pp 2-26 to 2-37, Figs. 2.7, 2.24 & 2.25, 4 4
+
r I i Page D-3f l
l QUESTION D 04 (1.0) (a) Describe the effect of the loss of the Gamma compensating signal on the indicated power obtained from a Compensated Ionization Chamber while the reactor is critical at low power (1 watt). (0.5) (b) Describe the effect of the loss of the Gamma compensating signal if the reactor is critical at full power. (0.5) ANSWER D.04 (a) Increase in the indicated power.
; (b) Probably not detectable.
Ref.: Training Manual, p 2-40 Page D-4
QUESTION D,05 (2.0) (a) Draw a sketch of the typical thermocouple feel element, showing the number of thereoccuples and their specific lo ations. (1.0) (b) Name three instruments (meters or recorders) in the Mark I TRI6A main i console that can provide a readout of fuel temperature. (1.0) l ANSWER D.05 (a) t f a a .i I , i (b) Fuel Temperature /Startup(Log Power) Bgttr, Fuel Temperature Brigt, and Startup(Log Power) Bregtdgr. Ref.: Trainine =
., fig. 2.13; Fig. 2.7; Figs. 2.17 and 2.20 l
l l l l i I Page D-5
d (TT SOFT SOLDER , STAINLESS STEEL (: h LEAD-0UT TUBE N ya an
.(f.9fcm .DIA.) _,
y - e :.% TRIANGULAR SPACER ,, END PLUG v GRAPHITE END REFLECTOR
\
ZlRCONIUM ROD i -~ FUEL-MODERATOR 72.06cm MATERIAL ??.F gf. o 'C N ~i ( THERMOCOUPLES (< 3 V3il~~ '"> - f J M
% .f. 6 0,i A - E i 2.s4 cm og.s O '-
c.3 STAINLESS STEEL W "le
..w
, . . .U CLADDING
$$e IE.f 1 ,
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~
l? NLi ;'l ' l i
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t:
, 3.73 ,
cm Fig. 2.13. Ther:noccuple fuel ele:nent 2-23
I r
- QUESTION D.06 (2.0)
. Name four additional parameters that must be measured when fissionable ! material is irradiated in the Mark F TRIGA in an in-core electrically heated furnace ?
_____________.c...______________________________________________________________ ANSWER D.06 Internal furnace pressure, furnace electrical current, flow rate of helium purge, and furnace temperature. Ref.: Mark F Technical Specification 10.2.5 (a)(4). r i 1 j ,- S
,1 i
j i
^
i J i j i i J I l i l l Page D-6 i
. . , - . . - .,,r. .,, , r. ,-__-- ._ . . . . , _ - . , , , , , . , , - . - - - - . - , - . ~ , . - . . ,----v , . .
QUESTION D.07 (1.0) Explain why a minimum source level interlock is provided in the Mark I control rod drive withdrawal circuit. ANSWER D.07 To assure the neutron flux is sufficiently large that it can be seen on the startup channel before beginning rod withdrawal or to assure the reactor does not go critical below the range of the indicating instruments. Ref.: TRIGA Training Program, Test 1, Question 1 t END OF SECTION D PROCEED TO SECTION E Page D-7
O_UESTION D 08 (2.0) Given below is the recorder plot for calibration of a control rod at the Mark I TRIGA using the Rod Drop method. Use the attached Figure D.08 to estimate the reactivity worth of this control rod. P EE R C E M T POWE R O 2P 49 60 80 00 0 P 1. O = ; : a-A I - . _1
~~'
3 . g -; 1
. -e -q --
_. m _ 3 Z -_ .
=
C O-
-l
<n J
e .-
/ 0 0 */. Power - / kW ANSWER D.08 See attached Figure.
Ref.: Mark I Procedure IX, Control Rod Calibration END OF-CATEGORY D - PROCEED TO CATEGORY E Page D-0
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E. SAFETY AND EMERGENCY SYSTEMS OVESTION E.01 (2.0) List FIVE ways to interrupt magnet power to the Control Rods other than use of the Manual Scram. (0.4 each)
----------------------------------------------,n-----------------------------
ANSWER E.01 (0.4 for any five of the following)
- l. Open Magnet Power Supply Key Swit'ch
- 2. Open Console Power Switch
- 3. Open Console Circuit Breaker - --- - . -
- 4. Actuate Seismic Trip
- 5. Cause Percent Power Level Scrams to actuate by switching to a lower range
* (Steady State Mode) Cor by placing in TEST Mode and resetting Scram setpoint]
- 6. Reset fuel temperature Scram.sitpoints down to present fuel temperature
~
- 7. Turn off High Voltage" Supply to detectors
- 8. Disconnect cables from control rod drives.
Ref.: Training Manual, Table Figs. 2.12 and 2.22; and pp IV-6 to IV-Il and IV-15 to IV-17. i:
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25 2:
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QUESTION E.02 (1.51 (a) The Mark I TRIGA is subtritical by 60 cents with one Control Rod stuck in the fully withdrawn position. Basrd on the definition given in the facility Technical Specifications, is the reactor " shutdown" ? (0.5) (b) Explain your answer. (1.01 (a) NO. (b) To be " shutdown", the reactor must be subtritical by 6t least $1.00. . 1 Ref.: T.S. 1.1 t I i l l l 1 1 1 l l l l Page E-2 l _- - - - - . . , . - - . - . - , ~ , - - - - , - -
l ! QUESTION E.03 (1.5) A direct conversion (thermionic) device is to be irradiated in the Mark F TRIGA at a power of 10 kw; and water cooling will be used for the bus bars. Name three parameters associated with this experiment that must be reasured l ' and connected to provide automatic Scram input signals to the reactor safety system ? l ANSWER E.03 ~ Yemperature of the primary containment Tube, the bus bar cooling water flow, and the Continuous Air Monitor activity. (0.5 each). Half credit for installed scrams not required by the Technical Specifications. Ref.: T.S. 10.2.6 (f) i Page E-3
i l OUESTION E.04 (2.0) l ! (a) While operating at I t w, the Mark 1 TRIC-4 Scrams due to a loss of electric power to the Control Console. What.is the location of the Control Reds and the Centrol Rod Drives follo.ving this Scram and before power is restored to the console 9 (1.0) (b) What will occur when electric power is restored to the Console ? (1.0) ANSWEP E.04 (a) Rods will fall into ccre. Drives will remain where they were at time of scram. (b) In steady state mode, drives will drive down to bottoo limit. In AUTO mode, all drives except regulating rod will drive down to bottom limit; regulating rod will remain where at was. Ref.: Training Manual, p IV-10 l Page E-4
t QUESTION E.05 (2.0) (a) What is the Technical Specification requirement for the reactivity worth i of the control rods for the Mark I TRIGA ? (1.0) (b) How is the above requirement different for the Mark F TRIGA ? (1.0) i , ANSWER E.05 (a) As necessary to make the reactor subtritical by at least 50 cents with the most reactive rod stuck out. Half credit if they state the worth of transient rod is limited to $3.00. (b) Same as above, except if direct conversion experiments are loaded, it is t only necessary f or the reactor to be subtritical by 10 cents with the most reactive rod stuck out. Half credit if they state the worth of
- transient rod is limited to $5.50.
Ref.: Technical Specification 5.1.2 1 i - i i i t 1 i i 1 l t t t i - , a 4 i i
- Page E-5 !
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QUESTION E.06 (2.0) (a) What two monitoring systems are required by the Technical Specifications to be operable during reactor operation AND when work is done on or around the reactor core ? (1.0) (b) What action must the first system be capable of perf orming if activated ? (0.5) l (c) What action must the second system be capable of performing if activated ? (0,5) l ANSWER E.06 (a) The Area Radiation Monitoring System (ARMS) and the Continuous Air Monitor (CAM). (b)/(c) The ARMS must be capable of activating the evacuation alare. (cl/(b) The CAM must have an audible alarm capable of being heard in both reactor and control rooms,. Ref.: T.S. 5.2.3 (Mark !), 6.2.3 Mark F E
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l ( l QUESTION E.07 (1.0) l l (a) TRUE OR FALSE. i For the Mark I TRIGA, only experiments having reactivity worths greater than $2.00 need be securely located or fastened. (0.5) (b) TRUE OR FALSE. The Rod Withdrawal Prohibit (RWP) interlock is checked with the source in the core. (0.5) ANSWER E.07 (a) False. (Criterion is $1.00.) l l (b) False. (Checked with source out of core) 1 Ref.: (a) T.S. 8.2.1.c g (b) Mark i Fracedure IV, p IV-4 l l M-END OF CATEECRY E RDCEED TO CATEGORY F " Page E-7
F. STANDAFD AND Er.ERGENCY OFERATING PAOCEDURES 1 QUESTION F.01 (1.0) You are alone it, the Mark 1 Control Room and the reactor has just Scrammed from Steady State operation at 50 % power due to an apparent electrical
- t r a n s i e r,t .
1 What must yea de in order to restart the reacter and bring it back to 50% power ? ANSWER F.01 Dbtain approval (0.5) from an SRO (0.5) S Ref.: Mark I Procedure I, p 1-4 1 1 i M
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QUESTION F.02 (3.0) For Pulse Operation with the Mark 1 TRIGA: (a) What is the maximum allowable power level prior to the pulse 9 (0.5) (b) What is the required positioning of the motor-driven rods and the CTR nrior to initiating the pulse. ' (1.0) (c) What is the maximum core excess reactivity for Pulse Operation ? (0.5) (d) How due you assure the pulse does nct exceed a reactivity insertion of
$3,00 ?
(0.5) (e) How do you obtain the desired reactivity insertion ? (0.5' =
---...........--..--...........n--- .....----------------------------- - ....
(a) One kilowatt (b) Mater-driven rods: "calance2 cor.ftsuration" or equally withdrawn CTR: unfired ~ (c) $3.25 (d) Worth of CTR is 53.00 or less (e) Based on CTR calibration curve, CTP. drive is withdrawn tc positt en which will proviced destred reactivity insertton Ref.: Mark l Procedure V. p V-1 Page F-2
l CUESTION F.03 (2.0) .o You are operating the Mark F reactor in the Steady State mode when the Absolute Air Filter Channel alarms. (a) According to the facility procedure, what two other instruments do you check to verify the alarm ? (0.75) (b) If it is a valid alarm, what two individuals do you notify ?. (0.75) (c) If it is determined a release of radioactivity has occurred, what procedure do you follow ? (0.5) t A .03 (a) Continuous Air Monitor and Area Radiation Monitor (b) DPIC or above, and HP (c) " Release of Radioactivity" Procedure. If steps in procedure are given 1 ~, instead of name of procedure, assign credit of .16 each for following l (1) scram reactor, (2) secure ventilation system (includes closing inlet), and (3) perform radiation survey. Ref.: Mark F Procedure VI, Table, Item 9 I l 8 Page F-3
DUESTION F.04 (1.5) Name three indications of a failure of rods to drop following a Scram from 100% power (other than the control rod push button lights). ANSWER F.04
- 1. Failure of rod position indicators to decrease
- 2. Failure of indicated power level to decrease
- 3. Failure of fuel temperatures to decrease
- 4. Visual inspection of rod drives Ref.: Mark F Procedure VI, p VI-5 Page F-4
a QUESTION F.05 (3.0) You have confirmed that the rods have failed to drop following receipt of an automatic Scram signal. (a) titt the three steps you should take to interrupt magnet current and thereby shut down the reactor core. (1.0) (b) Why should circuit breaker power to the Console not be secured ? (1.0)
-s (c) What power source, if it was secured and did not cause reactor shutdown, should be turned back on ? (0.5) '( d ) Explain your answer to (c). (0.5)
R ANSWER F.05 (a) 1. Try the Manual Scram Bar; 2. Turn off the Magnet Power Key;
- 3. Secure Console Power. ;
(b) All indications will be lost. (c) Console Power. (d) So all power channels can be monitored. Ref.: Mark F Procedure VI, p VI-5 4 t 1 1 1 I l Page F-5 l J
b QUESTION F.06 (2.0) Due to a series of failures, it has become necessary to remove fuel elements from the core in order to shut down the reactor. (a) From what region of the core should you start fuel removal if this occurred at the Mark I TRIGA ? (0.51 (b) From what region of the core should you start fuel removal if this occurred at the Mark F TRIGA ? (0.5) (c) Explain the difference. (1.0) ANSWER F.06 (a) Central region or inner rings. (b) Outer region or periphery, or D-Ring. (c) [ Mark F is loaded with FLIP fuel and) water-gap peaking is a big consideration in the FLIP core. [Thus, if removal of fuel did not make reactor subtritical, water gap might cause adjacent fuel to overhtat.) If candidate answers D-Ring for Mark F, reason for difference is that for Mark F, fuel in D-Ring has greatest reactivity worth. Either answer acceptable. Ref.: Mark I and Mark F Procedures VI, and discussions with facility management. Page F-6
O OUESTION F.07 (1.0) (a) What is the minimum number of persons that must be present WITHIN the TRIGA Reactor Facility when one reactor is operating ? (0.5) (b) What are the minimum qualifications of these individuals if the reactor is in normal operation ? (0.5) l ANSWER F.07 (a) Two (b) One perscr. rust hold valid reactor operator's license on the reactor
; system in operation; other must be capable of initiating emergency action Ref.: Mark I and F Procedures I, Item 4.
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QUESTION F.08 (1.0) (a) What is the minimum number of persons that must be present when reactor mechanical maintenance work is to be performed ? (0.51 (b) What are the minimum qualifications for these individuals ? (0.5) ANSWER F.08 (a) Two (b) At least one must hold an NRC Senior Operator's license for tne reactor being worked on. Ref.: Mark I and F Procedures I, Item 10. END OF CATEGORY F PROCEED TO CATEGORY G Page F-8
e G. RADIATION CONTROL AND SAFETY QUESTION G.01 (1.0) (a) What is the normally permissible quarterly radiation exposure to the hands ? (0.5) (b) What is the normally permissible quarterly exposure to the whole body ? (0.5) ANSWER 6.01
, (al 18 3/4 Ren (b) 1 1/4 Rea Ref.: Training Manual, p V-29 l
l l Page 6-1
QUESTION G.02 (0.5) TRUE OR FALSE: According to f acility procedures, personnel monitoring devices of appropriate type and sensitivity shall be worn by each individual working within a :ene of radiation exceeding 3 mrem /hr. ANSWER G.02 TRUE Ref.: Training Manual, p V-27 Page G-2
OUEST!0N G.03 (1.5) A readily accessible location in the reactor room has a continuous radiation level of 3 mrem /hr, and authori:ed personnel could spend as much as eight hours per day in this area. (a) Is it required that this area be posted " CAUTION RADIATION AREA" ? (0.5) (b) Explain your answer. (1.0) ANSWER G.03 (a) Yes 1 (b) Criterion is 5 mrem in one hour or 100 mrem in five consecutive days: 3 mrem /hr x 8 hr/ day x 5 days = 120 mrem Ref.: Training Manual, p V-2 Page G-3
QUESTION G.04 (1.5) i (a) "ALARA" an abbreviation for what phrase ? (0.5) (b) What is the goal of the ALARA concept ? (1.0) l ANSWER G.04 (a) As low as reasonably achievable. (b) To keep radiation exposure to individuals and releases of radioactive l naterials as low as reasonably achievable.
, Ref.: 10 CFR 20.1 (c) l i
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Page 6-4
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i o QUESTION G.05 (2.0) l When performing in-core experiments: (a) What is the principal benefit of using plastic sample containers ? (0.5) q (b) Name two limitations of plastic sample containers. (1.0) (c) Name two radiological risks associated with experiments that have been j withdrawn following irradiation in the core. (0.5) ANSWER 6.05 (a) Very low induced radioactivity compared to other materials. 6 t ] .I (b) Cannot withstand elevated temperatures and will deteriorate when exposed- ! to high radiation doses. Will also accept limitations imposed by - facility and license, such as cannot be used for irradiation of , fissionable materials or explosives. (c) Radiation (0.25) and contamination (0.25). Ref.: Training Manual, p V-6 l 1 i I i l 1 l i 1 1 i .i 1 4 i Page G-5
i e l l QUESTION G.06 (1.5) (a) A ten Curie point source emits 2.5 MeV gammas. What is the dose rate 10' feet from the unshielded source ? (1.0) (b) For the same thickness of material, which would provide better shielding for this source: Lead or Paraffin ? (0.5) ANSWER G.06 i l (a) 6x 10 x 2.5 = 150 R/hr at,one foot. At ten feet, dose = 150/10' = 1.5 R/hr. (b) Lead 3 Ref.: Facility Training Program, Test No. 3, Question 11 & Glasstone l -' l Page G-6
a , QUESTION G.07 (2.0) (a) A neutron flux of 50 n/cm /sec is measured at the end of a straight air-filled beam port originating at the edge of the core. What is this local dose rate in mrem /hr ? (1.0) (b) A similar flux is measured at the end of a similar beam port originating near the face of a thermal column. What is this local dose rate in mrem /hr ? (1.0) ANSWER G.07 (a) Based on 100% Fast neutrons: Dese = 2.5 mrem /hr x (50/18) = 6.9 mrem /hr (1 5 %). If another sprectral mixture is assumed and stated, full credit
- if properly calculated.
(b) Thermal Neutrons: Dose = 2.5 mrem /hr x (50/670) = 0.186 mrem /hr (i 5 %) Ref.: Training Manual, Radiological Safety Study Material
)
t f I l l Page G-7.
D . e QUESTION G.08 (2.0) While operating the Mark I TRIGA, a significant radiation release occurs (believed to be in excess of limits or 10 CFR 20). (a) Name three immediate actions. (0.33 each) (b) If the radiation level is greater than 5 R/hr, what three immediate ' actions shall be taken ? (0.33 each) ANSWER G.08 (1) Shutdown Mark I, secure Mark I ventilation system, survey radiation levels in the reactor building, notify PIC and HF, evacuate personnel from reactor rooms. (b) Sound evacuation alara, shutdown reactor you are operating, and evacuate. Ref.: Mark I Procedure VII, p VII-4 iD l t Page G-8 i
o m %' t QUESTION G 09 (2.0) While irradiating a direct conversion device at the Mark F TRIGA, a ggntingggs alars is received from the cell top monitors (a) What is the probable cause of this alare ? (0.5) (b) Name three immediate actions (or changes in procedures) that the operator should undertake in response to this alare. (1.5) ANSWER G.09
* (a) Fission products in the secondary containment of the direct conversion device.
(b) 1. Evacuate reactor room.
- 2. Restrict entry to reactor room to persons wearing self-contained (and/or air-supplied) breathing apparatus.
- 3. Immediately notify DPIC or PIC (and thermionic engineer).
Ref.: Mark F Procedure XX, p XX-5 1 e l l Page G-9
O a 00ESTION G.10 (1.0) Name three radiological safety precautions that are to be taken when performing neutron radiography. ANSWER G.10 (0.33 each for three of the following) (1) High radiation areas roped off, (2) gamma rays and neutrons monitored at location of Mark I operator (and other selected areas), (3) finger rings used by those changing specimens, (4) objects monitored for induced radiation following NR operations, (5) let cassettes cool to allow radioactivity to decay, (6) treat cassettes as radioactive objects, (7) warn reactor operators when cassettes are to be carried to darkroom, (8) reduce purge air flow to
, minimize Argon-41 production, and (9) exclude any unnecessary persons.
Ref.: Mark 1 Procedure XV, p XV-1 and discussions with facility management. l
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