ML20136D608
| ML20136D608 | |
| Person / Time | |
|---|---|
| Site: | Berkeley Research Reactor |
| Issue date: | 12/06/1985 |
| From: | Pate R, Upton J NRC |
| To: | |
| Shared Package | |
| ML20136D586 | List: |
| References | |
| 50-224-OL-85-01, 50-224-OL-85-1, NUDOCS 8601060219 | |
| Download: ML20136D608 (67) | |
Text
.
l EXAMINATION REPORT i
i FACILITY LICENSEE:
Berkeley Test Reactor University of California
(
Department of Nuclear Engineering Berkeley, California 94720 t
FACILITY 00CXET NO.:
50-224 Exam Report No. 50-244/0L-85-01 t
FACILITY LICENSE NO.:.R-10 Examinations administered at the Berkeley Test Reactor, Berkeley, California.
'4//!PF Chief Examiner:
Jo ph W. Upton, J)f.'
'Date Signed Approved By:
_',r/bd
!Y
/2 f
Robe ~rt Pate,' Branch Chief Date Signed i
s
SUMMARY
l Examinations administered on November 12-13, 1985
' Written and oral examinations were administered to one R0 candidate.
The candidate passed these examinations.
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2 REPORT DETAILS 1.
EXAMINER (S)
- Joseph W. Upton, Jr.
2.
EXAMINATION REVIEW MEETING At the conclusion of the' written examination, the Examiner met with Tek H.
Lim and Mike Denton of the facility staff to review the written
-examination'and answer key. :The facility comments on the examination and answer key and the resolution of the comments are appended to this report.
3.
EXIT MEETING At the ' conclusion of the site visit,'the examiner met with a member of the facility staff to discuss the results of the examination. He was informed at this meeting that the candidate had clearly passed the oral and operating examination.
- Chief Examiner
\\
PROBLEM RESOLUTION OUESTION A.05 QUESTION A.05 The error in ANSWER A.05 was Ak should be 0.00175 as not noted in the review, but indicated in ANSWER A.04.
E was found in the grading then should be 43.8 msec.
process.
QUESTION A.06 0UESTION A.06 In the 9th line replace zero Yes, replace zero with with infinity.
infinity.
00ESTION B.03 00ESTION B.03 The figure from the material Figure B.03 (ANSWER) has provided is wrong. North is been corrected. " North has in the wrong direction, the been taken off of the figure location of the rabbit terminus and the rabbit terminus has is wrong and the location of been changed to position G22.
the control rods are wrong.
QUESTION B.04 00ESTION B.04 The indicated positions of It was agreed to accept the the control rods were wrong present position of the control in the provided material, rods which are C-10, D-1, D-10 and C-4.
QUESTION B.05 0UESTION B.05 The provided material was The QUESTION referred to wrong; the present source the source that was used is americium instead of in the reactor as described polonium.
in the documentation. No
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change in the a'nswer key.
QUESTION B.08 OVESTION B.08 The transient control rod An acceptable answer will is not as long as the others, be a shorter transient control about 10 in shorter, rod on Fiaure B.06-8 (0UESTION1,
PROBLEM RESOLUTION OVESTION C.05 0UESTION C.05 The reactivity worths of the The present values of control rods as given in the reactivity worths will be provided material are wrong.
accepted for the answer.
They are 2.5$,-2.5$, 3.2$'
and 2.7$.
QUESTION C.06 00ESTION C.06 It was noted by the candidate It was agreed to delete the while he was taking the words in the QUESTION that examination that it was not read, "and assume that your necessary to assume a reactivity answer in QUESTION C.05 for worth for the rod seeing as the total regulation-rod there was sufficient information worth was 2.0%".
The ANSWER in the provided data to calcu-then should indicate that late it as 3.6$.
the height of the curve is 360c.
QUESTION D.02 OVESTION D.02 The answer to part c. should The answer to c. has been be CLOSED.
changed to CLOSED.
QUESTION D.04 00ESTION D.04 The last bullet in the answer The answer will be modified is not correct as the transient to make this correction.
control rod would be driven into the core automatically.
QUESTION D.06.
OVESTION D.06 A 5th bullet should be added Agreed.
The 5th bullet will to state, "Provides for the be added for (+0.5) while circulation of'the water to the max credit remains at the fission-product monitor."
(+1.5).
l This wasn't in the origiaal design.
.0UESTION D.07 QUESTION D.07 1
Part c. is not correct as The answer to part c. will peak power refers only to be changed to FALSE.
the pulse mode.
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PROBLEM RESOLUTION QUESTION D.08 QUESTION D.08 4
The answer is not correct.
The answer key will be changed There is no " integrated flux to replace the words with circuit".
"the automatic insertion of the transient rod af ter 4 sec".
OUESTION D.09 00ESTION D.09 In part a. note that the fuel Either 1.4 or 1.5 in, will is 1.43 in. in diameter while be accepted for part a.
102 the cladding is 1.51 in..in
. fuel elements is not the diameter.
In part d., the loading for criticality.
present loading is 102 or 103 fuel elements.
QUESTION E.02 00ESTION E.02 The terminology problem was The " bulk-water temperature noted anc corrected during monitor" is replaced with the examination. The last
" inlet / outlet temperature paragraph on page 3-20 of the probe".
reference provided the ques-tion.
i OUESTION E.03 OUESTION E.03 There is a terminolo with the choice (d.)gy problem No change in the answer key The as (d.) is the only choice i
signal comparison occurs in possible.
the AUTO mode. Tne " steady-state mode" would refer to manual operation. The entire description in the reference is in Section 3.5.2 Steady-4 State Operation.
QUESTION E.05 00ESTION E.05 The answer should include Agreed that a 5th possible i
" lights in the reactor room".
response will be added to the answer key. The maximum credit remains the same.
,,,, _ _ ~, _.,.. - - _. _, -.
PROBLEM RESOLUTION l
OUESTION E.07 OUESTION E.07 The first answer is not correct No change to the answer key.
because pulsing or square-wave The answer is correct according operation is prevented above to Tech. Specs.
1 kW.
QUESTION F.01 OUESTION E 01 An additional response to the Agreed to add this response question is "all personnel as a 6th possible response, should have self-reading dost-
'all worth (+0.5).
The maximum meters and film badges".
credit remains at (+2.0).
OUESTION F.04 0UESTION E,_Q4 The answer to part a. should answer to a. will be be FALSE because it is only
,ed to FALSE. No change necessary to have an R0 at the console.
Part b. is diffi-cult to interpret with respect to."without any equipment /
material for experiments".
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OUESTION G.04 OUESTION G.04 There are no alarms-associated That part of answer in the with the air sampler.
' answer key will be taken out.
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U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: Berkeley Research Reactor Reactor Type: Non-Power / Triga M$kmI f-I November 12, 1935 Date Administered:
Examiner: Joe Upton Candidate: Anwar May INSTRUCTIONS TO CANDIDATE:
Print your name on the'line above marked " Candidate." The grade points available for each question are indicated within parentheses after each ques-tion. The passing grade is at least 70% in each of the seven (7) categories.
Use separate paper for your answers and write on only one (1) side of the paper, unless a specific question instructs you otherwise. Staple this quest-tion package to your answer sheets. The examination questions and answers will be picked up six (6) hours after the examination was started. Read the state-ment at the bottom of this page. When you have finished this examination, affim the statement by signing your name.
Category
% of Candidate's
% of value Total Score Cat. Value category 16 16 A.
Principles of Reactor Operation 16 16 B.
Features of Facility Design 16 16 C.
General Operating Charac-teristics 15 15 D.
Instruments and Controls 13 13 E.
Safety and Emergency i
Systems 1?
l.2--
F.
Standard & Emergency Operating Procedures 12 12 G.
Radiation Control l
Safety l
100 TOTALS l
Final Grade All work done on this examination is my own; I have neither given nor received aid.
l Candidate's Signature 1
Page 1 Berkeley Research Reactor November 12, 1985 A..
PRINCIPLES OF REACTOR OPERATION (16.0)
Roints Available For QUESTIONS A.01 and A.02, specify the letter designation of the phrase that provides the correct statement.
QUESTION A.01 It is impossible to obtain an extremely small magnitude for the reactor period for any value of negative reactivity because (1.0)
(a.) the decay rate associated with the reduction of the temperature of the fuel determines the long-term decay rate for the neutron flux.
(b.) most of the neutrons are " prompt" and hence the neutron diffusion time determines the long-term decay rate for the neutron flux.
(c.) the delayed neutron emitters with the shortest half-life determines the long-term decay rate for the neutron flux.
(d.) the delayed neutron emitter with the longest half-life determines the long-term decay rate for the neutron flux.
ANSWER A.01 (d.)
(+1.0)
Reference (s) A.01 1.
GA: Syllabus & Triga Training Manual, GA Technologies Inc.,
Reactor Kinetecs, p. 6-14.
j
-Section A Continued on Next Page-I
i Page 2 Berkeley Research Reactor November 12, 1985 Points i
Available QUESTION A.02 As the result of the fissioning of U-235 nuclei by thermal neutrons (1.0)
I (a.) fission neutrons.are produced with an initial average energy of about 0.025 MeV.
(b.) energy is released in an amount of about 200 MeV per fission event.
(c.) two (2) fission fragments are usually produced per fission event with their kinetic energies accounting for a small fraction of the energy released.
(d.) two (2) fission fragments are usually produced per fission event with Pu-239 being one of the fragments that is produced.
ANSWER A.02 (b.)
(+1.0)
Reference (s) A.02 1.
OSU: Oregon State Triga Reactor Training Manual, Volume VI, Reactor Physics. Kinetics and Trina Characteristics, December 1978, pp. VI-2 to VI-15.
2.
Reed: Reed Training Document, Technical Education Research Center-Southwest, Nuclear Technoloay.
1
-Section A Continued on Next Page-
i Page 3 Berkeley Research Reactor November 12, 1985 I
Points Available O-00ESTION A.03 If the Berkeley Research Reactor was operating at very low power levels and was increasing in power with a period of 25 sec, hcw much time would be required for the power level to increase by 2 decades?
Shan your calculational procedures.
(2.0)
ANSWER A.03 T = 25 see P/PO = 100 = e /25 (+1.0) t in 100 = t/25 t = 25 in 100
= 115 sec
(+1.0)
= 1.92 min Reference (si A.03 1.
OSU: Oregon State Triga Reactor Training Manual, Volume VI, Reactor Physics. Kinetics and Triga Characteristics," December 1978, p. VI-38.
2.
Reed: Reed Training Document, Technical Education Research Center-Southwest, Nuclear Technology, pp. 12-1.13 to 12-1.18.
3.
GA: Syllabus & Triga Training Manual, GA Technologies Inc.,
Reactor Kinetecs, pp. 6-9 to 6-12.
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-Section A Continued on Next Page-
-Page 4 Berkeley Research Reactor November 12, 1985 Points Available r.
OUESTION A.04 a.
Using the graph of the Inhour Equation in Figure A.04-5 (QUESTION), what is the reactivity in $ of the reactor under the operating conditions described in QUESTION A.03?
(0.5) b.
What is the value of k,ff for this reactor?
(1.0)
ANSWER A.04 a.
Reading from Figure A.04-5 (QUESTION),
Ak/p,ff = 0.25 $
(+0.5) b.
Using p,ff = 0.007, Ak = (0.007)(0.25) = 0.00175
(+0.5)
- Hence, k,ff = 1.00175
. (+0.5)
References (s) A.04 1.
OSU: Oregon State Triga Reactor Training Manual, Volume VI, Reactor Physics. Kinetics and Triga Characteristics, December 1978, pp. VI-39 to VI-41 and Figure 6.6.
2.
GA: Syllabus & Triga Training Manual, GA Technologies Inc.,
Reactor Kinetecs, pp. 6-12 to 6-17.
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-Section A Continued on Next Page-
Page 5 Berkeley Research Reactor November 12, 1985 Points Available OUESTION A.05 What is the effective neutron lifetime for the reactor under a.
the conditions described in QUESTION A.037 (1.0) b.
Why is there a set of curves in Figure A.04-5 (QUESTION)?
Why do they converge into one curve for large reactor periods?
(2.0)
ANSWER A.05 a.
T = t/Ak
(+0.5)
E = T Ak 4.k
= (25 sec)(0.,175)
= 4,:p dec
(+0.5) 1 For ' reactivities where Ak > p ff;Under.these conditions,1.e., p is greater than 1$,
b.
thereactorispromptcriticaT.
the positive reactor period is so small that the delayed neutrons do not have a controlling influence and the period /
reactivity relationship is governed by the " prompt neutron generation time," 1*.
The family of curves are for various values of 1*.
(+1.0)
For Ak ( p$$f,he value of 1* is immaterial.the delayed neutrons govern the effective lifetime a t
The decay constants of the delayed neutron precursors determine the effective neutron lifetime.
(+1.0)
Reference (sl A.05 l
1.
OSU: Oregon State Triga Reactor Training Manual, Volume VI, Reactor Physics. Kinetics and Triaa Characteristics, December t
l 1978, pp. VI-39 to VI-41 and Figure 6.6.
2.
GA: Syllabus & Triga Training Manual, GA Technologies Inc.,
i Reactor Kinetecs, pp. 6-12 to 6-17.,
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-Section A Continued on Next Page-t
i Page 7 Berkeley Research Reactor November 12, 1985 Points Available
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- a.
QUESTION A.06 Consider the reactor with the operating conditions described in QUESTION A.03 (25 sec period). Assume that no reactivity change i
is introduced by any motion of any control rods. Onni the power level continue to increase? If not, what power-level sequence could be anticipated? Sketch the power sequence (power versus i
time) and orovide a justification for your sketch.
(2.0) j ANSWER A.06 The power does not continue to rise (+0.5).
The average power-defect coefficient is 3 to 4 $/MW, so one can anticipate that tF.e power level would rise to about 70 kW (+0.5).
See the sketch below (+0.5).
The original reactivity of the core is 0.25 $
and hence the power level of the reactor would increase with the 25 sec period. As the power level increases, the temperature of the fuel elements would increase, which would introduce negative reactivity until the total ctivity reaches zero, at which time the period would be
. (+0.5)
(Theassumptioninthe sketch and in this justification is that the reactor periods are 4
small enough that there is no time delay between the power level change and the temperature change in the fuel; otherwise therewouldbeanovershootinthesketch.)
/s go-u GW a c twa fy fe< </ba c):
e q,,,c,, i, a /
th M~~sec per.od
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ionc. (.rb i
Reference (s) A.06 l
1.
OSU: Oregon State Triga Reactor Training Manual, Volume VI, Reactor Physics. Kinetics and Triaa Characteristics, December i
1978, pp. VI-43, VI-79 and Figure 6.16.
2.
Berkeley: Safety Analysis Renort for the University of California Berkelev Research Reactor, pp. 5 5-6.
-Section A Continued on Next Page-4 f
n c-
,, --. v
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,--,-,.-,--m-r e-.--.-
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Page 8 Berkeley Research Reactor November 12, 1985 Points Available a
OUESTION A.07 The sketch below shows how the reactivity of the core of the reactor was changed. On the second sketch below shnu the change in the neutron population that would have occurred as a result of the reactivity changes. Indicate any differences in the responses of the neutron population to the two reactivity changes.
(2.0)
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( m in) y' i
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ANSWER A.07 6
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L Reference (sl A.07 l
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GA: Syllabus & Triga Training Manual, GA Technologies Inc.,
[
Reactor Kinetecs, pp. 6-12 to 6-17.
-Section A Continued on Next Page-
Page 9 Berkeley Research Reactor November 12, 1985 Points Available For QUESTIONS A.08 and A.09, specify whether the statement is TRUE or FALSE.
QUESTION A.08 When the Berkeley Research Reactor is operating at a steady 1 MW, the heat flow across the solid-fluid interface of fuel cladding to coolant is characterized as " partial film boiling."
(0.5)
ANSWER A.08 FALSE (+0.5)
Reference (s) A.08 1.
Generic: Samuel Glasstone and Alexander Sesonske.
Nuclear Reactor Engineering. New York: P. Van Nostrand Company, Inc., 1963, pp. 379-381.
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-Section A Continued on Next Page-
Page 10 Berkeley Research Reactor November 12, 1985 Points Available OUESTION A.09 Specify whether the following statement is TRUE or FALSE.
Neutron flux is a term that describes thg " neutron cloud";
can be expressed in units of neutrons /cm -sec; and, in a reactor, varies in magnitude with location and with the energy of the neutrons being considered.
(0.5)
ANSWER A.09 TRUE
(+0.5)
Reference (s) A.12 1.
OSU: Oregon Otate Triga Reactor Training Manual, Volume VI, Reactor Physics. s'ratics and Triga characteristics, December 1978, pp. VI-5 to VI-18.
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-Section A Continued on Next Page-
Page 11 Berkeley Research Reactor Novenber 12, 1985
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Points Available 00ESTION A.10 Indicate whether each of the following statements are TRUE or FALSE.
(2.5) a.
An increasing concentration in the reactor core of Xe-135 reduces the thermal utilization factor, f and hence, the multiplication factor, k,ff, of the reactor core.
b.
The thermal-neutron microscopic absorption cross section of Xe-135 is greater than that of uranium.
c.
Xe-135 is produced both directly as a fission product and as the result of.a decay chain from other fission products.
d.
A good approximation for determining the production in a reactor core of Xe-135 is to assume that the Xe-135 is produced from the decay of Cs-135.
e.
The removal rate of Xe-135 is due to the neutron absorption rate in Xe-135 atoms and due to the radioactive decay of Xe-135 atoms.
ANSWER A.10
- a. TRUE
- b. TRUE
- c. TRUE
- d. FALSE
- e. TRUE
(+0.5each)
Reference (s) A.10 1.
Generic: General Physics Corporation. Academic Program for Nuclear Power Plant Personnel, Volume II, p. 4-144f.
2.-
GA Technologies: GA Technologies, Inc., Syllabus and TRIGA Training Manual, p. 6-25.
3.
Reed: Reed Training Document, Technical Education Research Center-Southwest, Nuclear Technology, p. 12-7.12f.
4.
OSU: Oregon State TRIGA Reactor Training Manual, Volume VI, Reactor Physics. Kinetics and TRIGA Chacteristics, December 1978, pp. VI-23 to VI-28.
- End of Section A-r L
5 Page 12 Berkeley Research Reactor November 12, 1985 B.
FEATURES OF FACILITY DESIGN (16.0)
.foints Available i
For QUESTIONS B.01 and B.02, specify the letter designation of the phrase that provides the correct statement.
QUESTION B.01 The reactor pool structure is constructed such that (1.0) 3 (a.) there is at least 10,000 ft of water in the pool.
(b.) the entire pool is lined with a welded stainless steel stucture embedded in the steel reinforced concrete shield.
l (c.) at the beam-port end the structure will provide at least 9 ft of concrete shielding.
(d.) all of the concrete 1s of a heavy type with a nominal 3
density of 3.5 g/cm,
ANSWER B.01 (c.)
(+1.0) i Reference (si B.01 1.
Berkeley: Safety Analysis Renort for the University of California Berkeley Research Reactor, pp. 3-2, 3-3 and 3-30.
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-Section B Continued on Next;Page-
I Page 13 Berkeley Research Reactor November 12, 1985 Points Available QUESTION B.02 j
The Nitrogen-16 Diffuser is designed to (1.0)
(a.) remove the oxygen from water above the core and thereby reduce the N-16 radiation level at the pool surface.
J (b.) increase the transport time for the N-16 from the top of the core to the pool surface.
(c.) break up the gas bubbles of 0-16 and thereby reduce the probably of forming N-16.
(d.) provide a 20 gpm stream of pool water taken from the return flow of the Water Cooling and Purification System and angled downward above the top of the core shroud.
t ANSWER B.02 (b.)
(+1.0)
Reference (s) B.02 1.
Berkeley: Safety Analysis Renort for the University of California Berkelev Research Reactor, p. 3-31.
QUESTION B.03 DIAu a skematic of the upper grid plate as it appears when viewed from above. Shnu on the skematic the address / grid labeling used for the location of the holes. Indicate on the skematic the direction to the exposure room, the location of the rabbit terminus and the locations of the small neutron source holders.
(2.0)
ANSWER B.03 SeeFigure5.03(ANSWER).
(+2.0)
Reference (s) B.03
.1.
Berkeley: Safety Analysis Renort for the University of California Berkelev Research Reactor, Figure 3-12.
-Section B Continued on Next Page-
Page 14 Berkeley rch a
Answer B.03 (Contd)
Av e
a Ce nt ral Removable Thimble He xagonal Section Irradiatio 5-Locattort O
[Tradiation Space 8
e 180 0
8 G
'e O
g1 O
Source 8
hhe O=-
Syst (Ra bi )
Elems t l
In or Te rmir is Exposure Room Transient P)d
.4o h Figure B.03 (ANSWER)
(M111 18C)
-Section 8 Continued on Next Page-
Page 15 Berkeley Research Reactor-November 12, 1985 Points Available
+
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00ESTION B.04 Soecify the location of the four (4) control rods; the regulating rod, the transient rod, the shim rod and the safety rod. Soecify the addresses / grid labels or indicate the locations on the skematic of QUESTION B.03.
(2.0)
ANSWER B.04 See Figure B.03 (ANSWER), or Regulating rod N C ~'#
Shim rod DarD U-8
(+0.5each)
Safety rod CP90 A ~'O Transient rod C-4 Reference (s) B.04 1.
Berkeley: Safety Analysis Reoort for the University of California Berkeley Research Reactor, p. 3-12 and Figure 3-12.
-Section B Continued on Next Page-l l
Page 16 Berkeley Research Reactor November 12, 1985 Points Available QUESTION B.05 The following parts of this ouestion refer to the initial neutron source that was used in the Berkeley Research Reactor, Describe the operation of the neutron source; i.e., provide a.
the atomic equations for the nuclear interactions and/or radioactive-decay, and provide the associated half-life (order of magnitude) for any radioactive decay processes.
(1.5) b.
If the original strength of the source was 10 curies, what was the original strength of the neutron source in neutrons per second?
(1.0)
ANSWER B.05 210 206 a.
Po
> a + Pb
(+0.5)
A-7 t1/2 = 138 days
(+0.5)
[/
Be9+a ----------------> (12 + n
(+0.5) 10 l
b.
1 C1 = 3.7 x 10 dps II neutron-source strength = 3.7 x 10 n/sec
(+1.0)
Reference (s) B.05 1.
Berkeley: Safety Analysis Reoort for the University of California Berkeley Research Reactor, p. 3-25.
3 I
-Section B Continued on Next Page-
,n--
,,.,. - ~ -. - -.
Page 17 Berkeley Research Reactor November 12, 1985 Points Available
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~-
00ESTION B.06 Shown in Figure B.06-8 (QUESTION) are the relative elevations of the safety plate, the lower grid plate and the upper grid plate. Also shown is a representative fuel element.
a.
Sketch another fuel element on Figure B.06-8 (QUESTION) showing the locations of the different materials within a fuel element can and soecify the different materials.
(1.0) b.
Shan on your sketch of the fuel element the dimension for the fuel length. Also orovide the length between the upper and lower grid plates. Provide /show your two (2) answers in inches.
(1.0) i
, c.
What is the weight in 1bs of a fuel element?
(0.5) l ANSWER B.06 a.
See Figure B.06-8 (ANSWER).
(+1.0)'
b.
See Figure B.06-8 (ANSWER) where the fuel length is 15 in.
(+0.5) and the grid-plate spacing is 27 in. (+0.5).
c.
The weight is 7.5 lbs.
(+0.5for6to9lbs)
Reference (s) B.06 1.
Berkeley: Safety Analysis Renort for the University of California Berkeley Research Reactor, Figures 3.5, 3.6.
I
-Section B Continued on Next Page-
Page 18 Berkeley Research Reactor November 12, 1985 Points QUESTION B.06-8 (Contd)
Available h
u ee GrW rePista-iI T
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k-k lt 5
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=
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N d
7,5 X L 4, /
(
Lower Grid
~~
P/ fo a
u l
S fe fy P/< i e-Hot necessarill correcY
.e i
Figure B.06-8. (QUESTION) i
-Section B Continued on Next Page-a
Page 19
, Berkeley Research Reactor November 12, 1985
.E.
Points ANSWER B.06-8 (Contd)
Available Wre " Gr,V W
Posta 0
A
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Re Ned g,g Finure B.06-8 (ANSWER)
-Section B Continued on Next Page-
Berkeley Research Reactor Page 20 November 12, 1985 Points Available 00ESTION B.07 a.
UsingFigureB.06-8(QUESTION),sketchthelocationof the regulating rod when it is fully inserted into the core.
Shan on the sketch of the fully inserted rod the location and contents of the different raterials used in the design of the regulating rod.
(1.0) b.
Using Figure B.06-8 (QUESTION), sketch the location of the regulating rod when fully withdrawn. Shan on the sketch of the fully withdrawn regulating rod the location of the different materials used in the design.
(1.0)
ANSWER B.07 a.
See Figure B.06-8 (ANSWER).
(+1.0) b.
See Figure B.06-8 (ANSWER).
(+1.0)
Reference (s) B.07 1.
Berkeley: Safety Analysis Renort for the University of California Berkelev Research Reactor, pp. 3.12, 3.13, Figures 3.5, 3.6.
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-Section B Continued on Next Page-l
Page 21
~ Berkeley Research Reactor November 12, 1985 Points Available T..
QUESTION 5.08 Using Figure B.06-8 (QUESTION), sketch the location of the Transient Control Rod when it is fully inserted into the core.
Shng on the sketch of the fully inserted Transient Control Rod the location and the contents of the different materials used in the design of the rod.
(1.5)
ANSWER B.08 See Figure B.06-8 (ANSWER).
(+1.5)
Reference (s) B.08 1.
Berkeley: Safety Analysis Reoort for the University of California Berkeley Research Reactor, pp. 3.16, 3.17, Figures 3.5, 3.6.
QUESTION B.09 Why is it undesirable to have too high a flow rate of coolant through the demineralizer? List two (2) reasons.
(1.5)
ANSWER B.09 channeling in the demineralizer flushing of the demineralizer
(+0.75each)
Reference (s) B.09 1.
CAF
-End of Section B-I
Page 22 Berkeley Research Reactor November 12, 1985
~
(16.0)
C.
GENERAL OPERATING CHARACTERISTICS Roints
.. Available For QUESTIONS C.01 and C.02, specify the letter designation of the phrase that provides the correct statement.
QUESTION C.01 The rod-drive motor for the regulating control rod is (1.0)
(a.) connected to a potentiometer which rotates 10 times for each rotation of the motor shaft.
(b.) capable of withdrawing the control rod at a maximum withdrawal rate of 6 inches per minute.
(c.) a nonsynchronous, single-phase, reversible motor.
(d.) driving the extension rod into the core when it is rotating clockwise.
ANSWER C.01 (c.)
(+1.0)
Reference (s) C.01 1.
Berkeley: Safety Analysis Reoort for the University of California Berkeley Research Reactor, pp. 3-14, 3-15.
-Section C Continued on Next Page-t
Page 23 Berkeley Research Reactor November 12, 1985 i
Points Available QUESTION C.02 Beam ports are provided at the thermal-column end of the pool.
The design provides (1.0)
(a.) four (4) 8-inch diameter radial-beam ports and two (2) 6-inch diameter through-beam ports.
(b'. ) small-diameter steel pipes embedded in the concrete to providq for draining water from the beam ports.
(c.) six (6) steel, removable shielding plugs inside each of the radial beam ports.
(d.) terminating aluminum flanges for the beam ports containing a 1/4-inch tube and gas cock to permit purging of the tube with CO2 or other gases.
ANSWER ~C.02 (d.)
(+1.0)
Reference (s) C.02 1.
Berkeley: Safety Analysis Reoort for the University of California Berkeley Research Reactor, pp. 4-4 to 4-6.
t l
l t
l l
l l
-Section C Continued on Next Page-(
l w
m wi-
-=w w
wa w
%yr
+m v-v-
+
w ry-v--
m m7-
Page 24 Berkeley Research Reactor November 12, 1985 Points Available a:
00ESTION C.03 Measurements of the " power coefficient" were made for typical Mark III cores.
a.
Sketch a typical power-defect curve for a Mark III core for reactor powers from 0 to 1000 kW.
(1.0) b.
Bau does this curve change for a fresh core versus a core that has been pulsed 2000 times to 2000 MW7 Why does the power defect change with the number of pulses?
(2.0)
ANSWER C.03 a.
See Figure C.03 (ANSWER) (+1.0).
b.
The power coefficient increases in magnitude, i.e., the power defect increases for any power level, as the number of pulses increases (+0.5).
The changes are due to the thermal cycling of the fuel (+0.5) which results in a decreased thermal conductivity of the gap (+0.5).
This results in a higher fuel temperature for a given power level (+0.5) and due to the negative temperature coefficient, a larger decrease in reactivity for a given power level (+0.5).
(+2.0 max)
Referencefs) C.03 1.
Berkeley: Safety Analysis Reoort for the University of e
California Berkeley Research Reactor, pp. 5-5, 5-6 and Figure 5.2.
l
-Section C Continued on Next Page-
Page 25 Berkeley Research Reactor November 12, 1985 Points ANSWER C.03 (Contd)
Available 1
I N
f!!!
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52.00 d
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j l N,' !)lj! I
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1 1
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0 0 200 400 600 800 1000 1200 1400 1600 l
Reactor Power, kilowatts Reactivity loss versus ' reactor power-prototype reactor Fioure c.03 (ANSWER) i l
-Section C Continued on Next Page-
Page 26 Berkeley Research Reactor November 12, 1985 Points Available h
OUESTION C.04 Data on the last pulse performed on the Berkeley Research Reactor is listed in the log as Ak/k
= 2.10 $
peak power = 1600 MW energy
= 24 MW-sec width = 8 msec.
full-width-at-half-max a.
To produce a pulse with a peak power of 2000 MW, what should be the reactivity insertion?
(1.0) b..
What would be the energy content of the pulse if the answer to part "a." was 2.50 $7 (1.0) c.
What would be the pulse width if the answer to part "a." was 2.50 $7 (1.0)
ANSWER C.04 Pa(Ak/k-1)2 a.
IfiQa. 20.0A l
(1.1)2 2
(+0.5) x 2. 2Q02 (3,1)2 x
1600 j
x = (5/4)1/2 (3,3)
= (1.12)(1.1) i
= 1.23~
Ak/k = 2.23 $
(+0.5) i
-Section C Continued on Next Page-
Page 27 Berkeley Research Reactor November 12, 1985 Points Available
~ -
ANSWER C.04 (contd) b.
E a (Ak/k-1)
E=
(+0*5)
(1.1)
(1.5) x = U (24) 1.1
= 32.7 t1W-sec
(+0.5) c.
Width a(1/Ak/k-1)
AT=h(8)
(+0.5)
= 5.87 msec
(+0.5)
Reference (s) C.04 1.
Berkeley: Safety Analysis Reoort for the liniversity of California Berkeley Research Reactor, pp. 5-7 through 5-9.
2.
OSU: Oregon State TRIGA Reactor Training Manual, Volume VI, Reactor Physics. Kinetics and TRIGA Characteristics, December 1978, pp. VI-82 through VI-103.
l I
-Section C Continued on Next Page-
Page 28 Berkeley Research Reactor November. 12, 1085 Points Available QUESTION C.05 List the total reactivity worths for the four (4) control rods: the safety rod, the shim rod, the regulation rod
- w and the transient rod.
g (2.0)
,r.. s ANSWER C.05 3
safety rod 2.7%
0{/
f/
j 77 shim rod 1.8%
e>
'/
/
regulating rod 1.8%
?
f
(+0.T each)
'7 /
transient rod 2.1%
y Reference (s) C.05 1.
Berkeley: Safety Analysis Reoort for the University of California Berkeley Research Reactor, p. 3-13.
s
-Section C Continued on Next Page-
Page 29 Berkeley Research Reactor November 12, 1985 Points Available OUESTION C.06 Experimental measurements were made on the Berkeley Research Reactor regulating rod and the following data was recorded.
47.3 units /in.
=
0.021 in./ unit
=
total sec/ travel 40.0
=
22.5 in./ min
=
0.375 in./sec
=
h #"I
~
a ra
/sec
.9 0.15 max $/sec
- g
=
max $/ unit 0.01
=
a.
Use this data M ::: re th:t yr,ac er.s r M QJEST!^" C.^5 fer the t:t:.1 r;;;;eth,v-iva
, th was W.
Graph the " integral rod-worth curve" for the regulating rod. Accurately indicate the slopes and limits of the curve.
(2.0) b.
Why does the integral rod-worth curve have the shape.
you have graphed above?
(1.0)
ANSWER C.06 a.
The integral rod-worth curve is 5-shaped
+0.5. The curve has an abscissa domain of 0 to 15 inches
+0.5 and an ordinate range of 0 tog e (+0.5).
The peak slope is (15 t/sec)/0.375 in./sec) = 40 t/in.
(+0.5) b.
The integral rod-worth curve is S-shaped because the effect of making a small change in the amount of poison in a given location in the core is due to magnitude of the flux at that point and due to the importance of that change in the flux throughout the core. The result is that the effect is pro-portional to the flux squared. The flux is the largest at the vertical midplane and decreases toward zero near the vertical limits of travel for the control rod.
(+1.0)
-Section C Continued on Next Page-
Page 30 Berkeley Research Reactor i
November 12, 1985 L
Points
- Available e
r Referentcl;I _ C.06 1.
JerKeley: Safety Analysis Reoort for the University of M ilpfcliL ?erkeley Research Reactor, pp. 5-7 through 5-9.
l 2.
OSU: Or..!or. State TRIGA Reactor Training Manual, Volume I, t
Egeral Ctscriotion of Reactor and Facilities, October 1973,
- p. I-58.
j 3.
OSU: Oregon State TRIGA Reactor Training Manual, Volume VI, f
Reactor Physics. Kinetics and TRIGA Characteristics, December l
1978, pp. VI-18 through VI-19.
QUESTION C.07
[
Lb1 the three (3) effects (components) that contribute to the large prompt negative fuel-temperature coefficient of the Triga reactor. Indicate which component has the largest effect and which has the smallest.
(2.5)
ANSWER C.07 cell and inhomogenities Doppler core leakage i
The cell and inhomogenities effect is the largest.
l The core leakage effect is the smallest.
(+0.5each)
Reference (si C.07 1.
GAi Triga Training Manual, GA Technologies Inc.,
Chapter 6, para 6.2.3.
t L
-Section C Continued on Next Page-I
Page 31 Berkeley Research Reactor November 12, 1985
~
Points Available
.r-OUESTION C.08 Suecify the value of the fuel temperature coefficient. Provide the algebraic sign for the coefficient and the magnitude within 25%.
(0.5)
ANSWER C.08
-1.26 x 10-4 Ak/k per C
(+0.5)
U Reference (s) C.08 1.
Berkeley: Safety Analysis Reoort for the University of California Berkelev Research Reactor, p.11.
-End of Section C-
Page 32 Berkeley Research Reactor November 12, 1985.
D.
INST'RUMENTS AND CONTROLS (15.0)
=
Points
_.~~ Aviilable OUESTION D.01 Shown in Figure D.01-2 (QUESTION) is the fail-safe circuit for AC power and air pressure for the Berkeley Research Reactor, a.
If AC power is lost, soecify the status (CLOSED or OPEN) of the contact in the air monitor.
(0.5) b.
If AC power is lost, soecify the status (CLOSED or OPEN) of the switch marked "1".
(0.5) c.
If AC power is lost, soecify the status (CLOSED or OPEN) of the switch marked "2".
(0.5)
ANSWER D.01 a.
CLOSED b.
OPEN c.
OPEN
(+0.5each)
Reference (s) D.01 1.
Berkeley: Safety Analysis Reoort for the University of California Berkeley Research Reactor, Figure 2.5.
s i
l
-Sectior. D Continued on Next Page-i l
1 Page 33 Berkeley Research Reactor November 12, 1985 QUESTION 0.01-2 (Contd)
Points AC LINE Available 120 V y.
lj c _ _ _ _ _ _,
O- "" OUTLET
- 1 I...-
I MONITOR T
[. '-
___r 120V AC n
ll-8 l ((AND EXHAUST ~ FAN MOTORS lN SERIES WITH MAIN SUPPLY 3 POLES-T S BUTTERFLY AIR CYLINDER VALVES -
~
l l l
- 3 MAIN EXHAUST h
l SPRING J LOADED
~-
6 SOLENOID 5 POLES-5 VALVES-4 a
v CONTINUOUS OPERATING N
IS PSIG SUPPLY AIR EXHAUST FAN E-20 ON EMERGENCY POWER G
E-20 200 CFM 3 BUTTERFLY VALVES-DIAPHRAM OPERATORS p
N AE INLET FROM i
CHARC0AL NEl-l
~
~
SCRUBBER
~
=
0 a
i Figure D.01-2 (QUESTION)
-Section D Continued on Next Page-
Page 34 Berkeley Research Reactor November 12, 1985 Points Available OUESTION D.02 Using Figure D.01-2, a.
If air is lost from the " AIR CYLINDER", soecify the
~
status (OPEN or CLOSED) of the five (5) butterfly valves.
(0.5) b.
If AC power is lost, soecify the status (OPEN or CLOSED) of the valve connected to the 15 psig supply air.
(0.5) c.
If the valve is OPEN from the 15 psig supply air, soecify the status (OPEN or CLOSED) of the two (2) valves on either side of the " CHARCOAL SCRUBBER".
(0.5)
ANSWER D.02 a.
CLOSED b.
CL SED s
c.
PE C?r'f D
(+0.5each) i Reference (sl D.02 1.
Berkeley: Safety Analysis Reoort for the University of California Berkelev Research Reactor, Figure 2.5.
I
-Section D Continued on Next Page-l
Page 35 Berkeley Research Reactor November 12, 1985 Points Available OUESTION D.03 Briefly exclain shy the power level monitor that reads in %
power (2 to 100+%) can use an uncompensated ion chamber (UIC) rather than a compensated ion chamber (CIC).
(1.0)
&HIWER D.03 The intensity of the neutron at the signal range of this instrement (2 to 100+%) overwhelms the included signal from the gamma flux making compensation unnecessary.
(+1.0)
Reference (s) 0.03 1.
Berkeley: Safety Analysis Renort for the University of California Berkeley Research Reactor, pp. 3-8, 3-20.
l I
-Section D Continued on Next Page-
fe'
/
/
ff Page 36 JgrkeleyResearchReactor 1
November 12, 1985 gh [
Points Available j
f ('y j F
,,f OUESTION D.04 Briefly describe h the reactor is set up and b the control system works in the "souare wave" operational mcde that results in producing a square wave of power.
(2.1)
ANSWER D.04 The ~ answer must contain the essence of the-following.
A preadjusted step reactivity change adjustinent limit is set on the remaining travel of the transient rod.
[
The reactor is brought to a power level of up to 1000 watts l
in the steady-state mode.
The range switch on the linear power channel is set at 1 MW.
)
The period meter and its scram signal are disconnected.
c[v
(
The mode switch is changed to the square-wave operation. v '"
The high speed servo automatically inserts reactivity to hold the power level constant as the fuel heats up after rod has been ejected.
j A*------+-+i-
+'- +--- i--+
-^d is-release & to de^p tc it; ;tertins ;;;ttien.
(+0.3 for each) s Reference (s) 0.04 1.
Berkeley: Safety Analysis Reoort for the University of California Berkeley Research Reactor, Section 3.5.3, p. 3-21.
-Section D Continued on Next Page-
Page 37 Berkeley Research Reactor November 12, 1985 Points Available QUESTION D.05 Soecify the condition (ON or OFF) of the UP, DOWN, and CONT lights for the regulation under the following conditions:
a.
The reactor was scramed 100 msec ago and there are no system malfunctions.
(0.5) b.
The control rod and rod drive are fully withdrawn and there are no system malfunctions.
(0,5) c.
Either control rod insertion or withdrawal is possible and there are no system malfunctions.
(0.5) d.
The control rod and rod drive are at their lower limits and the magnet is making contact with the armature and there are no system malfunctions.
(0.5) e.
The reactor was scrammed 10 min ago and the control md stuck and did not move from its fully withdrawn position.
(0.5) f.
The reactor was scrammed 10 min ago and there are no system malfunctions.
(0.5)
ANSWER D.05 E
00MH C0HI a.
OFF 0FF OFF 40.5 b.-
ON OFF ON
+0.5 c.
OFF OFF ON
+0.5 d.
OFF ON ON
+0.5 e.
ON OFF ON
+0.5 f.
OFF ON ON
+0.5 Reference (si D.05 1.
GA: Syllabus & Triga Training Manual, GA Technologies Inc.,
Reactor Instrumentation and Control Circuitry, pp. 2-9 through 2-14.
-Section D Continued on Next Page-l
Page 38 Berkeley Research Reactor November 12, 1985 Points Available OUESTION D.06 The water treatment system on the reactor serves four (4) functions.
Name three (3) of them.
(1.5)
ANSWER D.06 Maintain low conductivity of the water to minimize corrosion of reactor components,. particularly fuel.
(+0.5)
Reduces radioactivity in the water by(+ removing nearly all particulate and soluble impurities.
0.5)
Maintains optical clarity of the water.
(+0.5)
Provides a means of dissipating the heat generated in the reactor.
(+0.5)
- ,Z%
h
,:'g- (<-'
( ~',
iss. e n.a
(*d'-
(+1.5 max)
Reference (s) 0.06 g,;. C f
1.
Berkeley: Safety Analysis Reoort for the University of j,,;
California Berkeley Research Reactor. p. 3-30.
, l' -
s-4
, s' '
f
-Section D Continued on Next Page-
Page 39 Berkeley Pesearch Reactor i
November 12, 1985 Points Available QUESTION D.07 Answer TRUE or FALSE.
a.
An automatic shutdown (scram) will result if an operator attempts to manually drive two (2) control rods simultaneously.
(0.3) b.
An automatic shutdown (scram) will result if a pulse is attempted when the reactor power level is above 1 kW.
(0.3) ove r -
c.
An automatic shutdown (scram) can occur from a peak power trip in any operating mode.
(0.3)
Y[,. b ANSWER D.07
,f' a.
FALSE b.
FALSE
(+0.3each) c.
TRUE FAL'E Reference (si D.07 1.
Berkeley: Safety Analysis Reoort for the University of California Berkeley Research Reactor, Section 3.5.6.
QUESTION D.08 lfng is an automatic shutdown (scram) provided during pulsing operation?
(1.0)
ANSWER D.08 During pulsing operation, normal instrumentation is disconnected and reactor shutdown is provided by an 4tegrated f!;x cir:;it fMp [ p-obtaining its signal from an ion chamber.
(+1.0)
' 'ps Reference (si D.08 1.
Berkeley: Technical Soecifications, Appendix A. Description,
- p. 2.
-Section D Continued on Next Page-
Page 40 Berkeley Research Reactor November 12, 1985 Points Available
~.
OUESTION D.09 For the fuel-moderator elements of the Berkeley Research Reactor soecify:
a.
the diameter (1 0.1 inch)
(0.5) b.
the fuel enrichment of active region (A 2%)
(0.5) c.
the type of cladding (0.5) d.
the approximate loading (number of fuel-moderator elements)
(0.5) for criticality with the present configuration e.
the location of the burnable poison.
J (0.5) o y. rj r i N Nr,'
I ANSMER D.09 a.
1.4 inches
/, + 3 ['
ge,,
b.
20%
I h"'f y c.
stainless steel J+0.5each) d.
79 (+6, -2) ip5 A - if 7 e.
discs between the active region and graphite reflector slugs Reference (s) 0.09 1.
Berkeley: Safety Analysis Reoort for the University of California Berkeley Research Reactor, p. 3-3.
-End of Se.ction D-
Page 41 Berkeley Research Reactor November 12, 1985 E.
SAFETY AND EMERGENCY SYSTEMS (13.0)
Points Avai'lable For OUESTIORS E.01, E.02, E.03 and E0.4 specify the letter designation of the phrase that provides the correct statement.
QUESTION E.01 The log-n channel (1.0)
(a.) provides over 5 decades of reactor period indication.
(b.) provides the signal to automatically withdraw or insert the count-rate channel detector.
(c.) utilizes an ion chamber that operates in the Geiger-Huller mode.
(d.) provides a power-level trip at 110% power.
ANSWER E.01 (b.)
(+1.0)
Reference (s) E.01 1.
Berkeley: Safety Analysis Reoort for the University of California Berkeley Research Reactor, pp. 3-19, 3-20.
~
l l
-Section E Continued on Next Page-
Page 42 Berkeley Research Reactor November 12, 1985 Points y'/
Available
,\\
w J
/
OUESTION E.02 y
[
f I
The bulk-water temoerature monitor (1.0) i (a.) is provided with an adjustable-level scram.
(b.) is operational only in the pulse mode.
(c.) is provided with a selector switch to alternatively read fuel temperature.
(d.)isprovidedwithanalarmthatsoundsif.thebulk-water temperature drops below a preset value.
ANSWER E.02 P'
/&
[
ti i
D
. 'tI
[l# ) / (
I 9'
o' '
/ /
(c.)
(+1.0)
A
[S,.- (.. '#g
,/
f lr
- r
/
Reference (sl E.02
(
1.
Berkeley: Safety Analysis Renort for the University of California Berkeley Research Reactor, p. 3-20.
l
/
-Section E Continued on Next Page-
Page 43 Lerkeley Research Reactor November 12, 1985 Points Available "m-'
OUESTION E.03 1
The servo amplifier that automatically controls the regulating rod (1.0)
(a.) receives information on reactor power and on reactor period front the log-n channel.
(b.) receives information on reactor power and on reactor period from the linear-power channel.
(c.) compares the power-demand signal with the fuel-temperature signal when in the transient mode.
g'[g 5 [
? "l (d.) compares the power-demand signal with the inear-power channel signal when in the t!ndy :; tate mode PuTo r
e ANSWER E.03 g
(
C' (d.)
(+1.0)
/,, ' 'e //['
f, Reference (s) E.03 1.
Berkeley: Safety Analysis Reoort.for the University of California Berkeley Resgrch Reactor, Figure 3.10.
es ! '
s I
A
-Section E Continued on Next Page-O
.Ae
Page 44 Berkeley Research Reactor November 12, 1985 Points Available OUESTION E.04 According to the Operating Procedures, the reactor-power calibration is currently checked by:
(1.0)
(a.)
operating the rector at 1 MW several hours in position 3 and comparing the measured temperature increase per unit of energy input with a predetermincd value.
(b.)
operating the rector at 52 kW for several hours in position 3 and' comparing the measured temperature increase per unit of energy input with a predetermined value.
(c.)
operating the reactor at a steady power level above 1 kW for several hours in position 1 or 6 and comparing the temperature increase per hour with a predetermined value.
(d.')
. operating the reactor at 52 kW for no more than 10 minutes with the secondary cooling system turned 0FF and comparing the temperature 3
increase per hour with a predetermined value.
\\
ANSWER E.04 (a.)'
(+1.0) i Reference (s) E.04 1.
Berkeley: Interim coeration Manual. Calibration Procedure, Section 2.5, p. 47.
A it
-Section E Continued on Next Page-
\\
Page 45 Berkeley Research Reactor November 12, 1985 Points Available NW.
e.e OUESTION E.05 Identify three (3) electrical loads that are supplied by the emergency power supply.
(1.5)
ANSWER E.05 Reactor console
+0.5)
Air monitoring equipment
+0.5
(+1.5 max)
Radiation monitors
+0.5 S ubber fan (glove box fan)
+0.5 Cm
.a n.8
.w r-
-(e d Reference (s) E.05
.1.
Berkeley: Safety Analysis Reoort for the University of California Berkeley Research Reactor, p. 2-8.
QUESTION E.06 What types of radiation monitors would initiate a radiation alarm to the campus police? [Listfour(4).]
(2.0)
ANSWER E.06 Any of nine (9).c'ea radiation monitors Stackgas radiation monitor Air-particulate monitor Water-radiation monitor
.(+0.5each)
Reference (s) E.06 1.
Berkeley: Emergency Procedurgs, 4.8.2, p. 72.
i
-Section E Continued on Next Page-
Page 46 Be'rkeley Research Reactor November 12, 1985 Points A_vailable 1
QUESTION E.07 Of the many interlocks to ensure safe operation, three (3) of these interlocks provide protection / safety operation for the pulse mode Liit these interlocks and what they eag4r (2.4)
V acco:nplish.
j
\\q.;(Y f.<'
4
.A
,9 Y
,[ f ANSWER E.07 Log power (+0.4)
Prevents pulsing the reactor at initial power levels above 1 kW. (+0.4) b Presettimer(+0.4)
Provides a transient-rod scram 15 seconds
',/
c or less after pulse initiated. (+0.4)
/
v Rod drive control (+0.4) Prevents withdrawal of any rod except
/
f
//g. '-
transient rod. (+0.4)
/
v*
Reference (si E.07 1.
Berkeley: Technical Snecifications,' Table 1, paragraph 3.5, p.12.
i QUESTION E.08 Describe what information the instrumented fuel element provides, andwhy(how)thisinformationcanaffectfuelintegrity.
(1.6)
~
l ANSWER E.08 The instrumented fuel element monitors the temperature of the section (+0.8) points about the vertical center of the fueled fuel at three I
This temperature determines the pressure of the gases within the cladding to be below cladding failure point. The limit is set on the temperature to limit the internal pressures of the fuel to prevent the cladding failure.
i(+0.8)
Reference (si E.08 1.
Berkeley: Safety Analysis Renort for the University of California Berkeley Research Reactor, Section 7.5, p. 7-45.
-Section E Continued on Next Page-l ~
~
Page 47 Berkeley Research Reactor November 12, 1985 T-Points
'Available QUESTION E.09 Answer these three (3) questions TRUE or FALSE based on the following. Assume the reactor has been operating over 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> at 1 MW when for some reason total loss of pool water occurred within a few few minutes.
a.
The reactor would go super critical.
(0.5) b.
Fuel temperatures would rise suftf;tently to allow a breach of cladding on some elements.
(0.5) c.
The dose rates on the patio would be high enough to expose those present to more than several R integrated dose in the first 10 minutes.
(0.5)
ANSWER E.09 a.
FALSE b.
FALSE c.
FALSE
(+0.5each)
Reference (s) E.09 1.
Berkeley: Safety Manual for the University of california Berkeley Research Reactor, pp. 7.47, 7.84, and 7.49, respectively.
-End of Section E-k
J Page 48 Berkeley Research Reactor November 12,' 1985 F. STANDkRD AND EMERGENCY OPERATING FROCEDURES 1
(12.0)
Ppints Avai-l abl e OUESTION F.01 During fuel-handling operations several radiation-monitoring instruments are required to be operating. Lisi four (4) of these required radiation monitors.
(2.0)
,[ 4
/
ANSWER F.01 s
/(. y
,f' /(. ej Bridge-area radiation monitor f
g
/
?
At least two (2) other radiation area monitors
[
[)
Stackgas monit'or
(,
- Air-particulate monitor One (1) portable audible radiation monitor on the bridge
(+0.5each,+2.0 max)
Reference (s) F.01 1.
Berkeley: Interim coeration Manual. General Operating Procedures, Section 1.7, pp. 13-15.
- Section F Continued on Next Page -
Page 49 Berkeley Research Reactor November 12, 1985
~
Points Available QUESTION F.02 Answer TRUE or FALSE.
According to the Technical Snecifications. the instrumented fuel a.
element may be positioned in either the B or C ring.
(0.5) b.
As instructed by the General Ooerating Procedures. the reactor is normally shutdown by manually driving the rods down.
(0,5) c.
Only personnel on the BRR Emergency Call List can authorize disabling of a BRR radiation alarm.
(0.5)
ANSWER F.02 a.
TRUE b.
FALSE c.
TRUE
(+0.5each)
Reference (s) F.02 1.
Berkeley: Technical Soecifications, Section 2.2.
2.
Berkeley: Interim ooerations Manual. General Operating Procedures, Section 1.1.5, Reactor Shutdown.
3.
Berkeley: Interim ooerations Manual. Emergency Procedures, Section 1.9, Disabling of a BRR Radiation Alarm.
t P
- Section F Continued on Next Page -
{
Page 50 Berkeley Research Reactor November 12, 1985
=
Points
.Available i
1 *-
00ESTION F.03 The following statements refer to the BRR General coerating Procedures and Emergency Procedures.
In each, complete the statement to read correctly by supplying the missing word (s) or choosing the proper term, a.
For steady-state operations, reactor operation must be approved by (0.5) b.
During a normal power increase, the period should not be less than (0.5) c.
During all modes of operation, a must remain at (1.0)
ANSWER F.03 a.
Reactor supervisor (+0.5) b.
12 seconds (+0.5) c.
licensedoperator(+0.5) at the console (+0.5)
Reference (s) F.03 1.
Berkeley: Interim coerations Manual. General Operating Procedures, Section 1.1.2.3.
2.
Berkeley: Interim coerations Manual. General Operating Procedures, Section 1.1.2.6.1.
3.
Berkeley: Interim Ooerations Manual. General Operating Procedures, Section 1.1.2.9.
l
- Section F Continued on Next Page -
Page 51 Berkeley Research Reactor November 12, 1985 Points Available 4F=
OUESTION F.04 Answer TRllE or FALSE to the following statements, based on the Operating Procedures for the Berkeley Research Reactor.
a.
During fuel-handling operations, one licensed sou6er reactor operator must be at the console.
(0.5) b.
During fuel-handling operations, the reactor must be subcr(tical by a given margin assuming a cold, clean (plus samarium) reactor without any equipment / material for experiments.
(0.5) c.
If the core configuartion is temporarily changed the reactor shutdown margin for the new arrangement must be determined by measurement.
(0.5) d.
If the core geometry is temporarily changed, the rod worths for the new arrangement must be estimated.
(0.5)
ANSWER F.04 a.
W. j~ r9 L ? E b.
TRUE c.
FALSE d.
TRUE
(+0.5each)
Reference (si F.04 1.
Berkeley: Interim coeration Manual. General Operating Procedures, Section 1.7, pp. 13-15.
P
- Section F Continued on Next Page -
Page 52 Berkeley Research Reactor November 12, 1985 Points Available OUESTION F.05 Answer TRUE or FALSE.
a.
The reactor is considered in operation whenever the reactor is not secured.
(0.5) b.
A channel test of each of the reactor safety system channels with scram capabilities shall always be performed prior to each day's operation, independent of the intended mode of operation.
(0.5)
ANSWER F.05 a.
TRUE
(+0.5each) b.
FALSE Reference (s) F.05 1.
Berkeley: Technical Soecifications, Appendix A,1.0 Definitions, paragraph 1.3, p. 1.
2.
Berkeley: Technical Seocifications, Appendix A, paragraph 4.2.2, p.19.
l
- Section F Continued on Next Page -
_ _ _.. _ _ _ -. ~. _ _. -,
Page 53 Berkeley Research Reactor November 12, 1985 Points areAvailable C
- 00ESTION F.06 The off-hours door alarm will be activated by opening any one of four (4) doors.
a.
Specify these four (4) doors.
(1.0) b.
When would an off-hour door alarm be ignored by the Campus Police?
(1.0)
ANSWER F.06 a.
Any one (1) of three (3) doors to reactor laboratory and the door to the decontamination room in the airlock (+1.0)
An opening accompanied by(a phone call to campus police office b.
by a legitimate entrant.
+1.0)
Reference (si F.06 1.
Berkeley: Interim coerations Manual. Emergency Procedures, Section 4.8.3, Door Alarm, p. 74.
- Section F Continued on Next'Page -
I i
I Page 54 Berkeley Research Reactor.
November 12, 1985 Points
~ ~ Ayii-l abl e QUESTION F.07
?
L Choose those three (3) statements from those below that are i
limiting conditions for operation specified by the Technical i
Specifications.
(1.5) i l
(a.) The reactivity worth of any single experiment shall be less than 3.0 dollars.
(b.) Any divice or material used under the classification of an irragjation shall be placed in a neutron flux of less than 5x10 inv.
(c.) The reactivity worth of any device or material used under the classification of an irradiation shall be less than 0.25 dollars.
(d.) Any device or material used under the classificaiton of an irradiation shall be in the reactor for less than 15 days.
fNSWER F.07 i
i (a.), (c.), (d.)
[+0.5 each for (a.), (c.), (d.); -0.5 'for (b.); +0.0 min]
l i
Reference (si F.07 1.
Berkeley: Technical Soecifications. Appendix A, Section 3.8, pp.14-17.
l i
l
- End of Section F -
t i
I i
l
\\
i
+
I
[
Page 55 Berkeley Research Reactor November 12, 1985 G. RADIATION CONTROL SAFETY (12.0)
~~Po'i nt s Available OUESTION G.01 Briefly exolain hng a radiation source is obtained to calibrate the stackgas monitor.
(1.0)
ANSWER G.01 A disposable syringe is filled with argon gas, irradiated for about 200 sec at 10 kW in the lazy Susan. The gas is injected into the chamber area of the stackgas counter.
(+1.0)
Reference (s) G.01 1.
Berkeley: Interim coerations Manual, General Operating Procedures, Section 2.2, Stackgas Monitor Calculations.
OUESTION G.02 a.
The "BC" extinguishers are one of the types of fire extinguishers provided in the laboratory. For what kinds of fires are these extinguishers effective?
(1.0) b.
There are three (3) types of enviror. mental dosimetry:
- 1) alpha-beta-gamma films, 2) neutron films, and 3) TLD packets. Of these three (3) types of dosimetry, which is the most sensitive and which is the least sensitive?
(1.0)
ANSWER G.02 a.
For electrical and flammable liquid fires.
(+1.0) b.
Most sensitive - TLD packets (+0.5)
Least sensitive - neutron films (+0.5) i Reference (sl G.02 1.
Berkeley: Radiation Safety Training Manual, Section G,
- p. 5.
2.
Berkeley: Radiation Safety Training Manual, p. 2.
- Section G Continued on Next'Page -
Page 56 Berkeley Research Reactor Noveriber 12, 1985 Points
-. Available OUESTION G.03 Outline the requirements that are associated with areas in which (a) the exposure rate may be 5 to 100 mR/hr and (b) t:1e exposure rate may be greater than 100 mR/hr.
(3.0)
ANSWER G.03 5 to 100 mr/hr
> 100 mr/hr posted with radiation posted with radiation sign, Caution sign, Caution High Radiation Area (+0.5)
Radiation Area (+0.5)
Entrants must be-Entrants must have accompanied by reactor' permission, be staff member or use accompanied and a survey instrument directly supervised
(+1.0) by staff And have a surve instrument
(+1.0 Reference (s) G.03 1.
Berkeley: Sadiation Safety Training, Section 4.b, p. 6.
I i
- Section 9 Continued on Next Page -
Page 57 Berkeley Research Reactor November 12, 1985 Points
-.Available 00ESTION G.04 Briefly exolain & the flowrate in the air particulate vacuum samplers must be accurately established at least every six (6) months.
(1.0)
ANSWER G.04 The flowrate determines the ' calibration of the air sampler W th. L.,_.n. a c.. ;.;; c.,f ;;.. elam ::t ;;it:. (+1.0)
Reference (s) G.04 i
1.
Berkeley: Radiation Safety Procedures. Procedure RP-34-8.
I l
- Section G Continued on Next Page -
Page 58 Berkeley Research Reactor November 12, 1985 Points Available s..
s OUESTION G.05 Radiation Contamination is monitored by an extensive swipe program.
Most locations are classified as abnormal when the disentegration rate exceeds 75 dpm. However, three (3) locations are exceptions and are routinely high.
Identify these three (3) areas from the swipe locations given below.
(1.5)
(a.)
floor by chemical hoods (b.)
airlock door handles (c.)
bridge floor, E side (d.)
RHP counter area (e.)
lowering bucket (TD)
(f.)
TD floor, E end (g.)
bridge CT table top (h.)
Janitor mops and buckets.
ANSWER G.05 (c.), (e.), (g.); (+0.5 for each correct answer
-0.1 for each wrong answer,
+0.0 min).
s Reference (s) G.05 1.
Berkeley: Radiation Safety Proceduresi Routine Swip Program RP 34-4.
- Section G Continued on Next Page -
Page 59 Berkeley Rescatch Reactor November 12, 1985 Points Ava,il abl e
_7
=
QUESTION G.06 Relative to radiation incidents where a radioactive spill occurs; i.e., contamination is present, what characterizes a Minor Incident?
Glyn three (3) characteristics.
(1.5)
ANSWER G.06 a.
contamination of equipment or small section of lab (+0.5) b.
no health hazards
(+0.5) c.
no abnormal conditions beyond reactor lab
(+0.5).
Reference (si G.06 1.
Berkeley: Interim coerations Manual. Emergency Procedures, Section 4.1.1, p. 60.
QME1 TION G.07 If two (2) centimeters of lead placed at a ce'rtain location in a narrow beam of gamma rays would reduce the gamma radiation level from 100 mR/hr to 50 mR/hr, what thickness of lead placed in this beam would reduce the gamma radiation level from a.
400 mR/hr to 50 mR/hr?
(0.5) 50 mR/hr to 25 mR/hr?
(0.5) b.
ANSWER G.07 a.
6 cm
+0.5 b.
2 cm
+0.5 Referencefsl G.07 1.
Generic: Radiation Shieldino. B.T. Price et al., 1957, pp. 36, 37.
2.
Reed: Reed Training Document, Technical Education Research Center-
~ Southwest, pp. 1-24,.1-25, 2-1, 2-2.
- Section G Continued on Next Page -
Page 60 Berkeley Research Reactor November 12, 1985 Roints
~ ~ Ava11 abl e OUESTION G.08 If the gamma-ray radiation level from a pump (point source) has been 30 mR/hr 1 foot from the pump, what would be the radiation level 10 feet from the pump?
(1.0)
ANSWER G.08 Neglecting gamma-ray absorption by the air,
~
distance factor = (10)2 / (1) = 100
(+0.5) rad level (1)/100 rad level (10)
=
0.30 mR/hr
(+0.5)
=
Reference (s) G.08 1.
Generic: Nuclear Energy Training, Module 5, " Radiation Protection,"
pp. 3.3-1 to 3.3-4.
- End of Section G -
- End of Examination -
i l
i t
i l
'I l
l
J EQUATION SHEET
~_;_........
Where mi = m2
( den si ty) t ( vel oc i ty ) t ( a rea )1 = ( den si ty ) 2 ( vel oc i ty) 2 ( a rea ) 2 I
2 PE +KE +P V 1 i = PE +KE +P V22 where V = specific KE = mv PE = mgh 2
2 i
i
~1[
volume P = Pressure b
p out-Tin)
.Q = UA (Tay,-Tstm) 0
- bIh -h )
Q = Ac (T l 2
+
l P = P 10(SUR)(t) p, p e,t/T SUR = 26.06 T = (B-p)t o
o T
p I
CR (1-K,ffi) = CR (1-Keff2)
CR = S/(1-Keff) delta K = (Keff-1) 1 2
1 M = (1-K,gft)
SDM = (1-K,ff) x 100%
l Il-Keff2I Keff i
i i
1 = A e-(decay constant)x(t) in (2) 0.693 A
decay constant
=
=
g t
-t j
1/2 1/2 I
Water Parameters Miscellaneous Conversions i
i t
j 1 gallon = 8.345 lbs 1 Curie = 3.7 x 1010 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs l
i
)
1 ft3 = 7.48 gallons I hp = 2.54 x 10 Btu /hr
[
3 t
Btu /hr f
Density =62.4lbg/ft 1 MW = 3.41 x 105 3-Density = 1 gm/cm 1 Btu = 778 ft-lbf
~ 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 2
l 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft.1bm/lbf-sec i'
s s
8
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