IR 05000199/1986002
| ML20207H484 | |
| Person / Time | |
|---|---|
| Site: | 05000199 |
| Issue date: | 06/30/1986 |
| From: | Coe D, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20207H473 | List: |
| References | |
| 50-199-86-02, 50-199-86-2, NUDOCS 8607240341 | |
| Download: ML20207H484 (49) | |
Text
T.
,
.
)
U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT
,
EXAMINATION REPORT N0.
50-199/86-02 (0L)
,
j FACILITY DOCKET NO. 50-199 i
'
FACILITY LICENSE N0. R-94 LICENSEE: Manhattan College Corporation Riverdale, New York 10471
,
FACILITY: Manhattan College
EXAMINATION DATES: June 3-4, 1986 i
5/2 g CHIEF EXAMINER:
ch l
D. Coe, Reactor ngineer (Lead Examiner)
Date REVIEWED Bf:
d[2'>7@
R. M. Keller, Chief, Projects Section 1C Date NA,b 4LO/M, APPROVED BY:
HaFry B. LMter,' Ott ef, Projects Branch No.1
/Dat4 i
i
!
SUMMARY: Written and oral examinations were administered to one SRO candidate.
i The candidate passed the oral examination and failed the written examination.
'
i
!
i 0607240341 860711 r
l PDR ADOCK 05000199 l
V PDR i
_
_
e A
REPORT DETAILS TYPE OF EXAMS:
Initial Replacement X
Requalification EXAM RESULTS:
l SR0 l
l Pass / Fail l
l l
l l
l l Written Exam l
0/1 I
I I
l I
l l
10ral Exam l
1/0 I
I I
I I
I l
l0verall l
0/1 l
l l
l l
l l
1.
CHIEF EXAMINER AT SITE: John D. Smith, PNL 2.
EXIT MEETING No exit meeting was held at the conclusion of the site visit as the facility staff was not available.
3.
EXAMINATION REVIEW Copies of the examination and answer key were left with the facility for their review. Their comments were submitted by mail.
The comments and the resolutions to the comments are included in this repor _
%
.
Attachments:
1.
Written Examination and Answer Key (SRO)
2.
Facility Comments on Written Examination
- -
- -
-
_
- - _
hTTACbj71ct)f /
%
U.S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION Facility:
Manhattan College Reactor Type:
Pool Date Administered:
June 3, 1986 Examiner:
J. D. Smith Candidate:
Answer Key M d 57#4 INSTRUCTIONS TO CANDIDATE:
Use seperate 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 parenthesis 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
% of Candidate's
% of Value Total Score Cat. Value Cateoory 21.0 21.0 H.
Reactor Theory 19.0 19.0 1.
Radioactive Materials Handling, 01sposal, and Hazards 20.0 20.0 J.
Specific Operating Characteristics 20.0 20.0 K.
Fuel Handling and Core Parameters 20.0 20.0 L.
Administrative Pro-cedures, Conditions, and Limitations
..
100.0 TOTALS Final Grade
%
All work done on this examination is my own; I have neither given nor received aid.
Candidate's Signature
-
.. _
._
.
b Hanhattan College Page 1 June 3, 1986 Points Available
,
(21.0)
.
H.
REACTOR THEORY 00ESTION H.01 The MCZPR is increasing power with a period of 25 seconds.
'
How much time is required for the power level to
!
a.
increase by two (2) decades? Show your calculations.,
(2.0)
b.
What is the reactivity of the core during this power l
increase? Show your calculations.
(1.0)
,
ANSWER H.01
!
a.
T = 25 sec P/P = 100 = e /25
[+1.0]
t o
Ln 100 = t/25 t = 25 Ln 100
= 115 sec
[+1.0]
,
!
= 1.92 min
'If
[+0.5]
!
b.
p=1 AT 0.0068
" 1 + 0.081 x 25 p = 0.225% delta k/k
[+0.5]
i REFERENCE H.01 1.
Generic: Technical Education Research Center-Southwest,
" Nuclear Technology", pp. 12-1-13 to 12-1-18.
i
!
i i-Section H Continued on Next Page-
!
,
I
-
--
-. --
--_---.
_
-__.-.
-..- -.
. _ _ -... _ _
.
'
i f
Manhattan College Page 2 June 3, 1986
'
Points Available
-
OVESTION H.02 i
Explain why the delayed neutrons have such a large effect on the operator's ability to control the reactor when the delayed
+
neutron population is only about 0.6% of the total neutron (1.0)
population in the core.
ANSWER H.02 Even though the percentage of delayed neutrons is small, their relative effect is great because their generation to generation time may be on the order of 4 x 10-5 seconds.
[+1.0]
Reference (s) H.02 1.
Generic:
G. A. TRIGA Trainina Manual, " Reactor Theory",
Chapter 6.
-Section H Continued on Next Page-
_ _ _ _ -
_-
-
.
%
Manhattan College Page 3 June 3, 1986 Points Available OVESTION H.03 Select the statement that correctly completes the sentence.
Doubling the time a target nuclide is irradiated will (1.0)
.
(a.) double the activity (b.) more than double the activity (c.) less than double the activity ANSWER H.03 (c.) [+1.0]
[whichresultsfromthedelayofthenuclide
,
generated expressed in terms of its decay constant A as the decay factor (1 - c-t))
Reference (s) H.03 1.
Generic: Stephenson, R., McGraw-Hill.
-Section H Continued on Next Page-
..
b Manhattan College Page 4 June 3, 1986 Points Available 00ESTION H.04 Explain what is meant by a dollars worth of reactivity in terms of K and the delayed neutron radiation (beta) and define the termIintheequation.
(2.0)
f ANSWER H.04
3*
p [+1.0]
K,ff - I where c = reactivity =
[+0.5]
g ff e
and p is the delayed On fraction.
[+0.5]
Reference (s) H.04 1.
Generic:
G. A. TRIGA Trainina Manual, Section 6.2.4, pp. 6-12.
.
.
-Section H Continued on Next Page-
-
- - -
..
_
.
.
%
Page 5 Manhattan College June 3, 1986 Points Available
-
QUESTION H.05 i
A thermal neutron is (Select one)
(1.0)
(a.) a neutron possessing thermal rather than kinetic energy.
(b.) a neutron that experiences no net change in energy after several collisions with atoms of the diffusing media.
(c.) a neutron that has been produced in a significant time (on the order of seconds) after its initiating fission took place.
,
.
(d.) the primary source of thermal energy increase in the reactor
'
coolant during reactor operation.
ANSWER H.05
(b.)
[+1.0]
Reference (s) H.05 1.
Generic:
Stephenson, R., McGraw-Hill.
!
-Section H Continued on Next Page-
_ _ _ _.. _ _
_ -.
.____ _
_ _ _.. _ -.. _ - _. _ _ _. _ _. _.. _. _. ___. _. _ _ _. _ _ _..
.
. -
-..
.... _. _ _
-
_
.
.
Manhattan College Page 6 June 3, 1986 Points Available 00ESTION H.06 Which of the following statements best accounts for the fact that irradiated fuel elements are radioactive?
(Select one.)
(1.0)
(a.) The high-neutron flux activates impurities in the fuel cladding and matrix, therefore yielding radioactivity.
(b.) Fission products, like the parent U-235 atom, are very neutron rich, and therefore tend to decay into more stable elements via beta minus decay.
(c.) Uranium is highly radioactive, and becomes even more activated under a thermal neutron flux.
(d.) Af ter fission, the fission products are very neutron deficient and therefore decay into more stable elements via beta plus decay.
ANSWER H.06 (b.)
[+1.0]
Re4erence(s) H.06 1.
Generic: Stephenson, R., McGraw-Hill.
.
-Section H Continued on Next Page-
.
t Manhattan College Page 7 June 3, 1986 Points Available QUESTION H.07 JWh is the worth of a control rod dependent on the position of that control rod?
(2.0)
ANSWER H.07
-
The reactivity effect, i.e., worth, of a control rod depends on the impact that the material of the control rod has on the absorption rate of neutrons (assuming a poison-type of control rod). The reactivity worth of a small-sized absorber can be expressed as dependent on the frelative) neutron flux in the l
i vicinity of the absorber [+1.0; and the position in the core
[+1.0] and the impact that a change in that location will have
'
on the total neutron population. Mathematically, the result is i
that the effect is proportional to the square of the neutron flux at the location where the change is made in absorber concentration.
Hence, changing the amount of absorber material
'
near the center of the reactor core will have the largest effect on reactivity.
Reference (s) H.07 1.
Generic:
Stephenson, R., McGraw-Hill.
,
-Section H Continued on Next Page-
--_
.
- -
.-. -
-
_
. _.
. - -
_
_ -. _ -.
-
- _ -.
.
.
.
Page 8 Manhattan College June 3, 1986 Points Available
.
'
,
QUESTION H.08 If the Reactor is shutdown by 5% delta k/k with a count rate (CR) of 10:
a.
How much positive reactivity would have to be added to double the count rate? Show work.
(1.0)
b.
Would it take (MORE/LESS/THE SAME) reactivity change to reduce the count rate by one half?
(1.0)
c.
Explain why there is a difference between the values obtained for part (a.) and part (b.) above.
(1.0)
ANSWER H.08 CR 2 = I~K CR
p 1,g k
a.
1-KI 2 = 1,g 2-K2 " I-K1
K +1
K 1-0.05 0.95 K2"
1
'9 +
0.975 K2
Reactivity added = 0.975 - 0.95 = 2.5% delta k/k
[+1.0]
b.
It would take MORE
[+1.0]
The count rate is inversely dependent on delta k.
Hence, c.
for any initial value of delta k and CR it will take more change in delta k to reduce the CR than to increase the CR.
[+1.0]
Reference (s) H.08 1.
Generic:
G. A. TRIGA Trainino Manual, " Reactor Theory",
Chapter 6.
-Section H Continued on Next Page-
.
. - - - - -
-.., _.
- - -
_
_
.
_
.
.
Page 9 Manhattan College June 3, 1986 Points Available 00ESTION H.09 Choose, by specifying a letter designation, the most correct statement from those given below.
(1.0)
(a.) The unit (of measure) of the " barn" is a measure for the macroscopic neutron cross section.
(b.) Delayed neutrons have a harder energy spectrum at birth than neutrons produced from the fission of U-235 by thermal neutrons.
(c.) The microscopic cross section for neutron interaction depends upon the isotopic composition of the material and of the energy of the neutron.
(d.) The reaction rate for neutron absorption in a given material is inversely proportional to neutron flux.
ANSWER H.09 (c.)
[+1.0]
Reference (s) H.09 1.
Generic:
Academic Program for Nuclear Power Plant Personnel, Volume 1, General Pnysics Corporation, p. 4-25f.
j i
i
}
-Section H Continued on Next Page-
-
- -.
.
.
.
Page 10 Manhattan College June 3, 1986 Points Available OUESTION H.10 Consider the " Doppler broadening" effect that takes place in the fuel of the reactor. As the temperature of the fuel increases, what parameter of the six-factor formula pre-dominantly is affected and what impact does this have on K,ff?
(1.0)
ANSWER H.10 As the fuel temperature increases, the widening of the resonance peaks causes the resonance escape probability [+0.5] to decrease and hence, for K,ff to decrease [+0.5].
Reference (s) H.10 1.
Generic: Technical Education Research Center-Southwest,
" Nuclear Technology," pp. 12-7-8 to 12-1-9.
QUESTION H.11 How does p differ from p ff (larger / smaller) in the MCZPR Reactor S
(2.0)
and briefly explain why.
ANSWER H.11 is larger [+0.5].
Delayed neutrons are born with lower p [bgies (hence, fewer fast fissions), greater thermalization, e8 less fast neutron escape.
Resulting in more thermal neutrons present [+1.5].
Hence,p,ff is larger.
Reference (s) H.11 1.
Generic:
NUS, Vol. 3, p. 5.3-3.
i-Section H Continued on Next Page-
-_
__
__
___ _
__
_ _ _, _ _ _. _._- _ _ ---
_ - -
-. -
,
-
.
-
.
.
Page 11 Manhattan College June 3, 1986 Points Available QUESTION H.12 How is a chain reaction in a reactor described quantitatively, i.e., what is k, the multiplication factor?
(1.0)
ANSWER H.12 No. of neutrons in one generation
= a ratio = No. of neutrons in preceeding generation
[+1.0]
Reference (s) H.12 1.
Generic:
Introduction to Nuclear Engineering, J. R.
Lamarsh, p. 102.
QUESTION H.13 Calculate the reactivity for a.
Keff = 1.004 (1.0)
b.
K,ff = 0.% 6 OO ANSWER H.13 k(<-'1oogi e
= 0.00398
[+1.0]
a.
.
,
'
gj
= 0.00402
[+1.0]
b.
=
g Reference (s) H.13 1.
Generic: Academic Program for Nuclear Power Plant Personnel, Volume II, General Pnysics Corporation, p. 4-95.
-End of Section H-
. _ -
_
...
. _ -.
__.
.-
.
.
Page 12 Manhattan College June 3, 1986 Points Available I.
RADIOACTIVE MATERIAL HANDLING, DISPOSAL AND HAZARDS (19.0)
00ESTION I.01 A target has been irradiated in the MCZPR.
a.
You anticipate that the target contains only one stable isotope of one low-Z element that has undergone a neutron absorption [(n,7) reaction]; you anticipate that the radioactive decay of the resulting radioactive isotope is a one-step decay to a new stable isotope. What type (s)
of emissions would you anticipate would come from the radioactive target after it is removed from the reactor?
Justify your answer.
(1.5)
b.
After you have removed the target from the reactor, and over a period of time record the count rate from a detector placed next to this target, how would you determine the half-life of the radioactivity?
(1.5)
ANSWER I.01 a.
If a stable isotope of an element absorbs a neutron, it will form a new isotope that is above the line of stability [+0.75).
Isotopes of low-Z materials that are above this "line" usually decay toward the "line" by p-emission.
Such p-emissions may be preceded by or may include the emission of one or several 7s
[+0.75].
-Section I Continued on Next Page-
's
.
.
Page 13 Manhattan College June 3, 1986 Points Available ANSWER I.01 (contd)
b.
The radioactive decay of a single radioactive isotope will follow the exponential decay law.
-At Ag=Ae
[+0.5]
c-U A2=Ae
g-X(t -t )
i 2
=e A2 in Ag - in A2 = -1(t -t )
i 2 in A - in A
[+1'0]
A
"
t -t2 i
then, 0.693 1/2 *
A
,
Graphically, you can plot in A(t) versus t and the slope of the graph is -A.
[+1.5]
[+1.5 max.]
Reference (s) I.01 1.
Generic:
Technical Education Research Center-Southwest, pp. 1-7 to 1-12.
_
-Section I Continued on Next Page-
.
.
Page 14 Manhattan College June 3, 1986 Points Available 00ESTION I.02 If the target of QUESTION I.01 had been placed in the MCZPR and the reactor brought to 100% of full power, sketch the activity of the target as a function of time and provide the equation for the shape.
(2.0)
-
ANSWER I.02 A
Act.
-
A = Et(1-e-At)
[+1.0]
t
.
[+2.0] for shape Reference (s) I.02 1.
Generic: Technical Education Research Center-Southwest, p. 1-15.
l l
l f
l-Section I Continued on Next Page-
. - _..- - _ _
.--_.
,_
_-.
. - _ -. _.
... -.-.
.
.
-
-....
.
.
Page 15 Manhattan College June 3, 1986 Points Available 00ESTION I.03 Explain how each type of radioactive contaminants are removed from the reactor coolant.
(1.0)
ANSWER I.03
'
Particulate by filtration; soluable by ionic exchange
[+1.0]
Reference (s) I.03
1.
Manhattan College: MCZPR Radiation Safety Manual, Section 6.8, p. 6-3.
QUESTION I.04 Define " Radiation Area" as specified in 10 CFR 20.
(1.0)
-
ANSWER I.04 sco pe g
) 5 sem/hr [+0.5] and > 306 mrem /5 days
[+0.5]
Reference (s) I.04 1.
Generic:
10CFR20.202.[7)
!
,
-Section I Continued on Next Page-
!
__
_
__
_
_
_
_
__
.
_
.
.
Manhattan College Page 16 June 3, 1986 Points Available
..
00ESTION I.05 Describe the production...J G th; id ' t of:
(1.0)
a.
AR-41 (1.0)
b.
N-16 ANSWER I.05
U*7 1.82 ',,a-- [+1.0]
O * 18 a.
(n 7)
OnI + 18 Ar Ar l
16, }p 7.
acr [+1.0]
b.
(n,p)
0"
+80
+7N Reference (s) I.05 1.
Generic:
Stephenson, R., McGraw-Hill.
i
!
l.
l l
-Section I Continued on Next Page-
... - -., - --
-
.
-, _ _
.- - - ----
.
--
.. -,.
- _ - _ -..... -
--.
.
Manhattan College Page 17 June 3, 1986 Points Available QUESTION I.06
--
If 2 centimeters of lead will reduce gamma radiation level
~
from 100 mr/hr to 50 mr/hr, how many centimeters of lead will
'be required to reduce a gamma radiation level from
'
a.
400 mr/hr to 50 mr/hr (1.0)
b.
50 mr/hr to 25 mr/hr (1.0)
Which makes a better shield, lead or water? Explain why.
(0.5)
c.
ANSWER I.06 a.
6 cm
[+1.0]
b.
2 cm
[+1.0]
c.
Lead - greater density [+0.5]
_ Reference (s) I.06 1.
Generic: Technical Education Research Center-Southwest, pp. 1-24, 1-25, 2-1, 2-2.
l l
l
\\
i
,
.
-Section I Continued on Next Page-
-.
..
. -
-
-..
_ -.
..
,....
a Manhattan College Page 18 June 3, 1986 Points Available QUESTION I.07 a.
Define rem. Clarify whether or not a rem is a mea.ure of energy or a measure of biological damage.
(1.0)
b.
Is a rad received as a result of alpha radiation equivalent to a rad received as a result of gamma radiation? Explain. (1.0)
.
ANSWER I.07 Rem reflects the amount of energy dissipated and biological a.
damage derived from such energy dissipation.
[+1.0]
b.
NO [+0.5].
Alpha has a quality factor of 20 [+0.5]
.
l Reference (s) I.07 1.
Manhattan College: MCZPR Radiation Safety Manual, Sections 2.1.1.3 and 2.1.1.5, p. 2-1.
(
l-Section I Continued on Next Page-l
. _.. _ -. -.. -
,. -. - -. - - - _ - - _ _. _ -
_
- - -
_-
.
<
Page 19 Manhattan College June 3, 1986
i Points Available OUESTION I.08 If the gamma-ray radiation level from a pump (point source)
had been 30 mr/hr 1 foot from the pump, what would be the
~ radiation level 10 feet from the pump?
(1.0)
ANSWER I.08 Neglecting gama-ray absorption by the air, distance factor = (f)
[+0.5]
=
100 rad level (10) = rad level (1)/100
= 0.30 mr/hr.
[+0.5]
i i
Reference (s) I.08 1.
Generic: Nuclear Enerav Training, Module 5, " Radiation Protection", pp. 3.3-1 to 3.3-4.
-
-Section I Continued on Next Page-
.
_ _ - - - - - -
-
-
-
- _ _ _
_ _ _ _ __
_ _ _
.
.
a
.
Manhattan College Page 20 June 3, 1986 Points Available 00ESTION I.09 If a man had been exposed to 0.01 R gamma radiation, 0.04 rad of beta radiation and 0.02 rad of fast neutrons, what is his total biological dose in rems? Show your work.
(2.0)
ANSWER I.09
.
0.01 R of gamma x 1 QF = 0.01 rem 0.04 rad of beta x 1 QF = 0.04 rem 0.02 rad of prompt neutron x 10 QF = 0.20 rem Total dose
= 0.25 rem
[+0.25 for dose equation, +2.0 for answer, +2.0 max.]
i
Reference (s) I.09
1.
Generic: Nuclear Eneroy Training, Module 5, " Radiation Protection", pp. 2.1-1 to 2.1-3.
2.
Generic: Technical Education Research Center-Southwest, p. 2-3.
3.
Generic:
10 CFR 20.4, p. 234.
_
.
-Section I Continued on Next Page-j
.
-.
_ _. _
_. _ _. _,
_
_ _ _ _
.
-.
_
_
_ _.
._
.
.
Manhattan College Page 21 June 3, 1986 Points Available OVESTION I.10 Explain how solid radioactive waste is handled at the MCZPR, include any precautions and how labeled.
(2.5)
ANSWER I.10 Cans marked CONTAMINATED WASTE, COLD WASTE, and CONTAMINATED GLASSWARE will be provided as needed. These cans shall be polyethylene-lined and shall not be filled so as to prevent closure of the polyethylene bag liner. The cans should be foot-operated to reduce the possibility of spread of contamination by handling the lid.
Extreme care should be exercised in keepina contaminated waste out of the cold waste cans, and vice versa.
The cans will be monitored regularly by the Health Physicist
,
'
and shall be marked with the normal radiation sign if the radia-tion field is creater than 2.5 mR/hr at any point outside the Persons placing material in the can that has sufficient can.
activity to produce such a field must notify the Health Physicist.
[+1.0]
The essence of the above will be accepted for the answer.
Reference (s) I.10 1.
Manhattan College: MCZPR Radiation Safety Manual, Section 6.2.1, p. 6-1.
-End of Section I-
.-
-
...
-. -..
- - - -. -..
...-
- -.-
- - --
.
.
Manhattan College Page 22 June 3, 1986 f
Points I
Available
_
J.
SPECIFIC OPERATING CHARACTERISTICS (20.0)
00ESTION J.01 Answer the following questions TRUE or FALSE.
If answer is false, state why.
(3.0)
A mercury thermometer is an acceptable monitor of pool a.
temperature, b.
Explosives can be irradiated in or near the core.
The maximum reactivity insertion rate by rod withdrawal is c.
'
0.01 delta k/k/sec.
j ANSWER J.01 i
a.
FALSE [+0.5]
(corrosive to aluminum)
[+0.5]
b.
FALSE
[+0.5]
(not licensed for explosives) [+0.5]
c.
FALSE [+0.5]
(0.001 delta k/k/sec)
[+0.5]
Reference (s) J.01 1.
Manhattan College: MCZPR Technical Specification, Section 3.8.3, B/C, p. 3-11.
2.
Manhattan College: MCZPR Technical Specification, Section J.2, pp. 16-23.
-Section J Continued on Next Page-
.--
. -. _
__
_
-_.
. - _. - -
. _.
. -.
_
_ - _.
_.
_--
___
__
.
.
Manhattan College Page 23 June 3, 1986 Points Available OVESTION J.02 What is the purpose of the bypass switch "A" in the Safety System and why is it needed?
(1.0)
-
ANSWER J.02 Bypass to eliminate a reverse [+0.25] as gamma recorder being downscaled [+0.25), utilized during startup [+0.25] until gamma recorder reads on-scale [+0.25]
Reference (s) J.02 1.
Manhattan College: MCZPR Technical Specification, Table 3-1, p. 3-4.
OUESTION J.03 What is the maximum rod withdrawal speed allowed at the MCZPR?
(0.5)
ANSWER J.03 12 inches per minute [+0.5]
Reference (s) J.03
,
1.
Manhattan College: MCZPR Technical Specification, Section 4.2.3B, p. 4-2.
1
,
.
-Section J Continued on Next Page-
-
- _ _ - _ _ _ _ _ _ -
.
.
Manhattan College Page 24 June 3, 1986
Points Available QUESTION J.04 What are the neutron absorbing materials in (1.5)
a.
the shim rod?
b.
the regulating rod?
ANSWER J.04 a.
cadmium and stainless steel
[+1.0]
b.
stainless steel
[+0.5]
Reference (s) J.04 1.
Manhattan College: MCZPR SAR, Section 4.2, p. 4-1.
OVESTION J.05 What three (3) conditions of the count rate channel will cause a reverse trip?
(1.5)
ANSWER J.05 1.
count rate recorder off [+0.5]
2.
( 2 cps
[+0.5]
!
3.
> 50,000 cps
[+0.5]
[
Reference (s) J.05 l
1.
Manhattan College: MCZPR Technical Specification,
Table 3-1, p. 3-4.
-Section J Continued on Next Page-
.
.
.
Manhattan College Page 25 June 3, 1986 Points Available
.
QUESTION J.06 In reference to the moderator temperature coefficient, Explain what is meant by Jhe turnover point.
(2.0)
a.
b.
At what temperature does the turnover point occur?
(0.5)
ANSWER J.06 The MCZPR temperature coefficient is positive and excess a.
reactivity increases with an increase in temperature [+1.0]
at which point, the turnover point, becomes negative with a further increase in temperature reducing excess reactivity
[+1.0].
b.
110. 6*F [+0.5]
Reference (s) J.06 1.
Manhattan College: MCZPR Technical Specification, Section 3.1.4 Bases, p. 3-1, 2.
Manhattan College:
Experimental Determination of the Temperature Coefficient of Reactivity of the MCZPR.
i f-Section J Continued on Next Page-I l
-
--~-
.-.-
.
.
_
_ _ _ _ _
_ __
_
_
.
.
Page 26 Manhattan College June 3, 1986 Points Available OUESTION J.07 For the two (2) radiation monitoring channels, Gamma 1 and Gamma 2, gjyve the locations, the alarm set points and the (3.0)
ranges.
ANSWER J.07
.e Gamma 1 - on the reactor platform over the core
[+0.5]
6 mr/hr [+0.5]
0.01 to 100 mr/hr
[+0.5]
Gamma 2 - on the side of the reactor tank
[+0.5]
10 mr/hr [+0.5]
0.01 to 100 mr/hr [+0.5]
Reference (s) J.07 1.
Manhattan College: MCZPR Technical Specification, 3.7.3 A, B and C, pp. 3-9.
QUESTION J.08 List four (4) automatic scrams and their appropriate setpoints.
(4.0)
ANSWER J.08 1.
count rate channel [+0.5]
125% full power [+0.5]
2.
linear power channel [+0.5]
125% full power [+0.5]
3.
high gamma activity [+0.5]
s 10 mR/hr [+0.5]
4.
low water level [+0.5] 6 ft [+0.5]
Reference (s) J.08
,
1.
Manhattan College: MCZPR Technical Specification, Table 3-1, p. 3-4.
-Section J Continued on Next Page-
.
.
Page 27 Manhattan College June 3, 1986 dr Points Available 00ESTION J.09 Can the MCZPR be taken critical with no water in the reactor tank?
(Consider physics, not administrative or control
'ci rcuitry.)
Explain your answer and include calculations you make to confirm the reactor critical or subcritical.
(3.0)
,
ANSWER J.09 No, the reactor cannot go critical [+0.5].
Void coefficient is -5.8 x 10-s% Ak/k [+0.5].
Water volume in the core is 55,000 cc [+0.5]. Negative reactivity effect = -5.8 x 10-s x 55,000 -
t
!
-0.32% Ak/k [+0.5].
Maximum core reactivity = 0.29% Ak/k [+0.5]
I
. suberitical by 0.03% Ak/k with all rods out
[+0.5]
~ ! r r' e ' T e Ale vid>t wr ANy $
1 opa nc e* g x on A,ve7 t-a W I a-
-
c A c c itor CO Reference s)
.09 1.
Manhattan College: MCZPR SAR, Section 15.2. p.15-1.
2.
Manhattan College: MCZPR SAR Void Coefficient Measurements, Appendix G.
-End of Section J-
,
a
!l i
l, I
t
.
.
Page 28 Manhattan College June 3, 1986 Points Available K.
FUEL HANDLING AND CORE PARAMETERS (20.0)
OUESTION K.01 How and where (physical location) are the fuel elements that are not currently installed in the core stored? Include the methods use to insure they are physically secured.
(3.0)
ANSWER K.01 These fuel elements are permanently stored in a locked steel container [+0.5] (8-1/4 inches x 8-1/2 inches x 50 inches made of 1/16-inch steel sheet metal). The steel container is fastened to the floor [+0.5] of the first floor of the MCZPR Room. [+0.5]
(The container has a shelf welded inside it.)
The three fuel plates are placed on the shelf and secured with metal straps
[+0.5].
The metal straps are welded to the shelf [+0.5].
The container has a hinced cover which is kept padlocked [+0.5].
Reference (s) K.01 1.
Manhattan College: MCZPR SAR, Section 9.1.1, p. 9-1.
-Section K Continued on Next Page-
_ _ _
- --
- - -
..
.
Page 29 Manhattan College June 3, 1986 Points Available OUESTION K.02 Give the definition of shutdown margin.
(2.0)
ANSWER K.02 Shutdown margin - Shutdown margin shall mean the minimum shutdown reactivity necessary to provide confidence that the reactor can be made subcritical by means of the control and safety systems [+0.5] starting from any permissible operating condition
[+0.5] although the most reactive rod is in its most reactive position [+0.5), and that the reactor will remain subcritical without further operator action [+0.5].
Reference (s) K.02 1.
Manhattan College: MCZPR Technical Specification Definitions, p.1-4.
,
l l
!
!
I-Section K Continued on Next Page-
+
,
- - -.
. _.
_
.-.
. _.. _ _..
...-
-
-.
'
.
Page 30 Manhattan College June 3, 1986 Points Available
,
OUESTION K.03 What is the source material and the nuclear reaction that a.
produces source neutrons?
(2.0)
b.
Approximately how many neutrons are generated per second.
(1.0)
ANSWER K.03 a.
A Pu-Be source
[+1.0]
12 + On [+1.0]
2a4+4e
)6C B
b.
Approximately 10 neutrons per second
[+1.0]
Reference (s) K.03
,
1.
Manhattan College: MCZPR Technical Specification, Section 5.3.4, p. 5-4.
QUESTION K.04 What is the Technical Specification limit for the reactivity worth of any single experiment?
(1.0)
t ANSWER K.04
+ 15.0 x 10~4 Ak/k
[+1.0]
Reference (s) K.04 1.
Manhattan College: MCZPR Technical Specification, Section 3.8.3F, p. 3-12.
-Section K Continued on Next Page-
.
,. - - - - - -
,
.,-
-
, _ - - -
, -, - -,
, -
..
.
Page 31 Manhattan College June 3, 1986 Points Available OUESTION K.05 Explain why, relative to the safe operation of the reactor, the location of the experiment in the core is an important
' consideration.
(2.0)
ANSWER K.05 Experiments which could adversely affect proper operation of the control rods must be avoided for obvious reasons. [+1.0]
Experiments which shadow any nuclear instruments can give erroneous or unreliable information to the reactor operator.
[+1.0]
Reference (s) K.05 1.
Manhattan College: MCZPR Technical Specification, Section 3.8.4A, p. 3-12.
QUESTION K.06 If fuel elements need to be removed from the core for purposes of preventive maintenance, what will they be stored in and where will they be stored?
(1.5)
.
ANSWER K.06 If fuel elements need to be removed from the core for purposes of preventive maintenance, they w]ill be stored in their original Sylcor shipping containers [+1.0 on the first floor of the MCZPR Room. [+0.5]
,
Reference (s) K.06
-
1.
Manhattan College: MCZPR SAR, Section 9.1.3, p. 9-1.
-Section K Continued on Next Page-
, _ - - - - - - -.
- - _ -,.. -. _ ___ -.-
.
-.
.
-._
.
O Page 32 Manhattan College June 3, 1986 Points Available OUESTION K.07 Give the definition of excess reactivity.
(2.0)
ANSWER K.07 Excess reactivity is that amount of reactivity [+0.5] that would exist if all control rods [+0.5] (control, regulating)
were moved to the maximum reactive condition [+0.5] from the point where the reactor is exactly critical [+0.5] (keff = 1).
Reference (s) K.07 1.
Manhattan College: MCZPR Technical Specification Definitions, p. 1-1.
OVEST10N K.08 What is the maximum rod drop time allcwed by Technical Specification?
(0.5)
ANSWER K.08 The drop time for either safety rod shall not exceed 1 second.
[+0.5]
Reference (s) K.08 1.
Manhattan College: MCZPR Technical Specification, Section 3.2.1C, p. 3-2.
i
t-Section K Continued on Next Page-
.
-.
-...
n
- - -
.---. -
- _.
_
_.
.
,
e Page 33 Manhattan College June 3, 1986 Points Available OVESTION K.09 Explain why it is impossible for the MCZPR to go prompt critical.
(1.0)
.
ANSWER K.09 p,
MCZPR core excess reactivity 4:29% ( beta 0.654% = 1.0$ [+1.0]
Reference (s) K.09 1.
Manhattan College: MCZPR SAR, Section 15.2, p. 15-1.
.,
i QUESTION K.10 Answer TRUE or FALSE.
If answer is false, state why.
(1.5)
...
a.
The fine control rod indicators determine the position of the control rod to within 0.01%.
b.
The course control rod indicators determine the position of the control rods to within 2.0%.
ANSWER K.10 a.
False
[+0.5] 0.1%
[+0.5]
l b.
True
[+0.5]
Reference (s) K.10
,
1.
Manhattan College: MCZPR SAR, Section 7.2.1, p. 7-2.
!
.
-Section K Continued on Next Page-
. _ -.
-
. - _ - - - -. _. _,
_. -. _ _ _ _
_
.-_ _
.
- -
- -
..
.
Page 34 Manhattan College June 3, 1986 Points Available 00ESTION K.11 What is the negative worth of a.
the regulating rod?
(0.5)
b.
the shim rod?
(0.5)
ANSWER K.11 a.
0.90% Ak/k (1.40$)
[+0.5]
b.
2.50% Ak/k (3.88$)
[+0.5]
Reference (s) K.11 1.
Manhattan College: MCZPR Technical Specification, Section 3.2.3B, p. 3-2.
,
l-Section K Continued on Next Page-
.
Page 35 Manhattan College June 3, 1986 Points Available OUESTION K.12 Give three (3) possible methods of introducing maximum excess reactivity into the reactor during operation.
(1.5)
ANSWER K.12
-
1.
All the circuits of the reactor protection system were to fail simultaneously, and the operator withdraws both control rods completely.
This is extremely unlikely to happen.
[+0.5]
2.
The operator deliberately withdraws both rods completely allowing the reactor to operate at a power level that
would exceed the maximum allowable limit of 0.1 watt. [+0.5]
.
l 3.
A sample having very high cross section could be inserted into the core and both control rods could be withdrawn
'
completely without exceeding the allowable power limit.
If the sample is withdrawn without reinsertina the control roos, maximum excess reactivity could occur. [+0.5]
Reference (s) K.12 1.
Manhattan College: MCZPR SAR, 15.2.1, p. 15-1.
-End of Section K-
'
,
t I
.. _ _ - _.
, _ _ _ _ _ _ _ _.
, _ _ _ _ -
. -
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -. _.
.-
.
.
Page 36 Manhattan College June 3, 1986 Points Available L.
ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS (20.0)
00ESTION L.01 What is the difference between a channel check and a channel
test?
(2.0)
.
ANSWER L.01 A channel check is a qualitative verification of acceptable performance by observation of channel behavior.
This verification, where possible, shall include comparison of the
'
channel with other independent channels or systems measuring I
the same variable.
[+1.0]
A channel test is the introduction of a signal into the channel
'
for verification that it is operable.
[+1.0]
i Reference (s) L.01 1.
Manhattan College:
MCZPR Technical Specification Definitions, p. 1-1.
.
i t-Section L Continued on Next Page-
_ _. - -.. _ _ _
. -
. - _ _ _ _ _ _, _ _ _ _ _ _ _ _. _. _ _ _
- -.
.
..
_ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _
-
. _ _ _
-
e
.
Page 37 Manhattan College June 3, 1986 Points Available 00ESTION L.02 What is the emergency classifftation for:
a.
A fire that may effect any reactor safety system (s)?
(0.5)
b.
Tornado or hurricane winds that are damaging the reactor structure?
(0.5)
ANSWER L.02 a.
Ab i i.
[+0.5] TJ o NM*'" *
0"***!
E b.
E te er : ::: T ary [+0.5] henbMh [ L As M h Reference (s) L.02 1.
Manhattan College: MCZPR Emergency Plan, ?.pp;r. dix I, N f3
/ 7 i-Section L Continued on Next Page-I
-
.-
.
.
- -.
.
-
. -._. --. -
_
--
-
.
___
-..
.
O-a Page 38 Manhattan College June 3, 1986 Points f
,
Available
\\
'
OUESTION L.03
.
'
i What is the minimum staffing when the roector is not secured
-
and where would they be located?
(3.0)
ANSWER L.03 The minimum staffing when the reactor is not secured shall be:
a.
A licensed Reactor Operator in the control room [+1.0]
b.
A licensed Senior Reactor Operator present in the Leo i
Engineering Building
[+1.0]
l Ahealthphy] sics-qualifiedindividualcontactableby c.
phone
[+1.0 Reference (s) L.03 1.
Manhattan College: MCZPR Technical Specification, Section 6.1.3, p. 6-3.
l l
J
!
I
,
o
'
<
-
,
,
.,
l
-'
t.
'
-Section L Continued on Next-Page '
.
-
e
-.
a
_._
. -, -
-
.
._
,
.
_
P
.
.
Page 39 Manhattan College June 3, 1986
Points
--
Available OUESTION L.04 What four (4) conditions must be satisfied for the reactor to
,
be considered secured when it contains all of its fuel?
(3.0)
ANSWER L.04 A combination of all of the following:
1.
All neutron absorbing control rods are fully inserted and other safety devices are in shutdown position, as required by the technical specifications
[+0.75]
2.
The console key switch is in the off position and the key is removed from the lock
[+0.75]
3.
No work is in progress involving core fuel, core structure, installed control rods, or control rod devices unless they are physically decoupled from the control rods [+0.75]
4.
No experiments are in or near the reactor [+0.75]
Reference (s) L.04 1.
Manhattan College:
MCZPR Technical Specification Definitions, p. 1-3.
I i
.
!
i
~
-Section L Continued on Next Page-
_ _ _ _
~
. _ _
..
.
.
...
__
w
.
.
Page 40 Manhattan College June 3, 1986
-
Points Available s
QUESTION L.05 List the four (4) records that are to be retained for the TTTetime of the MCZPR facility.
(3.0)
.
.
ANSWER L.05
-,
1.
Gaseous and liquid radioactive effluents, if any, released toLthe environs
[+0.75]
2.
On-site e'nvironmental monitoring surveys required by the Technical Specifications
[+0.75]
i 3.
Radiation exposure for all personnel monitored
[+0.75]
'
4.
Drawings of the reactor facility.
[+0.75]
,
i
.
b
~
Reference (s) L.05 1.
Manhattan College:
MCZPR Technical Specification, Section 6.7.3, p. 6-13.
',
OUESTION__ L.06
_
Define 'an unsctieduled shutdown as defined by Technical
'
Specifications.
(2.5)
ANSWER L.06
- i An unscheduled shutdown is defined as any unplanned shutdown
'
(
of the reactor caused by actuation of the reactor safety system
'
[+0.5], operator error [+0.5], equipment malfunction [+0.5], or f l'
a manual shutdown in response to conditions which could adversely affect safe operation [+1.0], not-including shutdowns which t
occur during testing or check-out operations.
Reference (s) L.06 1.
Manhattan College:
MCZPR Technical Specification
'
Definitions, p.1-4.
-Section L Continued on Next Page-
.
k s
-
_
..
-.
.
.
. ---
.
.-. - --
e
.
.
.
Page 41 Manhattan College June 3, 1986
.
Points Available 00ESTION L.07 In case of a bomb threat, unauthorized intrusion or civil disorder, who is to be notified?:
(1.0)
ANSWER L.07 In case of a bomb threat, unauthorized intrusion,-or civil disorder, the campus security officers [+0.5] and the New York City Police Department will be notified [+0.5].
g\\ fewh Reference (s) L.07 1.
Manhattan College: MCZPR -fiassegury Plan, p. 8.
QUESTION L.08 When is the reactor considered to be shutdown?
(1.5)
ANSWER L.08 The reactor is shut down if it is suberitical by at least one dollar [+0.75] in the reference core condition and the reactivity worth of all experiments is accounted for [+0.75].
!
!
!
Reference (s) L.08 l
1.
Manhattan College: MCZPR Technical Specification
Definitions, p.1-3.
i i
t
.'
l-Section L Continued on Next Page-l
_ _ _ - -
a
'
-
e Page 42 Manhattan College June 3, 1986 i
Points
Available i
QUESTION L.09
!
I List six (6) of the types of laboratory exercises that can be conducted in the MCZPR without the presence of a reactor I
supervisor.
(3.0)
ANSWER L.09 1.
Startup and Operation of Manhattan College Zero Power Reactor: Approach to Criticality 2.
Critical Mass Determination 3.
Reactor Period and Reactivity 4.
Void Coefficient Measurement
- l 5.
Flux Distribution in the Manhattan College Zero Power Reactor 6.
Determination of Buckling 7.
Measurement of Diffusion Length and Age 8.
Temperature Coefficient of Reactivity 9.
Gamma Ray Energy Spectrum in the Vicinity of the Reactor Core
'Y #
'
Any six (6) [+0.5] each.
k fn;c ebv-res A hea/$ p yp%f P*dSwS
^
Reference (s) L.09
.
1.
Manhattan College: MCZPR Technical Specification,
,;
Section 3.8.3E, p. 3-12.
g i
!
.
-End of Section L-
-End of Exam-
a
4
____________________________________________________________________________
IQUATION FORMULA AND PARAMETER SHEET
____________________________________________________________________________
.
.
Where mi = m2 (density)3(velocity)3(area)i = (denstty)2(velocity)2(area)2
_________________________________-__________________________________________
1 1 = PE +KE #Ii 2 where V = specific KE = "V PE = mgh PE + KE +P Y Y
2
y volume P = pressure
____________________________________________________________________________
Q = mc (T-Tin)
Q = UA (T-Tstm)
Q = m(h -h )
i p p out ave
____________________________________________________________________________
= IO - #I P = P 10(SUR)(t)
p, p,t/T SUR = 26.06 T=
"
o o
T p
p X,ff
___________________________________________________________________________
CR (1-K,ffy) = CR (I-Keff2)
CR = S/(1-X,ff)
delta K = (Keff-1)
2 (1-K,fg)
(1-K,ff) x 100%
,1 SOM =
X'ff = 0.08 sec M = (1-Keff2)
eff K
____________________________________________________________________________
= A e (decay constant)x(t)
decay constant = in (2) = 0.693
-
A t
t
g 1/2 1/2
____________________________________________________________________________
Water Parameters Miscellaneous Conversions l
1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs
3 1 ft = 7.48 gallons I hp = 2.54 x 10 Btu /hr j
6 Density = 62.4 lbg/ft 1 MW = 3.41 x 10 Btu /hr
.
Density = 1 gm/cm 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters2 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft-lbm/lbf-sec 1 ft H O = 0.4335 lbf/in.2
____________________________________________________________________________
., -,
-. -..
.--
%
a e'.
d EQUATION SHEET
-
-
h*-AN S.U.R. - 26/r-N it=Ne HVL = 0.693/p o
t1/2 = 0.693/A N = S/1-k,ff f
P=Pe/r t
A = AN o
.
P=P M D o
-
A=Aen
+
Stay time =
8" i+ r dos te
Id
"Id 3i
R/hr 9 1 foot = 6 CE I=IeM
-
c CR (1-keff ) = CR (1-keff)
2 i
i
i:
_.
_
...
.. - _ _..
_ _. _ _ _ _. - _ _ _ _ _. _ _
.
..
- - - -. -. - -
.
_ _ _ _ _ _ _ _ _.,. _ _
O ATTACHMENT 2 FACILITY COMMENTS RESOLUTION QUESTION I.05 QUESTION I.05 It seems unreasonable to expect Accepted. Deleted half-lives from a candidate to have memorized answer.
the half-lives of a large number of radionuclides.
QUESTION J.09 QUESTION J.09 No quantitative answer should Accept any reasonable explanation be require 3.for this answer.
without calculation.
If there is no water in the reactor, there is no moderator to sustain a critical reaction.
QUESTION K.09 QUESTION K.09 The MCZPR core excess reactivity Answer key changed to 0.44% delta is 0.44% delta k/k.
The change k/k.
of excess reactivity from 0.3%
delta k/k to 0.44% delta k/k was approved in a letter dated April 17, 1968 from Donald J.
Skovholt of the U.S. Atomic Energy Commission.