IR 05000002/1987001
| ML20215K367 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 05/04/1987 |
| From: | Burdick T, Hare E, Ridgway K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20215K360 | List: |
| References | |
| 50-002-87-01OL, 50-2-87-1OL, NUDOCS 8705110170 | |
| Download: ML20215K367 (47) | |
Text
.
.
.
U.S. NUCLEAR REGULATORY-COMMISSION
REGION III
Report No. 50-002/0LS-87-01(DRS)
Docket No.50-002 License No. R-28
,
Licensee:
University of Michigan Phoenix Memorial Laboratory Ann Arbor, MI 48105 Facility Name:
Ford Nuclear Reactor Examination Administered At:
University of Michigan, Ann Arbor, Michigan Examination Conducted:
April 14, 1987
' d-M b N Examiners:
E. A.
re
$w 4'-27
'
Date Approved By
.u[ic, ief
Operating Licensing Section Date Examination Summary Examination administered on April 14, 1987 (Report Nos. 50-002/0LS-87-01(DRS)
to one reactor operator retake and one senior reactor operator upgrade.
Results:
Both candidates passed.
,
8705110170 870505 PDR ADOCK 05000002 PDR
,
-
. - - -.
.
-
.
. - -. -.
-,
._ -
_ - _ _________.
.
.
REPORT DETAILS 1.
Examiners E. A. Hare
- K. R. Ridgway
- Chief Examiner-2.
Examination Review Meeting Refer to the Attachment.
3.
Exit Meeting On April 14, 1987, at the conclusion of the examinations, a meeting was held to discuss generic findings made during the course of'the examinations.
The following personnel attended the meeting:
Facility Representatives:
R. Burn, Reactor Manager G. Cook, Assistant Reactor Manager NRC Representatives:
E. Hare K. Ridgway
.
The items discussed during this meeting are listed in the following paragraphs.
a.
The examiner noted that the general condition of the facility appeared to be uncluttered and neat.
b.
The examiner noted that all the material previously requested by the examiners during the October 10, 1986 examinations was received.
A controlled copy of the Administrative procedure were obtained from the.NRC III Division of Radiation Safety and Safeguards Inspector in charge of the Ford facility.
c.
The examiner noted that the candidates were cooperative with the examiners.
'l
__
.
-
_
_
_ _.
,
.
.
ATTACHMENT Examination Review Meeting An examination review meeting is no longer conducted.
The specific facility comments, followed by the NRC response, are contained in the following paragraphs.
Facility Comment:
In Section L, three questions (L.01, L.02, and L.05)
were taken directly from supplementary material that we provided at your request.
We do not require our operators to memorize that material in our training program.
The material was labelled as supplementary.
A statement was made on the binder cover and within the binder that operators require open access to the material when answering written questions about it.
We request that Questions L.01, L.02, and L.05 be deleted from the examination.
NRC Response:
Disagree.
The questions are valid and will not be deleted.
These questions fall under the scope of what the operator must know per 10 CFR 55.21(j).
All material marked as supplementary falls under the scope of written examination as outlined in 10 CFR 55 and will be covered in future examinations at the examiners discretion.
Licensee comment from letter dated February 24,.1987, pertaining to the
'
reactor operator test administered October 10, 1986.
Question A.09 (2.00)
Explain why the Doppler coefficient is an important factor in reactor stability.
Answer A.09 (2.00)
As power increases fuel temperature increases, resulting in increased thermal agitation of the fuel atoms.
(0.5) Most fuel atoms are U238, which has large resonance absorption peaks.
(0.5) The increased thermal-motion of the U238 as power increases causes more neutrons over a range of energies to have the proper energy for resonance absorption.
(0.5) Therefore, as power increases more neutrons are absorbed parasitically by the U238, reducing the core's reactivity (0.5).
,
Facility Comment:
The appropriate answer to the question as written should be something similar to:
- -
__
-
-
.
.
.
Attachment.
2-
"As reactor power increases in a transient,' fuel temperature increases.
Negative Doppler coefficient-4 -
acts to rapidly insert negative reactivity as power increases, thus tending to decrease power, and reduce the magnitude of the transient."
And the key answer-would more appropriately seem to answer.the question:
" Describe the negative Doppler. coefficient."
NRC Response:
Agree.
Both answers are acceptable for full credit.
Reference licensee material' supports both answers and will be taken into account in the future. A review of the candidates' tests showed that this question would not change their results in the October 10, 1986 examination.
.
h
,--
,
,
-
-
-
l MASTER COPY l
.
U.
S.
NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
_UNIyERgITY_QF_ MICHIGAN __
REACTOR TYPE:
_IEEI____________________
DATE ADMINISTERED: _@Zfg!fif________________
_RIgGWAY _K._____________
EXAMINER:
g CANDIDATE:
_________________________
IN@IBUCIlgN@_Ig_C@NDig@lEl Use separate paper for the answers.
Write answers on one side only.
Stcple question sheet on top of the answer sheets.
Points for each quastion are indicated in parentheses after the question.
The passing grcde requires at least 70% in each category.
Examination papers will bo picked up one (1) hour after the examination starts.
% OF CATEGORY
% OF CANDIDATE'S CATEGORY
__YebgE_ _Igl@6
___@CQ8E___
_y@LgE__ ______________C@IEGQBy_____________
_19199__ 199199
________ A.
PRINCIPLES OF REACTOR OPERATION
___________
_19199__
________%
Totals
___________
Final Grade
.
All work done on this examination is my own.
I have neither given nor received aid.
___________________________________
Candidate's Signature
__-
.
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIDNS
.
Ouring the administration of this examination the f ollowing rules apply of your application Chcating on the examination means an automatic denial 1.
cnd could result in more severe penalties.
R2stroom trips are to be limited and only one candidate at a time may
- 2.
1 cave.
You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
3.
Use black ink er dark pencil gnly to facilitate legible reproductions.
the Print your name in the blank provided on the cover sheet of 4.
examination.
5.
Fill in the date on the cover sheet of the examination (if necessary).
6.
Une only the paper provided for answers.
7.
Print your name in the upper right-hand corner of the first page of each caction of the answer sheet.
I B.
Consecuti vel y number each answer sheet, write "End of Category __" as cppropriate, start each category on a ngw page, write gnly gn gne side of the paper, and write "Last Page" on the last answer sheet.
I 9.
Number each answer as to category and number, for example, 1.4, 6.3.
j
10. Skip at least threg lines between each answer.
11. S3parate answer sheets from pad and place finished answer sheets face down on your desk or table.
,
12. Uze abbreviations only if they are commonly used in facility litetature.
13. The point value f or each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
14.' Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
15. Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND DD NOT LEAVE ANY ANSWER BLANK.
16. If parts of the examination are not clear as to intent, ask questions of the examinet only.
Yaa must sign the statement on the cover sheet that indicates that the 17.
is your own and you have not received or been given assistance in work completing the examination.
This must be done after the examination has been completed.
I
!
l l
!
!
!
.-
-
_ _.
_.
._
-
.
.
.
10. Wh n you complete your examination, you shalla c.
Assemble your examination as follows:
(1)
Exam questions on top.
(2)
Exam aids - figures, tables, etc.
Answer pages including figures which are part of the answer.
(3)
b.
Turn in your copy of the examination and all pages used to answer the examination questions.
c.
Turn in all scrap paper and the balance of the paper that you did not use f or answering the questions.
d.
Leave the examination area, as defined by the examiner.
If after is still l eavi ng, you are f ound in this area while the examination in progress, your license may be denied or revoked.
.
l l
\\
-
_
_
_
_
_
_
_,
U
.
PAGE
B __EBINCJELES_DE_BEBCIDB_QBgBBIlgN
.
QUESTION A.01 (1.00)
is 100 watts and increasing on a 30 second period.
How long Racetor power will it take for the reactor power to reach 500 kilowatts?
(N2glect heating effects.)
Show your work.
(1.0)
QUESTION A.02 (2,00)
Explain what the difference is between k-infinite and o.
k-effective.
(1.0)
b.
K-effective of a reactor is given as 1.0795 delta k/k.
What k-excess does the reactor have?
(0.5)
What reactivity is associated with this k-effective?
(0.5)
c.
QUESTION A.03 (1.50)
c.
What is the purpose of the " moderator" in the reactor?
(1.0)
b.
Indicate wh'ich one of the following is considered an important (0.5)
aspect of a good moderator.
(1)
low mass number (2)
large scattering cross section (3)
small scattering cross section
.
DUESTION A.04 (2.00)
What effect does a moderator temperature increase have on the following?
Explain each, (1.0)
c.
Core Reactivity (1.0)
b.
Control Rod Worth QUESTION A.05 (2.00)
Criefly explain the dif f erences betweens o.
Fast and prompt neutrons.
(1.0)
b.
Sl ow and delayed neutrons. (1.0)
,
!
(*****
CATEGORY A CONTINUED ON NEXT PAGE
- )
.
.
,,
.
-.
-,
.
.
PAGE
B __EBINQ1P6ES_QE_SE991gB_ggE6811gN
.
QUESTION A.06 (2.50)
Xcnon is the major fission product poison in your reactor.
c.
How is it produced?
(Include pertinent half-lives)
(3.0)
b.
How is it removed?
(Include pertinent half-lives)
(1.0)
Why does xenon reactivity ps4.x after a trip from high power?
(0.5)
c.
QUESTION A.07 (2.50)
c.
Describe the Doppler ef f ect.
(1.5)
b.
Explain why the Doppler coefficient is an important f actor in reactor stability.
(1.0)
QUESTION A.08 (2.00)
An irradiated sample removed from the reactor reads 20 Rem /hr.
Fifteen hours later it reads 10 Rem /hr.
Show your work.
What is the materials half-life?
(1.0)
a.
b.
How long will it take to decay to 100 mrem /hr?
(1.0)
,
,
(***** END OF CATEGORY A
- )
(*************
END OF EXAMINATION ***************)
--
.. - -. -.. -
__
_.. _ _ _
_.
. _ _
_
_
_.
_ _ _ _ _
-
,
,
~
EQunTION SMEET
.
-
-
.
.
Cycle efficiency = (metwork
.
f = ma e = s/t est)/(Energyto)
f
.
,
!
w = og s = V,t + 1/2 at
,
r E = sc A= [
I A = &n EE = 1/2 ov a=(Vf-V,)/t
,
PE = ogh w = e/t a = sn2/tg g = 0.893/t1/2 Vf = V, + at t
eff = ':(tu,1(t ll m
,',,,,.
,,2 ifg A=
[(g)+(t,)]
-
,
aE = 931 am
-
e = V,yAo g, g, -h g
.
.
Q = aCpat 6 = UAAT I = I,e I = I, #
j l
Pwr = M ah f
TVL = 1.3/u i
sur(t)
HVL = -0.693/u P = P 10 p = p e /T t
o SG = 5/(1 - Kgg)
SUR = 26.06/T CR, = 5/(1 - Kdfx)
SUR = 26s/t= + (s - a)T CR (1 - Kdf1) = CR II ~ Ieff2)
j
T = (**/s) + [(s - ey Io]
M = 1/(1 - Kgf)=CR/G,
.
j T = a/(e - s)
M = (1 - Kgf,)/(1-Kgfj)
SDM = (1 - Kgf)/Kdf
.
,
T = (s - e)/(Is)
,
s= = 10"4 seconds
/Kgf e = (Kgf-1)/Kgf = aKgf I = 0.1 seconds-I e=((t*/(TKgf)] + [sgf (1 + IT)]-
/
Id
i i =2.2 2 P = (s4V)/(3 x 1010)
Id gd j
2 R/hr = (0.5 CE)/d (seters)
x = eN R/hr = 5 CE/d2 (feet)
,
Miscellaneous Conversions Water Paraneters
,
10dps 1 curie = 3.7 x 10 1 gal. = 8.345 len.
1 kg = 2.21 Ita 1 gal. = 3.78 liters I hp = 2.54 a 103 Stu/hr 1 ft- = 7.48 gal.
1 sw = 3.41 x 106 Stu/hr Density = 52.4 lbs/ft lin = 2.54 cm Density = 1 ge/cd Heat of vaporization = 970 Stu/lem
- F = 9/5'c + 32 Heat of fusion = 1.u 8tu/lem
'C = 5/9 (*F-32)
1 Atm = 14.7 psi = 29.9 in. Hg.
1 BTU = 778 ft-lbf I ft. H O = 0.4335 Itf/in.
}
-
-
.-
.. _
__
. - - - -
- -
- - - -.
-. -. -
,
,
- - - - - - - _ - - - - - - - - _ _
.
PAGE G
9_ _ _EBINGig6ES_QE_BE@gIQB _QgE8911gN ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-RIDGWAY, K.
.
ANSWER A.01 (1.00)
P=Psexp(t/T)
500,000= 1008 ex p ( t /30)
In 5000=t/30 t=30*B.5=255 seconds = 4.25 minutes (1.0)
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 4 ANSWER A.02 (2.00)
K-infinite is the multiplication constant for a theoretical c.
reactor with zero leakage.
K-effective takes into account neutrons lost due to slow and fast leakage (k-eff = k-inf *
slow and fast non-leakage probability.)
(1.0)
1.0795-1 = 0.0795 delta k (0.5)
b.
k-excess = k-effective-1
=
c.
Reactivity = (k-effective-1)/k-effective = (1.0795-1)/1.0795 =
0.0736 delta k/k (0.5)
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 6
.
ANSWER A.03 (1.50)
a.
Neutrons of low energy have the highest probability of causing fission in the fuel.
Most neutrons are born at high energy l evel s.
The moderator reduces the neutron energy level.
(1.0)
b.
(1) low mass number (0.5)
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 3 i
>
-
-
-
,
. _ -.
_ _ - -
-
-
.
PAGE
B __EBINg]E6ES_gE_SE991gB_9fEB91]QN ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-RIDGWAY, K.
.
ANSWER A.04 (2.00)
Core reactivity is decreased.
(0.5)
c.
in the moderator.
The temperature increase causes a density decrease There is less moderation and more neutron leakage which is a negative reactivity effect.
(0.5)
b.
Control rod worth increases.
(0.5)
As moderation is decreased and the probability of leakage into a control rod increases, the effectiveness of the control rods increases.
(0.5)
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 6 ANSWER A.05 (2.00)
Fast neutrons refer to those at high energy levels.
(0.5)
c.
Prompt neutrons refer to those released at the time of f i ssi on.
(0.5)
b.
Slow neutrons are neutrons at low energy levels.
(0.5)
Delayed neutrons are those which appear at some time after the f i ssi on e"ent due to fission product decay.
(O.5)
REFERENCE Introduction to Nuclear Reactor Operations, Chapters 2 and 3
,
ANSWER A.06 (2.50)
c.
Directl y f rom fission.
(0.25)
From beta decay of fission products iodine 135 and tellurium 135.
(0.375)
Tellurium 135 decays to iodine 135 (19 seconds half-life) which then decays to xenon 135 (6.7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> half-life).
(0.375)
b.
Burnout by neutron absorption.
(0.333)
Beta decay to cesium 135 (0.333) with a 9.2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> half-life.
(0.333)
Iodine has a shorter half-life than xenon, so initially after a trip, c.
xenon will build up because the only removal mechanism remaining is xenon decay.
(0.5)
(Exact half-life not required, must be within 20% of actual half-life.)
i j
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 8 l
i I
{
.
--___-_
,
PAGE
e __EBINg}ELES_gE_BEggIgB_gEEBSIlgN ANSWERS -- UNIVERSITY OF MICHIGAN-97/04/14-RIDGWAY, K.
ANSWER A.07 (2.50)
As a nucleus increases in temperature, it becomes thermally agitated.
c.
(0.5)
The thermal motion of the nucleus causes neutrons over a range of energies (and velocities) to have the desired relative energy (0.5)
for absorption by the nucleus.
(0.5$
b.
As fuel temperature increases, (0.5) reactivity decreases (0.5).
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 6 ANSWER A.OB (2.00)
c.
N=Not ex p (-1 t > ], LT2 = 0.693 where T2 = hal f-li f e (0.75)
10 = 20Cexp(-0.693(15)/T2)]
T2 = (0.693) (15)/In (10/20)
(0.25)
T2 = 14.99 hrs.
(0.75)
b.
100= 20,000 Cexp(0.693(t)/14.993 14.99 in (100/20,000)(-0.693)
t
=
(0.25)
114.6 hrs.
t
=
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 2
.
l
._
__
-
__ _.,
_ - _ _ _ _ _ _ _. _
- - - _ - - - - - -. - - - - -
--
o
.
TEST CROSS REFERENCE PAGE
QUESTION VALUE REFERENCE
.________
______
__________
A.01 1.00
~ RRKOOOO364 A.02 2.00 RRKOOOO365 A.03 1.50 RRKOOOO366 A.04 2.00 RRKOOOO367 A.05 2.00 RRKOOOO368
'
A.06 2.50 RRKOOOO369 A.07 2.50 RRKOOOO370 A.08 2.00 RRKOOOO371
______
15.50
______
______
15.50
e
.
I
,
i r
,
,.,,
7--
-,- -
--
, ---
-,, - -
,, -
,n
,
+ -,,
-
.,,n
-,
_
_ _ _ _ _ _
MASTER CORY
~
~
-
.
U.
S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR DPERATOR LICENSE EXAMINATION FACILITY:
_UNIVERglTY_gF,MIGHigAN__
j REACTOR TYPE:
_TggT____________________
DATE ADMINISTERED _@ZZ93/13________________
i EXAMINER:
_HARgz_@z________________
CANDIDATE:
_________________________
IN@IBUgIlgNS_Ig_g@Ngig@IEi U32 separate paper for the answers.
Write answers on one side only.
Stcple question sheet on top of the answer sheets.
Points for each qu2ction are indicated in parentheses after the question.
The passing grcde requires at least 70% in each category.
Examination papers will be picked up six (6) hours after the examination starts.
% OF
. CATEGORY
% OF CANDIDATE'S CATEGORY
__YBLUE_ _Igl@L
___SggBE___
_y@LUE__ ______________g@lEGgBy_____________
_12:ZD__ _12t?@
________ H.
REACTOR THEORY
___________
_12:29__ _12 29
________
I.
RADIOACTIVE MATERIALE HANDLING
___________
DISPOSAL AND HAZARDS
_21z99__ _21z99
________ J.
SPECIFIC OPERATING
,
___________
CHARACTERISTICS
_29199__ _29t@9
________ K.
FUEL HANDLING AND CORE
___________
PARAMETERS
_12 D9__ _12.D9
________ L.
ADMINISTRATIVE PROCEDURES,
___________
CONDITIONS AND LIMITATIONS 199z99__
________%
Totals
___________
Final Grade All work done on this examination is my own.
I have neither given nor received aid.
_____________-
_________
_______
_
Candidate's Signature
-
<
'
.
NRC RULES AND GUIDELINES FDR LICENSE EXAMINATIONS
'
During the administratien of this examination the following rules apply l
Cheating on the examination means an automatic denial of your application 1.
cnd could result in more severe penalties.
Rastroom trips are to be limited and only one candidate at a time may laave.
You must avoid all contacts with anyone outside the examination
.2.
i room to avoid even the appearance or possibility of cheating.
3.
Use black ink or dark pencil gnly to f acilitate legible reprodections.
the blank provided on the cover sheet of the 4.
Print your name in axamination.
5.
Fill in the date on the cover sheet of the examination (i f necessary).
6.
Use only the paper provi ded f or answers.
the upper right-hand corner of the first page of each 7.
Print your name in l
szetion of the answer sheet.
8.
Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write gnly gn gng side of the paper, and write "Last Page" on the last answer sheet.
,
9.
Number each answer as to category and number, for example, 1.4, 6.3.
i i
10. Skip at least three lines between each answer.
,
11. S2parate answer sheets from pad and place finished answer sheets face r
down on your desk or table.
,
12. Use abbreviations only if they are commonly used in f acility literature.
13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
15. Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND DD NDT LEAVE ANY ANSWER BLANK.
16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
f You must sign the statement on the cover sheet that indicates that the 17.
is your own and you have not received or been given assistance in work This must be done after the examination has completing the examination.
'
been completed.
_-
_
___
_
- _ _
.
.
.10. Wh n you complete your examination, you shall
.
f Assemble your examination as follows:
c.
J (1)
Exam questions on top.
,
(2)
Exam aids - figures, tables, etc.
Answer pages including figures which are part of the answer.
(3)
I b.
Turn in your copy of the examination and all pages used to answer the examination questions.
and the balance of the paper that you did c.
Turn in all scrap paper not use f or answering the questions.
d.
Leave the examination area, as defined by the examiner.
If after in this area while the examination is still l eavi ng, you are found your license may be denied or revoked.
in progress,
.
~~,
_
^ * + " " -
e e
r
.
.-
__
d
.
PAGE
.
t!:.__BE9cIg_ItgOgY
.
QUESTION H.01 (3.00)
Briefly explain the dif f erence betweens o.
Fast and prompt neutrons (1.0)
b.
Slow and delayed neutrons (1.0)
c.
Activity and' reactivity (1.0)
GUESTION H.02 (2.00)
What effect does a moderator temperature increase have ons o.
Core reactivity (1.0)
b.
Control rod worth (1.0)
Explain your answer.
QUESTION H.03 (2.00)
'
i Doms the value of Beta-effective change during the FNR core life?
!
Explain.
(2.0)
QUESTION H.04 (.75)
How much excess reactivity is permitted by the Technical Specifications?
(.75)
.
,
l QUESTION H.05 (2.00)
o.
A step insertion of a small amount of positive reactivity is made to a reactor while critical in the very low power range.
Describe the changes in neutron flux after the reactivity addition.
,
(Neglect heating effects.)
(1.0)
b.
Describe the changes in neutron flux following a reactor scram f rom f ull power operation.
(1.0)
GUESTION H.06 (1.50)
o.
What is the purpose of the " moderator" in the reactor?
(1.0)
b.
Indicate which one of the f ollowing is considered an important (0.5)
.
aspect of a good moderator.
<
(1)
Low mass number
!
(2)
Large absorption cross-section (3)
Small scattering-cross-section I
(***** CATEGORY H CONTINUED ON NEXT PAGE
- )
!
'
.
..
--.
. -..
PAGE
.
th__MBCIOR_IggDRy
.
QUESTION H.07 (2.00)
Indicate whether each of the following statements concerning fission prcduct poisons are TRUE or FALSE.
(If FALSE, explain why it is (2.0)
Folce.)The equilibrium xenon concentration increases with increasing o.
power level while the equilibrium samarium concentration level.
significantly decreases with increasing power A reactor startup several days after a scram from extended b.
high power operation is considered xenon and samarium free.
QUESTION H.08 (3.00)
>
o.
What is the major fission product poison in your reactor?
(1.0)
(1.0)
b.
How is it produced?
(Include pertinent half-life.)
(1.0)
c.
How is it removed?
(Include pertinent half-life.)
QUESTION H.09 (1.50)
Indicate whether the f ollowing statements are TRUE or FALSE.
(1.5)
If they are FALSE, briefly indicate why.
a.
The delayed neutron fraction is greater at BOL than at f
EOL.
(.75)
'
'
b.
When determining reactor period, the delayed neutron term may be considered insignificant if reactivity added is less than beta and the prompt term may be considered insignificant when the reactivity added is greater than or equal to beta. (.75)
QUESTION H.10 (2.00)
Explain what the dif f erence is between k-infinite and a.
k-effective.
(1.0)
b.
K-effective of a reactor is given as 1.0795 delta k/k.
What k-excess does the reactor have?
(0.5)
(0.5)
What reactivity is associated with this k-effective?
c.
(***** END OF CATEGORY H
- )
-_ _--
_ - - _ _ _-__
. - - - _
- - - - - - - - _
,
.
PAGE
1___RQQlg6CllVE_g@lEBl@bS_0@ND61NG_DISPgS@L_@NQ_dgggggg
.
QUESTION 1.01 (2.00)
Ancwer the f ollowing in accordance with 10 CFR 20.
What three conditions must be satisfied to permit whole body radiation exposure in excess of 1.25 rems per quarter?
(1.5)
c.
b.
What is the legal limit for skin exposure to individuals less than 18 years of age?
(0.5)
QUESTION I.02 (1.50)
A material decays at a rate of 35 percent per day, what is its hal f-li f e?
(1.0)
QUESTION I.03 (3.75)
Radioactive isotopes that are common from the operation of a research recctor are N-16, A-41 and, H-3.
(3.75)
e.
For each of the above, give the source, where it would be found, and the half-life.
(.25 each, total 2.25)
precautions or design attributes are taken to reduce b.
What, if any, the effect of these isotopes at Ford Nuclear Reactor?
(0.5 each, total 1.5)
.
QUESTION I.04 (1.50)
Fill in the blanks with the radiation level:
1.
Reactor electromagnet assemblies and ion chamber assemblies may be removed from the pool and placed in appropriate holders on the west is side of the pool provided that the maximum contact dose rate less than _________.
for Sample irradiation containers may be removed from the pool
,
2.
loading of samples provided that the maximum contact dose rate is less than _________.
3.
Handling tools may be removed f rom the pool provided that the maximum contact dose rate is less than __________.
QUESTION I.05 (2.00)
Explain the bases behind limiting the tritium content in the heavy water in the reflector tank to 50 curies.
(*****
CATEGORY I CONTINUED ON NEXT PAGE
- )
-_ --
.
_ _._ _
_
_ _ _ _ _ _ _ _ _ _ _ _ _ - _ _
.
1:__RegigeCIIVE_DeIEB196s_UOU961Ng_giggge6_eN9_U9ISB99
.
GUESTIDN 1.06 (1.00)
WhGt are the staff exposure guidelines instituted at your facility for weskly whole body dose and weekly dose to the hands.
QUESTION I.07 (2.00)
.
100 rem depend on whether it is a neutron Does the biological effect of or gamma done? Explain.
QUESTION I.OB (2.50)
D2 fine or explain the f ollowings (0.5)
c.
Dose (0.5)
b.
Contamination (0.5)
c.
Rad d.
Resolving Time (Dead time)
(0.5)
a.
Half Thickness (Half Value Layer)
(0.5)
t QUESTION I.09 (2.00)
What four pieces of equipment will automatically close when the radiation level in the building ventilation
.
'
Oxhaust duct is 1 mrem / hour or more?
QUESTION I.10 (1.00)
Place the f ollowing in the proper order f or removing protective clothing when preparing to exit a controlled area.
1.
Remove gloves 2.
Conduct careful survey of entire body 3.
Remove coveralls and hood 4.
Exit the controlled area 5.
Remove shoe covers (***** END OF CATEGORY I
- )
-_.
-
__
_
_.
_
, _ _ _ _
_ _
__
, _ _..
.
.
PAGE
Jc__EEEg1EJg_QEEBSIJNg_gdgB99]EB15I19S QUESTION J.01 (4.00)
Define what constitutes Class I systems.
(1.0)
'
c.
(1.5)
b.
State five of the six systems classified as Class I systems.
c.
What additional systems must be in operation f or the reactor j
to be made critical?
(1.5)
QUESTION J.02 (2.50)
o.
What is the purpose of the water treatment system?
(1.0)
b.
What type of chemicals are used and what do these chemicals affect?
(1.0)
QUESTION J.03 (2.00)
Radiation streaming around beamport plugs can be a problem at a research rocctor.
How is this problem alleviated at the FNR?
(2.0)
QUESTION J.04 (3.00)
Sketch a plan view of the reactor, showing the following:
o.
Fuel positions b.
Source location
,
c.
Nuclear Instrument locations d.
Saf ety and Regulating Rod positions (3.0)
QUESTION J.05 (2.00)
List 5 uses of the reactor air system at the FNR.
(2.0)
QUESTION J.06 (1.00)
What is the general purpose of the pool's water lock system?
(1.0)
QUESTION J.07 (2.00)
Where and why do we reset the circuit breaker to the main exhaust fan ofter an electrical power interruption?
(2.0)
(*****
CATEGORY J CONTINUED ON NEXT PAGE *****)
---
-
. - - _ -. _ _,,, -.
- - -..
_
__.
i
.
PAGE
'
J __[EEg1Elg_ggEB811!!@_9tfDB991ESIDIlgg
.
i GUESTION J.OB (1.00)
Why isn't compressed air used instead of nitrogen gas to the shim safety rod magnet mechanisms.
(1.0)
QUESTION J.09 (2.50)
List 3 ways makeup water can be added to the primary coolant system.
c.
(1.5)
List 2 ways makeup water can be added to the secondary coolant b.
system.
(1.0)
DUESTION J.10 (1.00)
What is the plant's response if the butterfly valve located at the entrance of the holdup tank is moved from the f ully open position.
Why?
(1.0)
.
.
(*****
END OF CATEGORY J
- )
~ - - ---
- - -
__
_
_ _ _ _ _ _
,
-
..
__
- _.
.- -
,
.
.
PAGE O
E __E9EL_veN_61NG_eND_QQBE_P M 9dEIEBS D
..
~
GUESTIDN K.01 (1.50)
How does flooding or draining of beam port af f ect the reactor through ' the
recctor instrumentation channels?
QUESTION K.02 (2.00)
,
hazards / effects that could be caused by sudden
'
Thcre are two potential unplanned movement of the bridge.
Name them.
,
GUESTION K.03
'(3.00)
'
fuel is the purpose of the holddown mechanism f or the control i
c.
What elements during reactor operation?
(1.0)
b.
What would happen if the mechanisms were not installed and how could this effect core reactivity?
(2.0)
-
DUESTION K.04 (1.00)
What is the difference between a control rod fuel element and a standard
!
'
fuel element?
..
l
?
.
QUESTION K.05 (2.00)
'
j List two requirements in your technical specifications which apply to fuel i
j ctorage at your facility.
,
i
.,
QUESTION K.06 (1.50)
i f
What type of temporary storage condition can exist while transferring
!
unirradiated fuel between the vault and the reactor pool?
I l
,
(*****
CATEGORY K CONTINUED ON NEXT PAGE *****)
.
.
.
__
_ _ _ _. _ _ _, _
_
..
.
.. -.
.
.
..
-,-.
_ - _ _ _.
_
__
,.
.
-
._
.
._
. _ -.
__ _ --_-__
.
PAGE
L.__EWEL_19HD61?g,gNQ_QQB[_P989t![IEBE
.
DUESTIDN K.07 (2.50)
(0.5 pts each)
State the setpoints f or the f ollowing scrams.
o.
High Power /No water flow (> 100 Kw)
b.
Period Safety
'
c.
Level Safety d.
Building exhaust radiation level Fu'el Vault Criticality detector o.
GUESTIDN K.OB (1.50)
True or False.
Fuel elements can be laid down on the convex plate side.
b.
All movements of fuel will be documented in the Fuel Logbook or c.
on the status board mounted on the pool floor, c.
In an emergency, the Lead Operator may authorize the removal of core fuel to the pool storage rack.
QUESTION K.09 (2.00)
the three scram interlocks which can be bypassed using a.
List Procedure DP-111, Defeating Reactor Interlock Scrams.
(1.0)
b.
What three people can direct the bypassing of any scram interlock?
(1.0)
.
QUESTION K.10 (1.50)
State th-ee reasons for the FNR operators to want an up-to-date i
calibration of the shim saf ety rods of the reactor.
/
QUESTION K.11 (2.00)
What does the rod release time measurements determine?
c.
(1.5)
how will this affect b.
If'a magnet current setting is too high, release time?
(0.5)
i (***** END OF CATEGORY K
- )
.
- _
- - _. -
-.
..
.
-
,
.
.-
-
-
-
-
,-
8 PAGE
k __e951NisIgeIlyE_PBQGE9WBES _ggNgillgNg,'gNg_L151IeI19NE t
.
DUESTION L.01 f1.50)
!
,
severity, least
,
Liot three emergency classes f or your f acility in order of covere first.
,
,
.
. +
QUEST!DN L.02 (1.00)
You You are the Lead Dperator when a reactor emergency has been declared.
conume the responsibilities of Emergency Director.
For a general notification, what two people must you notify?
(1.0)
.
QUESTION L.03 (3.50)
Why do the Tech Specs have saf ety limits and limiting saf ety system c.
settings?
(2.0)
b.
List the values of the safety limits in the Natural Convection Mode for the following:
(1.5)
1.
Reactor Thermal Power 2.
Reactor Coolant Inlet Temperature 3.
Height of Water Above the Top of the Core L
i QUESTION L.04 (2.00)
'
c.
What is the minimum staffing requirement during reactor operation?
(1.0)
b.
When is a Senior Reactor Operator required to be either on call or at the f acility?
(1.0)
QUESTION L.05 (2.00)
(0.5)
A volunteer may be,tuthorized to receive up to __________ Rem a.
t o save a li f e and up to ___________ Rem (0.5) to isolate equipment.
b.
List the two personnel selection considerations f or emergency
exposure volunteers.
(1.0)
QUESTION L.06 (1.00)
Pcr OP-f04, Reactor' Operations, if circumstances prevent chronological cntries, how will a late entry be recorded?
(***** CATEGORY L CONTINUED ON NEXT.PAGE
- )
.
__
. _.
.
.. _ _ _ _. -
,
,
_
_ _..,
_ _ -. _ _ _ _
__
_.__.- -
,..
.
.
PAGE
6 __BgDINISIBellyE_PgggEgg8Egi_gggg111ggs_ egg _6151IeIlges l
i
-
GUESTIDN L.07 (2.50)
For the f ollowing plant conditions, state the correct operator action.
Choices are scram reactor, insert all rods, or maintain power.
(0.5 each)
c.
Malf unction of Auto-Dundown circuit b.
Inability to control shim-safety rods c.
Loss of shim rod magnet contact light j
i d.
Loss of linear level channel o.
Blockage of greater than 10% of fuel element flow area l
l QUESTION L.OB (2.00)
i If a " duress" alarm is received at the control room, what would be the duties of the operator?
(2.0)
QUESTION L.09 (2.00)
)
\\
What is the on-shift lead reactor operator's responsiblity for the initial londing of an experiment?
(2.0)
i QUESTION L.10 (7.00)
What requirements apply to the transfer of radioactive experiments:
,
c.
Within the facility?
(1.0)
b.
To the other areas of the University?
(1.0)
l
I (***** END OF CATEGORY L
- )
(*************
END OF EXAMINATION ***************)
-
-
--
_ _ _ _
f
-
.
EQUATION SMEET
-
-
.
Cycle efficiency = (metwork j
.
f = es v = s/t
,
,
out)/(Energyta)
~
w = og s = V,t + 1/2 at
,
i E=d A = h* *
A = na KE = 1/2 av a=(Vf - V,)/t 9E = egh w = e/t
& = anZ/tgg = 0.6g3/t1/2 Vf = V, + at 1/Z'##*{I*11'II*h)3
'
t W = w aP-a0
[(*1/2 * I*tI3 I
A" i,
,
'
f aE = 931 mm
-h
"*Y A8 I=Ie av g
~
Q = aCpat I = I e "*
~
6=UAaT g
I = I,10-*E Pwr = W ah f
TVL = 1.3/u sur(t)
HYL = -0.693/u P = P,10 P = P,e /T t
SUR = 26.06/T SCR = 5/(1 - K,ff)
~
CR, = S/(1 - K,ffx)
CR (1 - K,ffj) = G (I ~ Eeff2)
SUR = 26s/t* + (s - s)T j
T = (1*/s) + [(s - eVIe3 M = 1/(1 - K,ff) = CR /CR,
.
j T = s/(o - s)
M = (1 - K,ff,)/(1 - K,ffj)
T = (s - e)/(Is)
SDM = (1 - K,ff)/K,ff
,
F = 10# seconds a = (K,ff-1)/K,ff = aK,ff/K,ff I = 0.1 seconds'I L
s = [(s*/(T K,ff)] + [a,ff (1 + IT)]-
/
ii=2=2k td I
i P = (34V)/(3 x 1010)
Id Id jj g2
R/hr = (0.5 CE)/d (meters)
z = eN R/hr = 6 CE/d2 (feet)
,
Miscellaneous Conversions Water Parameters
.
10dps 1 curie = 3.7 x 10 1 gal. = 8.345 lem.
1 gal. = 3.78 liters 1 kg = 2.21 Its 3 Stu/hr
'
1 ft" = 7.48 gal.
I hp = 2.54 x 10
1 sw = 3.41 x 106 Stu/hr
.
Density = 62.4 lbg/ft lin = 2.54 cm Density = 1 ge/cW I
Heat of vaporization = 970 Stu/lom
'F = 9/S*C + 32 Heat of fusion = 144 Bru/lem
'C = 5/9 ('F-32)
! 9 r.14 7_ psi _= 2911a Hs-1 eTu = 778 rt-ief n2v = u. aan scr/ in.
I IL.
_.
-_
_
. -
._
-
-.. -. _ -...
.
---,
,
_
_ _ _ _ _ _ _ _ _ _ _ _____ -
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
PAGE
H __BEBCIOB_IHEORY ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-HARE, B.
-
l ANSWER H.01 (3.00)
Fast neutrons refer to those at high energy levels.
(0.5)
c.
Prompt neutrons refer to those released at the time of fission.
(0.5)
Slow neutrons are neutronr: at low energy levels.
(0.5)
b.
Delayed neutrons are those which appear at some time after the fission event due to fission product decay.
(0.5)
c.
Activity refers to the rate of radioactive decay.
(0.5)
Reactivity expresses the deviation of a reactor from the critical condition.
(0.5)
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 3 ANSWER H.02 (2.00)
Core reactivity is decreased. (0.5)
The temperature increase a.
causes a density decrease of the moderator.
There is less moderation and more neutron leakage, which is a negative effect.
(0.5)
b.
Control rod worth increases. (0.5)
As moderation is decreased and the probability of leakage into a control rod increases, the effectiveness of the control rods increase.
(O.5)
.
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 6 ANSWER H.03 (2.00)
a.
Yes.
(1.0)
b.
This value will depend on the fraction of delayed neutrons f rom U-235 and the shape of the core.
(1.0)
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 3 ANSWER H.04 (.75)
.038 DK/K
.
.. _
_..--
_ _ - -
.
__
-_ -__ _.. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
'
l PAGE
H.__8ESClg8,lHE981 ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-HARE, B.
i
-
REFERENCE Tcchnical Specification 3.1 ANSWER H.05 (2.00)
a.
There is a " prompt jump" increase in neutron flux due to the immediate effects of prompt neutrons.
(0.5)
whi ch i s Power then increases on a stable period the value of determined by the amount of reactivity inserted and the delayed neutron generation time.
(0.5)
in neutron flux as b.
Following a scram there is a prompt drop is stopped.
(0.5)
prompt neutron generation then gradually decreases as delayed neutrons continue to Flux be generated from the decay of the precursor groups.
(0.5)
j REFERENCE
Introduction to Nuclear Reactor Operations, Chapter 4 ANSWER H.06 (1.50)
Neutrons of low energy have the highest probability of causing a.
f i ssi on in the fuel.
Most neutrons are born at high energy l evel s.
Tbd moderator reduces the neutron energy level.
( 1. 0)
j b.
(1)
Low n. ass number (0.5)
-
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 3 ANSWER H.07 (2.00)
a.
False (0.5) - After reaching equilibrium, the samarium concentration remains constant.
(0.5)
It may be xenon free but samarium will not decay b.
False (0.5)
-
away.
(0.5)
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 8
.
, - - _.
- - __
_
,
-
,
, _ _ _ _
_
_.-
.
.
PAGE to i
H.
REACTOR THEORY ANSWERS -- UNIVERSITY DF MICHIGAN-87/04/14-HARE, B.
-
ANSWER H.08 (3.00)
n.
Xenon 135 (1.0)
Directly f rom fission.
(.25)
b.
(1)
From beta decay of fission products iodine-135 and (2)
te11urium-135.
(0.375)
Tellurium-135 decays to iodine-135 (19 seconds half-lif e) which then decays to xenon-135 (6.7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> half-life).
-(0.375)
_1)
Burnout by neutron absorption.
(.333)
(
c.
(2)
Beta decay to cesium-135 (0.333) with a 9.2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> half-life.
(0.333)
(Ercet half-life not required, must be within 20*/. of actual half-life)
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 8
<
ANSWER H.09 (1.50)
a.
True b.
False - Just the opposite is true.
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 3
,
j ANSWER H.10 (2.00)
K-infinite is the multiplication constant for a theoretical
'
a.
reactor with zero leakage.
K-effective takes into account neutrons lost due to slow and fast leakage (k-eff = k-inf *
slow and fast non-leakage probability.)
(1.0)
1.0795-1 = 0.0795 delta k (0.5)
b.
k-excess = k-effective-1
=
c.
Reactivity = (k-effective-1)/k-effective = (1.0795-1)/1.0795 =
0.0736 delta k/k.
(0.5)
i REFERENCE Introduction to Nuclear Reactor Operation, Chapter 6
._.
- _. -. -
..
.
..
... -
- - -.. - -
--.-.
-.. --
.. -_-
,
_ _ _
_
.__
._
_.
.
_
. _ _ _
.
l l
.
PAGE
1___H09199CIlyE_ggIEg196g_geNg6}gg_pjgPgS96_ggg_Hg]ggpS ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-HARE,-B.
-
ANSWER I.01 (2.00)
c.
Quarterly dose less than 3 rems Lif etime dose less than 5(N-18)
Accumulated occupational exposure is documented on NRC Form 4
(0.5 each)
b.
.75 rems per quarter-l" REFERENCE 10 CFR 20.101 and 104
.
i ANSWER I.02 (1.50)
N = Noe[-lambdatt3 100 - 35 / 100 = e[-l ambda x 13 0.65 = e C-lambda x 13 in O.65 = -lambda O.43 = lambda T1/2 = 0.693 / lambda T1/2 = 0.693 / O.43 = 1.61 (day)
<
REFERENCE Introduction to Nuclear Reactor Operations, Chapter 2
'
~
i
ANSWER I.03 (3.75)
a.
O-16 [n, p3 N-16; Primarv coolant water; 7 seconds A-40 + (n, gamma) A-41; air space near reactor and primary water with dissolved air; 1.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> H-2 + (n, gamma) H-3; Primary coolant water and air above pool; also heavy water in reflector tank; 12 years.
,
(Exact half-lif e not required, must be within 20% of actual
!
hal f-li f e)
b.
N-16 = Hold-up tanks in primary coolant and domineralizer.
'
Some held in beam ports; use of other gases in A-41
=
pneumatic systems.
H-3 = Vents at top of pool.
REFERENCE Nuclear Power Plant Health Physics and Radiation Protection, Chapter 5 FNR Systems Descriptions p.
4-5, p.
12-1, p.
3-12
i l
,
.. - _ _.
.,_-.-n,
_.-.
, _.,,,
,
_
.,, -,, _.,,
,
,
,,_
.. - _ _. _ _ _ -..,..,,_,
_
.
.
PAGE
1___BBDigeCIlvg_MeIgeleLg_HeNQ(INQ_QlgPQgg(_@NQ_U91@BQ3 ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-HARE, B.
-
ANSWER I.04 (1.30)
1.
500 mrem / hour.,
2.
100 mrem / hour.
3.
50 mrem /houe
.
(3 G O.5 each = 1.5)
REFERENCE Hacith Physics F1anual, pg. 2-3 ANSWER I.05 (2.00)
This is based on an analysis which showed that, in the event of rupture of the heavy water tank, the water would not, under the conditions of the maximum evaporation rate from the reactor pool, produce tritium concentrations in the reactor building air in excess of the maximum psrmissible concentrations for that isotope.
REFERENCE OP-402, pg. 1 ANSWER I.06 (1.00)
.
Whole body < 100 mrem / week (0.5)
Hands < 1 rem / week (0.5)
REFERENCE H2cith Physics Manual, pp. 1.2 ANSWER I.07 (2.00)
Rem is a The unit REM already considers the different effects.
No.
thus different radiation causing the same dose in REM biological unit, chould have the same effect.
REFERENCE 10 CFR 20
,
-
,, - -.,..... ~.. - -
-,.
.
,,e..,,.,_4
,
,
- -.,, -.. -. -
, - -..
- - - - -. -
_.
__
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_
l I
.
PAGE
1 __Be91geCIIVE_U@lE@l3(S_d@Np(LNG _QlSPQS96_gNQ_d@[98Q@
ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-HARE, B.
-
ANSWER I.08 (2.50)
Dose - The quantity of radiation absorbed per unit mass by the body c.
or by any portion of the body.
(0.5)
b.
Contamination - The deposition of radioactive material in any place where it is not desired, particularly if its presence is harmful to personnel.
(0.5)
Rad - A measure of the dose of any ionizing radiation to body c.
tissues in terms of the energy absorbed per unit mass of the tissue.
100 ergs /g tissue.
(0.5)
d.
Resolving Time (Dead Time)- The time when a detector operating in the region of the curve is insensitive to incoming radia-Geiger-Mueller tion due to the process causing the anode to be engulfed by positive ions.
(0.5)
A half value Thickness Value-A term used to represent shielding.
e.
Half layer of a material, reduces the intensity of incident radiation by a factor of 2.
(0.5) Also called Half Value Layer (HLV).
REFERENCE Nuclear Power Plant Health Physics and Radiation Protection Chapters 3, 9,
ANSWER I.09 (2.00)
1.
Ventilation intake and exhaust dampers
'
2.
Intake and exhaust ventilating fans 3.
Dampers in the beamport exhaust system 4.
Room 3103 exhaust hood duct (4 @ O.5 each = 2.0)
REFERENCE Technical Specification 3. 3(1)
ANSWER I.10 (1.00)
3,5,1,2,4
- subtract 0.2 for each one out of order (0.2 pts for each correct answer up to the value of the question)
,
.
REFERENCE H2alth Physics Manual, pg. 19 l
l
!
t
_ _ _ _
_
,
-
_ _,.
_ _ _. _. _, _
,
.
.
PAGE
g___SeEQlElG_DEGR@l1NG_QH9R$QIER10I193 ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-HARE. B.
-
ANSWER J.01 (4.00)
.,
Class I systems are essential f or the saf e shutdown and isolation of the reactor (0.5) and to maintain the reactor in a safe, shutdown o.
condition (0.5).
(1.0)
b.
1.
The primary coolant 2.
The safety system 3.
The shim safety rods 4.
All scram functions The high temperature auto rundown function 5.
6.
The pool level rundown (5 of 6 required S.30 pts each = 1.5)
,
c.
LCR Log N level servo dropout function Lineararea radiation monitoring equipment except the monitor on the All Room 3103 hood 1.5)
(4 &.375 pts each
=
REFERENCE FNR Systems Description, Chapter 1 ANSWER J.02 (2.50)
This system controls general corrosion in the secondary system
~
a.
and fouling or blockage of the heat exchanger.
(1.0)
The chemicals used are Hagatreat (0.25) and sulfuric acid 7.25).
b.
(0.5).
Sul,aric Hagatreat controls corrosion and scale f ormation acid holds down the pH level (0.5).
REFERENCE Pg. 5-4 ANSWER J.03 (2.00)
a lead sleeve around each plug gives When the plugs are in position, protection against streaming through the annular space between the plug cnd the port shell.
REFERENCE FNR Systems Description, Chapter 3, pg. 5 i
.. -_
.
.~. _
_
.
__ _ _ _, _
_ _.. _ _. _..
_.... _.
-
.
.
.
PAGE
2 __SEEg1Elg_ DEER $1}Ng_gH9B991EB]SIlgg ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-HARE, B.
-
ANSWER J.04 (3.00)
Figure 2.1 in FNR Systems Description, pg. 2-2 REFERENCE Figure 2.1 in FNR Systems Description, pg. 2-2 ANSWER J.05 (2.00)
sump level control.
Mixing hot and cold domineralizer resin and f or resin separation.
2.
3.
Secondary water makeup valve control.
Controlling reactor building supply and exhaust ventilat' en dampers.
4.
5.
Controlling supply and exhaust ventilation duct bypass.
6.
Cooling tower sprinkling system.
(5 of 6 required & O.4 pts each = 2.0)
REFERENCE FNR Systems Description, Chapter 10 ANSWER J.06 (1.00)
Provides a means f or transf erring highly radioactive samples, experiments, cnd reactor fuel from the pool to a shielded hot cave.
(1.0)
REFERENCE FNR Systems Description, Chapter 3, pg. 1 ANSWER J.07 (2.00)
Racet circuit breakers in Room 2074 and Reset the mercury switches in Room 3073.
(1.0)
This allows exhaust blowers to operate which in turn stops tha emergency blowers from operating.
(1.0)
REFERENCE OP-100 ANSWER J.OB (1.00)
It would produce radioactive argon-41.
__
-_.. _-
-
.
_ -,.
-_
--
.
-- -
Ford Nuc1 Car Re:ctor Cy;tems Description 3
,
Recctor January 8, 1985
'
Figure 2.1 Typical Reactor Core
'
'
.
.
'l Power Linear Power Ing N Range B Level Range A I
Heavy Water Tank I
I V
Radiography Facility
"*"*' "
L75 L65 L55 L45 L35 L25 L15 Source C
A _
L76 L66 L56 I L36 I I
L16 L6
Rod Rod L77 L67 L57 L47 L37 L27 L17 L7 i
B
'gn L
L78 L68 L58 j
L38 _!
L18 L8 Rod Rod F
o
L69 L59 L49 L39 L29 L19 l
e O
1A0 L60 L50 L40 L30 l L10 (J l
Outrigger Outrigger Fage 2-2
-
_.__ _ - _
. - _ _ -. _
._-
.- _ _ _ _
_ - _
.
- -
-.
. _ _ _ - _
_ _ - _ _ -
.
-
-
.
PAGE
q___SeEg1Elg_DEg8911Ng_ghgB9QIgBISIlgg ANSWERS -- UNIVERSITY DF MICHIGAN-87/04/14-HARE, B.
-
REFERENCE FNR Systems Description, Chapter 2 ANSWER J.09 (2.50)
c.
1.
To the primary pump directly.
2.
To primary return line a the (N.O.) isolation valve.
3.
To the south pool by utilizing a 3 valve system.
(3 9.50 pts each = 1.5)
b.
1.
City water valves open to bring sump level back up to the sump level controller setpoint by allowing water to the suction side of secondary circulating pump.
'2.
Allow water to discharge side of secondary circulating pump.
(2 9.50 pts each = 1.0)
REFERENCE FNR Systems Description, Chapters 4 and 5 ANSWER J.10 (1.00)
The reactor is scrammed (0.5) due to a loss of primary coolant flow eignal.
(0.5)
REFERENCE FNR Systems Description, pg. 4-5
,
__..
.. _. _ _
-
_
,
, _..
_
. _ _ _ _
.
.
PAGE
K __E9Eb_dgNQ(lg@_ggg_CQBg_ggg@d{lgR@
ANSWERS -- UNIVERSITY DF MICHIGAN-87/04/14-HARE, B.
'
J ANSWER K.01 (1.50)
ion chambers are located directly above B port (0.5), and changes in Th2 tha condition of that port will affect instrument readings (0.5) which might initiate automatic control action (s)
(0.5).
(Because of this instrument response difficulty, draining of B port is unacceptable during rocctor operation.)
REFERENCE DP-401, pg. 1 ANSWER K.02 (2.00)
1.
Potential reactivity change due to changing the location of the core.
(1.0)
2.
The risk of damaging the core, the D,0 tank, and the beamports.
'
(1.0)
REFERENCE OP-214, pg. 1-2 ANSWER K.03 (3.00)
.
c.
The purpose of these mechanisms is to prevent the inadvertent withdrawal of a fuel element from the gridplate during rod withdrawal.
b.
Without the holddown mechanisms, it is conceivable that a rod could jam within the control element and the drive mechanism could lift both out of the core lattice (1.0).
If this should occur and the control element should subsequently drop back into the lattice, the sudden insertion of positive reactivity would put the reactor on a short positive period (1.0).
REFERENCE FNR Systems Description, Sec.
3.4, pg. 3-8 ANSWER K.04 (1.00)
Control rod fuel elements are identical to standard elements except that nine central plates have been replaced by a rod guide channel.
,
---
-
-_
-
. _ _ -.. _.
_ _ _ _ -
.
_.
_.
..
,
.
PAGE
K __Eug6_vegg61gg_ egg _gggg_P9899gIgBE ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-HARE, B.
- REFERENCE FNR Systems Description, pg. 2-1
)
ANSWER K.05 (2.00)
1.
All reactor fuel elements and fueled devices shall be stored in a (1.0)
geometric array which assures subcriticality.
2.
Irradiated fuel elements and fueled devices shall be stored in an
array which will permit sufficient natural convection cooling by water or air such that the fuel element or fueled device temperature will not exceed 100 C.
(1.0)
REFERENCE FNR Technical Specification 5.4 ANSWER K.06 (1.50)
!
Tho unirradiated fuel can be laid down in a row on a flat surface with not i
100s than 6 inches between each element.
I
]
REFERENCE OP-106, pg. 1
.
ANSWER K.07 (2.50)
c.
900 gpm b.
5 seconds or less c.
120% (2.4 Mw) or greater d.
1 mr/hr or greate-o.
5 mr/hr or greater (5 9 0.5 each = 2.5)
REFERENCE TGehnical Specifications Table 3.1 ANSWER K.08 (1.50)
c.
False b.
False c.
True (3 D 0.5 each = 1.5)
.
.
PAGE
k __guE(_hgND61Ng_gND_Cg6E_PgRgDEIERg ANSWERS -- UNIVERSITY OF MICHISAN-87/04/14-HARE, B.
-
REFERENCE DP-106, pg. 2
.
ANSWER K.09 (2.00)
c.
1.
Beamport doors scram 2.
Thermal column door scram 3.
Shim range bypassed (3 rods) scram (3 9.33 each = 1.0)
b.
1.
Reactor Manager 2.
Assistant Reactor Manager 3.
On-call Supervisor (3 9.33 each = 1.0)
REFERENCE OP-111 ANSWER K.10 (1.50)
1.
The license and technical specifications requires Core excess reactivity less than O.038 delta K/K.
a.
b.
Shutdown margin (3 rods inserted) not less than 0.025 delta K/K.
c.
Shutdown margin (most reactive rod stuck out) not less than 0.0045 delta K/K.
,
2.
Depletion of poison in a rod reduces rod worth.
3.
Breaking of a shim rod would result in loss of apparent worth.
4.
Improper fuel fabrication and/or location would result i
J in rod worth changes.
(3 of 4 required 3 0.5 each = 1.5)
REFERENCE DP-201, pg. 1
ANSWER K.11 (2.00)
They are performed for the purpose of determining the
,
c.
excessive decay time associated with the magnetic flux
,
generated by the electromagnet.
(1.5)
b.
Cause an excessive release time.
(0.5)
REFERENCE f
,
OP-211 f
-
.
__.
.
_
. _,.
. _ _ _ _
_
_ __
_
_
_
_. _, _ _.
__
_ __
-
.
.
.
PAGE
6 __0951NISIB911VE_PRQCEQURE@g_QQNQlligNS_gNQ_(1511@llgNE-87/04/14-HARE, B.
Non-Reactor Safety Related Events Unusual Event Alcrt (3 3 0.5 pts each = 1.5)
REFERENCE FNR Emergency Plan, Section 4 ANSWER L.02 (1.00)
1.
Project Director (Dr. Kerr)
2.
NRC Region III Duty Officer REFERENCE FNR Emergency Plan, Appendix 2, pg. 2-5 OP-101, pg. 8 ANSWER L.03 (3.50)
The safety limits shall assure that the intygrity of the fuel clad is maintained.
(1.0)
The LSSS shall prevent the safety limits a.
,
from being exceeded under the most severe abntrmal situation.
(1.0)
b.
1.
380 Kw 2.
131 degrees F
-
3.
18 feet (3 9 0.5 each = 1.5)
!
REFERENCE Tcchnical Specifications 2.1 and 2.2
,
--
- -, - -,
,
..-
-
- - - - - - - - - - -, -. -
--
-
e
_
.
.
bz__9DDINISIB911VE_ESQgEQUBESg_CpNp1IlDNS,@Np_(ID1I@IlDNE PAGE
ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-HARE, B.
.
ANSWER L.04 (2.00)
o.
The minimum operating crew will be composed of two individuals (0.5),
at least one of which will be a licensed operator (0.5).
b.
1.
During initial startup and approach to power 2.
Recovery f rom an unplanned or unscheduled shutdown or a significant reduction in power 3.
During refueling 4.
Otherwise prescribed in license (4 &.25 nach = 1.0)
REFERENCE Tcchnical Specification 6.1 DP-102, 103, and 106 ANSWER L.05 (2.00)
c.
100 Rem (0.5)
25 Rem (0.5)
b.
1.
Volunteer is familiar with the consequences of exposure.
2.
Volunteer is the eldest able bodied person
= 1.0)
(2 & O.5 each REFERENCE FNR Emergency Plan, Appendix 2, pg. 9
-
FNR Emergency Plan, Appendix 3.5, pg. 18 ANSWER L.06 (1.00)
If circumstances prevent chronological entries, events will be recorded as " late entries" with time of recording (0.5) as well as the actual time of the event indicated (0.5).
REFERENCE OP-104, pg. 2 i
.
. __
___
.. _.
.
. _. _.
__
_
_,
__. - _.. _
_
__ _
-
.
.
PAGE
6:.__9901N19188I1VE_ESQGggUBgh_QQNQlligNS_9NQ_(ig110IlgNE
- ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-HARE, B.
ANSWER L.07 (2.50)
c.
Insert all rods b.
Scram reactor c.
Maintain power d.
Scram reactor o.
Insert all rods (0.5 each)
REFERENCE DP-104, pg. 7-8 ANSWER L.08 (2.00)
c.
Scram reactor and remove the magnet key b.
Leave reactor building, advising anyone he sees to do the same.
(DO NOT INITIATE BUILDING ALARM.)
c.
Call 123 and notify security that someone is forcing his way into the reactor building.
2.0)
(3 9.66 each
=
REFERENCE OP-104, pg. 18
.
ANSWER L.09 (2.00)
Th2 lead reactor operator for initial loading of an experiment is racponsible for measuring the experiments' reactivity (1.0) and classifying it as moveable or secured (1.0).
REFERENCE AP-3
i
.,,
-
-
--
.
. - -.
_.
- - - -
,,
..,.
- -..
-
.
.
PAGE
6:.__0951NigIS911VE _P8QCEQg6EL _CQNQlllQNS_gNQ_(lg11gIlgNg ANSWERS -- UNIVERSITY OF MICHIGAN-87/04/14-HARE, B.
ANSWER L.10 (2.00)
Any handling or transfer of radioactive experiments within tbe (0.5).
If c.
f acility should be done with health physics assistance this is not possible, the Health Physicist must approve the proposed handling or transfer (0,5).
(This approval may be given for a series of duplicate capsules.
Under such general approval s, care must be taken to avoid changes in routine.)
b.
All experiment transfers to other areas, both within ared outside of the University, will be done under the direct control of Radiation Control Service (0.5) unless specific instructions to the contrary are listed on a particular Reactor Utilization Request (0.5).
REFERENCE c.
OP-105 9.3, pg. 6 b.
Op-106 9.4, pg. 6 i
l
.
- - - - - __ -
.
- _
.. - _ _
. -. -
-
.-.. _ _ _ _. _ _ _ -
. -
.
. _ - -.._
._
.
TEUT CROS3 REFERENCE PAGE
)UESTION VALUE REFERENCE
.-------
-_----
H.01 3.00 EAHOOO1117 H.C2 2.00 EAHOOO1118 H.03 2.00 EAHOOO1119 H.OG
.75 EAHOOO1120 H.05 2.00 EAHOOO1121 H.06 1.50 EAHOOO1122 H.07 2.00 EAHOOO1123 H.00 3.00 EAHOOO1124 H.09 1.50 EAHOOO1125 H.10 2.00 EAHOOO1126
- - - _ _ _ _
19.75 1.01 2.00 EAHOOO1127 I.02 1.50 EAHOOO1128 1.03 3.75 EAHOOO1129 1.04 1.50 EAHOOO1130 1.05 2.00 EAHOOO1131 1.06 1.00 EAHOOO1132 1.07 2.00 EAHOOO1133 1.08 2.50 EAHOOO1134 1.09 2.00 EAHOOO1135 1.10 1.00 EAHOOO1136
-_____
19.25 J.01 4.00 EAHOOO1137 J.02 2.50 EAHOOO1138 J.03 2.00 EAHOOO1139 J.04 3.00 EAHOOO1140
.
J.05 2.00 EAHOOO1141 J.06 1.00 EAHOOO1142 J.07 2.00 EAHOOO1143
J.08 1.00 EAHOOO1144
J.09 2.50 EAHOOO1145 J.10 1.00 EAHOOO1146 i
_____-
21.00
J K.01 1.50 EAHOOO1147 K.02 2.00 EAHOOO1148 K.03 3.00 EAHOOO1149 K.04 1.00 EAHOOO1150 K.05 2.00 EAHOOO1151 K.06 1.50 EAHOOO1152 K.07 2.50 EAHOOO1153 K.OB 1.50 EAHOOO1154 K.09 2.00 EAHOOO1155 K.10 1.50 EAHOOO1156 K.11 2.00 EAHOOO1157
_ _ -. _ _ _,
_
_. _..
_
_. _
,
..
_.
.
_ _ _ _
.
.
.
TEST CROS3 REFERENCE PAGE
QtJESTION VALUE REFERENCE
__________
.________
______
______
20.50 L.01 1.50 EAHOOO1150 L.02 1.00 EAHOOO1159 L.03 3.50 EAHOOO1160 L.04 2.00 EAHOOO1161 L.05 2.00 EAHOOO1162 L.06 1.00 EAHOOO1163 L.07 2.50 EAHOOO1164 L.OB 2.00 EAHOOO1165 L.09 2.00 EAHOOO1166 L.10 2.00 EAHOOO1167
______
19.50
______
______
100.00
i
.
%
, 6
i
I i
..,. _
...-
. _.
_., _. - _ _ _ -, _ _. _ _ - _.... _ _ _ _ _ _.., _ _ _ _.,,_
.. _.
_ _. _ _,._
.. _ _ _ _ _ _. _. _.
_,. -. _ _ _,