ML20214K943
| ML20214K943 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 11/04/1986 |
| From: | Burdick T, Hare S, Higgins R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20214K846 | List: |
| References | |
| 50-002-OLS-86-0, 50-2-OLS-86, NUDOCS 8612020522 | |
| Download: ML20214K943 (50) | |
Text
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U.S. NUCLEAR REGULATORY COMISSION REGION III-Report No. 50-002/0LS-86-01(DRS)
Docket No.50-002 License No. R-28 Licen!,ee:
University of Michigan Phoenix Memorial Laboratory Ann Arbor, MI 48105 Facility Name:
Ford Nuclear Reactor Examination Administered At:
University of Michigan, Ann' Arbor, MI Examination Conducted:
October 7 and 8, 1986 kb ld Examiners:
R. L. Higgins y
Date
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Date-flhW b
Approved By:
T. M. Burdick, Chief
//!
N.
l Operator Licensing Section Date/
Examination Summary Examination administered on October 7 and 8, 1986 (Report No. 50-002/0LS-86-01)(DRS) to two reactor operator candidates.
Results: One candidate passed.
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REPORT DETAILS 1.
Exarainers
- R. L. Higgins S. M. Hare
- Chief Examiner 2.
Examination Review Meeting - refer to Attachment 1.
3.
Exit Meeting On October 8, 1986, 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 Manger G. Cook, Assistant Reactor Manager NRC representatives:
R. Higgins, Chief Examiner S. Hare, Examiner-in-Training The items discussed during the meeting are listed in the following paragraphs.
a.
The chief examiner noted that some areas of the facility seemed cluttered.
As such could potentially impact safe facility operation.
b.
The chief examiner noted that procedural compliance was deficient during the startup, noting that one candidate forgot to withdraw the control rod when called upon to do so by the procedure.
The candidate caught his error later and at that time withdrew the control rod.
The chief examiner stated that the candidate was not referring to the startup procedure at the time and would certainly not have made a mistake had he been referring to the startup procedure.
c.
The chief examiner noted that control of control room access was lacking, noting that several people walked between the operator and the meters the operator was using to control the reactor during a reactor startup without permission of the operator.
The personnel involved entered the control to procure coffee and a stopwatch.
d.
The chief examiner noted that both candidates appeared to be extremely conscientious and knowledgeable, but seemed unfamiliar with the emergency plan.
On October 9, 1986, the meeting was resumed by telephone from the regional office.
The items covered are summarized in the following paragraphs.
2
a.
The chief examiner mentioned that one candidate displayed weakness in his knowledge of reactor theory and nuclear instrumentation.
b.
The chief examiner mentioned that facility literature was incomplete (no description of the heavy water tank controls or shim rod construction) and needed revision (reference was made in several procedures to the Supervisor of Reactor Operations, though this position has been eliminated).
The Reactor Manger acknowledged this fact and stated that facility literature is revised on a periodic basis and these deficiencies should be corrected in the next revision.
c.
The chief examiner mentioned that not all th'e facility literature needed to prepare for the examinations was sent initially.
The Emergency Plan was sent only after it was specifically requested, and even then certain appendices which were directly related to the operators' duties were not sent.
In addition, none of the 200, 300, or 400 series procedures were sent.
The Reactor Manager agreed to send all the aforementioned facility literature plus all other facility literature which the NRC requests for examination preparation.
d.
The chief examiner mentioned that the control room operators were extremely cooperative with the examiners.
i i
3
ATTACHMENT 1 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.
Question B.08 Facility Comment: Answer 2 should be " supplement flow moving through the fuel element."
NRC Response:
Agree.
The answer was changed per facility request.
Question C.02 Facility Comment:
Typical values a.
<90 F >116 F b.
<129 F NRC Response:
Disagree.
Reasonably close values will be awarded credit, but that range of values for which the facility requests credit is excessive.
The answer was not changed.
Question C.04 Facility Comment:
Operating Range 5.0 - 7.0.
NRC Response:
The question asked for " optimum range" rather than " operating range," however full credit will be awarded for the response "5.0 - 7.0."
Question D.02 Facility Comment: Operations staff at FNR use core ^T for power level information.
Heat exchanger ^T is not an approved technique.
NRC Response:
Noted.
The question is still valid.
Question 0.08.a Facility Comment:
Log N period channel which feeds the signal to the period scram circuit (Channel C).
NRC Resp'onse:
Agree.
Both the answers " Channel C" and " Log N period channel will be awarded full credit.
4
Question E.11 Facility Comment: Add "5.
control rod at lower limit, reactor in servo control."
NRC Response:
Agree.
The answer key was modified per facility request.
Question G.10 Facility Comment: This question is for the " holdup" tank, not the " holding" tank.
Operators might confuse this with the retention tanks which are for holding liquid effluent.
NRC Response:
Agree.
The question was changed to " holdup" tank at the conclusion of the exam.
All candidates answered the question by assuming
" holding" meant " holdup."
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NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
_UNIVEB@ITy_QF_MIGHIG@N__
REACTOR TYPE:
_IEST__
DATE ADMINISTERED: 86/10/07 EXAMINER:
_HIGGIN@2_B._____________
CANDIDATE:
INSIBUQIlgNS_IQ_CBNQlg8151 Use separate paper for'the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question.
The patsing grade 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
__Y86UE_ _IQI66
___SCQBE___
_y@(UE__ ______________C@IEGQBy_____________
_16199__ _13199
________ A.
PRINCIPLES OF REACTOR OPERATION
_19z99__ _16z99
________ B.
FEATURES OF FACILITY DESIGN i
_1dz99__ _19199
________ C.
GENERAL OPERATING CHARACTERISTICS
_1dz99__ _16z99
________ D.
INSTRUMENTS AND CONTROLS 1
_15z99__ _15z99
________ E.
SAFETY AND EMERGENCY SYSTEMS 1
_19199__ _19199
________ F.
STANDARD AND EMERGENCY OPERATING PROCEDURES
- aldz99__ _19199
________ G.
RADIATION CONTROL AND SAFETY 199s99__
Totals Final Grade 1
1 All work done on this examination is my own.
I have neither given I
nor received aid.
i Candidate's Signature 1
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
1.
' Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2.
Restroom trips are to be limited and only one candidate at a time may leave.
You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
3.
Use bla'ck ink or dark pencil gely to facilitate legible reproductions.
4.
Print your name in the blank provided on the cover sheet of the examination.
5.
Fill in the date on the cover sheet of the examination (if necessary).
6.
Use only the paper provided for answers.
7.
P,rint your name in the upper right-hand corner of the first page of each section of the answer sheet.
8.
Consecutivel y number each answer sheet, write "End of Category __" as appropriate, start each category on a ogw page, write gnly gn ggg sidg of the paper, and write "Last Page" on the last answer sheet.
9.
Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least threg lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations on1.y if they are commonly used in facility literaturg.
- 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 DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the g>1ami ner only.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.
This must be done after the examination has been completed.
~
~
[ ' ' '18.
When you complete your examination, you shall:
.a.-
Assemble-your. examination as follows:
-(1)-
Exam questions on top.
(2)
Exam aids - figures, tables, etc.
'(3)
Answer pages including-figures which' are part of.the answer.
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 for answering the questions.
d.
Leave the examination area, as defined by the examiner.
If after leaving, you are found in this area while the examination is still
]
in progress, your license may be denied or revoked.
+
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' QUESTION A.01 (1.50)
Reactor power is 100 watts and increasing on a 30 second period.
How
.long will it take for the reactor power to reach 1000 watts?
Show your work.
QUESTION A.02 (2.00)
Explain why xenon 135 concentration peaks after a reactor shutdown from high reactor power.
QUESTION A.03 (1.50)
Ex' plain how and why a moderator temperature increase will affect control rod worth.
QUESTION A.04 (2.00) a.
Explain the difference between K infinite and K effective. (1.0) b.
If the value of K effective of a reactor is 1.08, what is the value of K excess of this reactor? (0.5) c.
If the value of K effective of a reactor is 1.08, what is the value of the reactivity of this reactor? (0.5)
QUESTION A.05
(.50)
What is (are) the mechanism (s) by which samarium 149 is removed from the core?
QUESTION A.06
(.50)
What gas wculd be evolved by an aluminum-water reaction?
QUESTION A.07 (1.00)
Name two methods of generating source neutrons at the FNR.
(***** CATEGORY A CONTINUED ON NEXT PAGE
- )
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8t__EBINQlE6ES_QE_BE8QIQB_QEEB811gN PAGE 3'
QUESTION A.OB (1.00)
Why does the effective delayed neutron fraction differ from the delayed neutron fraction?
e QUESTION A.09 (2.00)
Explain why the Doppler coefficient is an important factor in reactor stability.
'OUESTION A.10 (2.00)
What are the two shutdown margin criteria specified in Technical
~
Specifications relative to the cold, xenon free critical condition?
e
(***** END OF CATEGORY A
- )
- B:__EE@IgBE@_OE_E9C1611y_DE@l@N PAGE 4
QUESTION B.01
(.50)
Choose the CORRECT response.
The active fuel meat is composed of:
i-e.
metallic uranium.
b.
uranium alumide, c.
uranium oxide, d.
uranium hydride.
QUESTION B.02
(.50)
Wh,at material is used to make the fuel cladding?
1 QUESTION B.03
(.50)
What is the enrichment of the uranium used in the FNR7 OUESTION B.04 (1.50) a.
What is heavy water? (0,5) b.
What is the primary purpose of the heavy water tank? (1.0)
QUESTION B.05 (1.50)
Describe the construction of the:
a.
shim rods. (0.75) b.
control rod. (0.75)
QUESTION B.06 (1.50) 4 Name two of the three conditions which must be satisfied in order for the reactor to be considered secured.
4 4
(***** CATEGORY B CONTINUED ON NEXT PAGE
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~ QUESTION B.07
'(2.00)
With what four circuits are the bridge controls interconnected in order to prevent bridge movement while the reactor is in operation?
QUESTION B.08 (1.GO)
What is the purpose of the holes drilled through the gridplate at locations on the diagonal between the fuel element holes?
QUESTION B.09 (1.00)
Ho,w is the buildup'of oil and dust on the reactor pool surface prevented?
QUESTION B.10 (1.00)
Specify the position (open or shut) in which valves 1,
2, 3 and 4 of Figure 11.1 must be placed in order to move the rabbit from the core to the dispatch station.
QUESTION B.11 (2.00)
What two functions are provided by the steam line which enters the secondary coolant system at the heat exchanger inlet?
4 QUESTION B.12 (1.00)
I Other than adding chemicals, how is the quality of secondary coolant maintained?
i b
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(***** END OF CATEGORY B
- )
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QUESTION C.01 (3.00)
What are the approximate values of the following FNR Reactor Physics Constants?
c.. Temperature coefficient (0.5) b.
Void coefficient-(0.5) c.
Power defect at 2 MW (0.5)
-d.
Equilibrium xenon reactivity (0.5) e.
Shim rod worth (0.5) f.
Control rad worth (0.5)
QUESTION C.02 (3.00) 4 What are the typical values of the following primary coolant system parameters at a power level of 2 MW ?
a.
Bulk pool temperature (0.5) b.
Heat exchanger inlet temperature (0.5) f c.
Hot demineralizer flow (0.5) d.
System loss due to leakage and evaporation. (0.5) e.
Primary coolant conductivity. (0.5) f.
Primary coolant pH. (0.5)
QUESTION C.03 (1.00) 1 Explain why tube leaks in the heat exchanger would flow from the 4
secondary into the primary?
(***** CATEGORY C CONTINUED ON NEXT PAGE
- )
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QUESTION C.04 (2.00)
What are_ typical values or ranges in values for the following secondary system parameters 7 c.
Coolant ^ flow rate. (0.5) b._ System loss due to evaporation. (0.5) c.
City water makeup. (0.5) d.
Optimum pH range. (0.5)
QUESTION C.05 (2.00)
Wh'at two chemicals are added to the secondarf system and why is each added?
QUESTION C.06 (1.00)
Answer the foltowing True/ False questions a.
Fuel elements should be laid down on the convex plate side. (0.5) b.
Fuel elements will be moved within the grid by hand. (0.5)
DUESTION C.07 (1.00) e a.
In an emergency situation per t.-
judgment of the ____________ fuel may be moved withont an approved Fuel Movement Schedule. - (0. 5) b.
Whenever new fuel elements are being transferred into or from the fuel vault the reactor building third floor becomes a ____________ area. (0.5)
QUESTION C.08
(.50)
When can fuel transfers into and out of the core be done without an operator in the control room monitoring an LCR channel 7
(*****
CATEGORY C CONTINUED ON NEXT PAGE
- +**)
C,.__ggNEB86_QBgB6IING_gM689CIEBISIICE PAGE 8
QUESTION C.09
(.50)
Who is responsible f or deciding when the procedure for determining the critical mass of an unknown core configuration is to be implemented?-
(***** END OF CATEGORY C
- )
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PAGE 9
QUESTION D.01 (1.50)
Explain the prinexple of operation of the primary coolant flow rate detector.
QUESTION D.02 (2.00) a.
Describe the location of the temperature sensors for the reactor pool temperature measurement system. (1.0) b.
Knowing the value of the primary coolant temperature at the inlet and
-exit of the heat exchanger, and the primary coolant flow rate, explain how to determine the thermal power output of the core. (1.0)
QUESTION D.03 (1.00)
What does a green beamport door status light signify when it is illuminated?
QUESTION D.04 (1.50)
Name the three scram interlocks which can be bypassed.
QUESTION D.05
(.50)
Startup will not be attempted with any instrument bypassed unless the bypass is specifically authorized on the _____.
QUESTION D.06 (1.00)
How is an alarm condition indicated on the scram alarm lights?
(Which light (s) illuminate, which light (s) extinguish?)
OUESTION D.07 (1.50)
What two conditions will cause the control rod limit annunciator to alarm?
Include setpoints.
(***** CATEGORY D CONTINUED ON NEXT PAGE *****)
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PAGE 10 QUESTION D.08 (2.00)
- o. Which reactor safety channel is a compensated ion chamber? (0.5) i b.
Explain how a compensated ion chamber is designed to compensate.for the gamma signal. (1.5)
QUESTION D.09 (2.00)
- a. What type of detector is the LCR channel? ( 0.-5 )
6.
How does the LCR' channel differentiate between neutrons and other radiation emissions? (0.5) c.,Why does the LCR channel have to be raised as power is increased? (0.5) d.
What interlock is associated with the LCR channel? (0,5)
OUESTION D.10 (1.00) a.
Which reactor safety channels are uncompensated ion chambers? (0.5) b.
Why is compensation not required for these reactor safety channels? (0.5)
(***** END OF CATEGORY D
- )
Ez__E6 Eely _6Np_gbEBGENGy_SYSIEdQ PAGE 11 d
(2.00)
QUESTION E.01 Name five components which'can receive emergency powerEfrom the emergency generator..
QUESTION E.02 (1.00)
What is the purpose of the water lock system in the south end of the reactor pool?
QUESTION E.03 (1.00) i What is the primary purpose of most of the neutron collimators used at FN'R?
i -
QUESTION E.04.
(.50)
What device is used to prevent the circulating water from flowing through the large unused holes in the gridplate and bypassing.the fuel elements?
i OUESTION E.05-(1.00)
F l
Without the hold down mechanisms, a rod could-jam within the control
}
element such that the drive mechanism would lift both the rod and control element out of the core lattice.
Explain why this is a potentially serious problem, 4
4 OUESTION E.06 (1.00)
What are the primary and backup sources of nitrogen?
4 OUESTION E.07 (1.00)
Would the irradiated fuel elements i n the spent fuel storage racks be adequately cooled if the water surrounding them was removed?
Explain.
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(***** CATEGORY E CONTINUED ON NEXT PAGE
- )
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.PAGE 12 QUESTION E.08 (2.00)
How is'the header designed to allow flow down through the core while in forced circulation, and flow up through the core while in natural circulation?
QUESTION E.09
(.50)
What system provides emergency fill for the reactor pool?
QUESTION E.10 (2.50)
Na,me five conditions, including setpoints, which will cause an automatic reactor scram.
QUESTION E.11 (1.00)
I.
Name two conditions, including setpoints, which will cause an automatic rod rundown.
OUESTION E.12
(.50)
During reactor operation, reactor air pressure will be maintained above _____.
QUESTION E.13 (1.00)
Name the four interrelated variables which are defined by Technical Specifications as the forced convection safety limits.
Setpoints are not required.
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(***** END OF CATEGORY E
- )
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PAGE 13 QUESTION F.01 (1.00)
What two actions must be taken if the Log N channel starts acting crratically during a reactor startup?
QUESTION F.02 (1.00)
What two actions must be taken if the reactor becomes critical with the' chim safety rods below the " Shim Range" position?
QUESTION F.03 (1.00) a..During startups, except rod calibration, shim rod positions will be kept within a distance of _____ of each other. (0.5) b.
Power level increases will not be made with the reactor on a stable positive period of less than _____. (0.5)
DUESTION F.04 (1.00) a.
Startup of the reactor will be under the direction of the _____. (0.5) b.
For startups following shutdowns in excess of.one hour, reactor power shall be raised to a maximum of (0,5)
OUESTION F.05 (1.00) a.
Who promulgates temporary operating instructions to the operating crews? (0.5) b.
Who is responsible for the conduct of control room visitors? (0.5)
OUESTION F.06 (1.00)
What two actions must the operator on duty perform if he is informed that the Ann Arbor area has been placed under a tornado warning?
(***** CATEGORY F CONTINUED ON NEXT PAGE +++**)
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PAGE 14-QUESTION F.07 (2.00)
What five actions must the console operator take during a building ovacuation in order to secure the reactor?
OUESTION F.08 (2.00)
What five actions must the plant operator perform during a building evacuation before proceeding to the lobby?
DUESTION F.09 (1.00)
Th,e first operator to arrive at the lobby during a building evacuation will wait for the second operator to arrive.
What action must the first operator take if the second operator does not arrive within 5 minutes of the first operator?
OUEST10N F.10
.(2.00)
During an evacuation due to a fire, the lead operator will await the arrival of the fire department at the south side door entrance to PML.
a.
What three items of information are required to be given to the fire captain by the lead operator when the fire department arrives? (1.5) b.
What other duty is the lead operator required to perf orm when the fire department arri'ves? (0.5)
OdESTION F.11 (1.00)
Answer the following True/ False questions.
a.
If a " duress" alarm is received at the control room, the operator on duty should initiate the building alarm. (0.5) b.
Work scheduled on the Shutdown Maintenance Schedule is considered approved. (0.5)
(***** CATEGORY F CONTINUED ON NEXT PAGE
- )
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QUESTION F.12 (1.00)
- o. As a temporary condition while transferring unirradiated fuel between the vault and the reactor pool, the fuel can be laid down in a row on a flat surface with not less than a distance of _____ between each element. (0.5) 6.
The control system isolation switches should be opened whenever a power failure persists for a period of time in excess of (0.5) i j
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(*****
END OF CATEGORY F
- )
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@z__R@Ql@I1QN_GQNI6Q6_@ND_S@EEIY PAGE 16 l
l QUESTION G.01
(.50) l Which radioactive liquid retention tank is normally reserved for higher l
'cctivity level liquids?
OUESTION G.02
(.50) l Each radioactive liquid drain is painted _____.
QUESTION G.03
(.50)
How many curies of radioactive liquids does the University of Michigan el,l ot the FNR to discharge into the sanitary sewer system per year 7 QUESTION G.04 (1.00) a.
How is tritium generated at FNR7 (0.5) b.
What characteristic of tritium causes it to be specifically mentioned in Tech Specs? (0.5)
OUESTION G.05
(.50)
How is argon 41 formed at FNR7 OUESTION G.06 (2.00)
Name the five radiation monitors, other than the building air exhaust NMC, which must be operable prior to making the reactor critical.
QUESTION G.07 (2.00)
Name f our automatic actions which will occur if the building exhaust NMC radiation monitor reaches its alarm setpoint?
(***** CATEGORY G CONTINUED ON NEXT PAGE
- )
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?l c.
In no case, during normal conditions, will an operator allow hi msel f or others to receive a dose of more than _____ per week. (0.5) j i
b.
How much radiation dose to the skin is a 17 year old allowed by 5
h' 10CFR2O to receive in one calendar quarter ? (0.5) i c.
How can an individual receive radiation exposure to the skin of the
[
whole body without also receiving whole body radiation exposure? (0.5)
)
[
I OUESTION G.09
(.50) a What is meant by the term "high radiation area"?
fi QUESTION G.10 (1.00)
The holdup tank is needed to allow time for a certain radionuclide to decay to a safe level.
i a.
What in this nuclide? (0.5) l b.
How is this nuclide produced at FNR? (0.5) i OUESTION G.11 (1.00)
What is the purpose of the lead sleeve which is placed around the beamport plug?
I OUESTION G.12 (1.00) a.
Whose approval must be obtained in order to raice the alarm setpoint of a radiation monitoring system radiation detector above its normal alarm setpoint? (0.5) b.
Who can initiate the building emergency procedure? (0.5) s
(*****
CATEGORY G CONTINUED ON NEXT PAGE
- )
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QUESTION G.13 (2.00)
What acti.on must be taken if the following circumstances occur during l
reactor operation.
Consider each situation separately.
- a. Cne airborne radioactivity monitor. unexpectedly alarms. (1.0) b.
Two airborne radioactivity monitces unexpectedly alarm. (1.0) h 4
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(***** END OF CATEGORY G
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(************* END OF EXAMINATION ***************)
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-.-w-,
-4,,
N F.00ATIONS S
REACTOR THEORY RADIATION Fl.UIDS/THERMO/ NEAT TRANSFER i
....>.-c I
e g
P = P,e /t = P,10 N = N,e m = A191V1 = AapzVa t
SUR.1
-1t i
A = AN Q = AhV1 = A2Va
=b+0~D
~#
or T
=
t p
10 Ap y,g,-ux = I 10-x/ M E, = E,,t + A Estored g
k-1 km - k p=
i = Ag AT = 0.693 E = KE + PE + U + PV+Q+W 6CE Y
R/hr 9 d feet =
g g D
k<1
~
8 2
Point source c
=
2 cpa
,1-k2 Idt lada a
=
l Is a y i
itd Inda line source 3,
g-=1-k H
R/hr x time - R reduced for - turbine. SG pump. nozzle.
i P pe. Rx j
g-cps or Co. con en8".
Rad x QF = Rem H
- cps, g
flow a (dp Th,g g = gBio Rad L ya Tbgg, + TisRad D 2g "nat "ODdoppler + Omod + Dvoid c
head lose a Ap
+DXe
- DSm * "Pu +
P"h +Pambient
=k i
2E F = PA c
- 4. pfuel +
Boron + prod p
AP1 ap2
=
phee phase x K (9"*
"I o
Poisons Pump laws speed a flow ka = kg + Sk (speed)2a pressure (8 Peed)3a Power 6k=k-1 MATil Q = kAaT = hAa7 = UAaT SUR =
y
=b 0 " *
- PAT Q = mah log b=a rgy
,3, q,g 3.1 x 101o log x = c log x all = m e. aT P
j log 1 = log x - log y AU = m c. AT E = No y
v 1
i log xy = log x + log y H=U+pV as = ^_2 l
Defect = Coeff x 4 Parameter T
PV = nRT l
l n i.. E112 v
T1 T2 i
C Vi + C V = C (Vi + V )
f}
A h v s e/2 ;(g" ~
&p,(,m.._ %:'.
~
m dt 1
sw o.
2..
m O___CBINQlELE@_QE_BE@CIQB_QEEB811QN PAGE 19 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER A.01 (1.50)
P = Po (e exp (t/T))
(0.5)
P/Po = e exp (t/T)
In(P/Po) = t/T t=T (In(P/Po))
(0.5) t=
(30 sec) x in(1000/100) t=
(30 sec) x In(10)
(30 sec) x 2.3
=
t = 69 seconds (0.5)
REFERENCE Introduction to Nuclear Reactor Operations, 1.2 1
ANSWER A.02 (2.00) i When the reactor is shutdown, the flux decreases to a low level which can be treated as if it were zero.
The fission yield and the burnout of xenon decrease to zero. (0.5)
Xenon continues to be produced by iodine decay and depleted by its own decay (0.5).
Because the xenon half-life is longer than iodine's, xenon builds up to a peak as iodine decays to xenon faster than xenon is decaying. (0.5)
Gradually the iodine depletes such that xenon decays at a faster rate than i odine decays to xenon, so the xenon concentration decays to zero. (0.5)
REFERENCE Introduction to Nuclear Reactor Operations, 8.4 1
ANSWER A.03 (1.50) 4 Control rod worth increases. (0,5)
As moderator temperature increases moderator density decreases. (0.5)
As the density decreases, moderation decreases and the probability of leakage into the control rods increases, which increases the effectiveness of the control rods. (0.5)
REFERENCE Introduction to Nuclear Reactor Operations, 7-12
~
~ -, - - -,. - - - - -
7 e- - - -,, - - - -
e
A ehiWGIFLES OF REACTOR OPERATION PAGE 20 z
ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER A.04 (2.00) a.
K infinite is the multiplication constant for a theoretical reactor with zero leakage (0.5).
K effective takes into account neutrons lost to slow and fast leakage (0.5).
(K effective equals K infinite multiplied by the fast and slow non-leakage probabilities.)
.08 (0.5) 1.08 - 1 b.
K excess = K effective - 1
=
=
c.
Reactivity = (K effective - 1)/(K effective)
(.08)/(1.08)
Reactivity = (1.08 - 1)/(1.08) =
Reactivity =.0741 delta K/K (0.5)
REFERENCE In,troduction to Nuclear Reactor. Operations, 3.3, 6.2 ANSWER A.05
(.50)
Neutron absorption REFERENCE Introduction to Nuclear Reactor Operations, 8.7 I
ANSWER A.06
(.50)
Hydrogen REFERENCE University of Missouri Hazards Summary 13-22 ANSWER A.07 (1.00)
Antimony-beryllium source (0.5)
Deuterium decay caused by gamma interaction in the heavy water tank (0.5)
-REFERENCE Gary Cook, FNR Introduction to Nuclear Reactor Operations, 5.2
6t__EBIUc1ELES_gB_SESCIQB_gBEBOIl90 PAGE 21 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER A.08 (1.00)
Delayed neutrons are born at lower energies (0.5) so they are less likely to leak out of the core (0.5).
REFERENCE Introduction to Nuclear Reactor Operations, 3.2, 3.3 4
4 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 U 238, which has large resonance absorption peaks.
(0.5)
The increased thermal moticn of the U 238 as power increases causes more neutrons over a range of energies to have the proper ener gy for resonance absorption. (0.5)
Therefore as power increases more neutrons are absorbed parasitically by the U 238, reducing the core 's r eacti vi ty (0.5).
REFERENCE I nt r oduc ti ore to Nuclear Rcactor Operatione, 6.4.4 ANSWER A.10 (2.00) 1.
.025 delta K/K with all three shim safety rods fully inserted and the regulating rod fully withdrawn. (1.0) 2.
.0045 delta K/K with the most reactive shim saf ety rod f ully withdrawn. (1.0)
REFERENCE Tech Spec 3.1 (1)
Eg81UBE@_QE_E9Cl(ITy_DESl@N PAGE 22 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER B.01
(.50) b.
REFERENCE System Descriptions 2.1 ANSWER B.02
(.50)
Aluminum REFERENCE System Descriptions 2.1 ANSWER B.03
(.50) 19.5%
^
REFERENCE System Descriptions Table 2.1 ANSWER B.04 (1.50) a.
Water which has at least one hydrogen atom replaced by a deuterium atom. (0.5) 6.
Provide a thermal neutron source for the beamports. (1.0)
REFERENCE
)
System Descriptions 3.1 ANSWER B.05 (1.50) a.
stainless steel with 1.5% baron. (0.75) b.
hollow stainless steel shell. (0.75)
REFERENCE Gary Cook, FNR l
m r__
,____,,m._r,.,.,-..
.-.__.__-.-__..-_,,m.-.
______,-,mm.
PAGE 23 Dz__EE6lyBES_DE_EOClbily_DEglGN ANSWERS -- UNIVERSITY OF MICHIGAN
-96/10/07-HIGGINS, R.
ANSWER B.06 (l.50)
(Any two of the following at.75 each) 1.
Full insertion of all control rode is verified.
2.
Contrel concole key is removed.
- 3. No operation is in progress which involves fuul movement to or from the core, the insertion or removal of secured experiments f rom the core, reflector element movement to or from the core, or control rod maintenance.
REFERENCE Tech Specs, p3 ANSWER B.07 (2.00) 1.
primary cool ant pump circui t.
(0.5) 2.
safety and control rod circuit. (0.5) 3.
bridge locking circuit. (0.5)
.0.5)
(
4.
rod magnet circuit.
REFERENCE Systeni Descriptions 3.3 ANSWER B.08 (l.00)
I Either of the f ollowing for full credit.
1.
Permit circulation of cooling water between the fuel elements.
- 2. Supplement i1ow moving through the fuel element.
REFERENCE System Descriptions 3.3 ANSWER B.09 (l.00)
Pool water is drawn into two ekimmers by a pump, then pumped tbrough a sand fi1ter and back to the pool.
i REFERENCE System Descriptions 3.5 y
E2__EEAlyBEg_DE_EAC16ITY_DEgl@N PAGE 24 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER B.10 (1.00) 1.
Shut 2.
Open 3.
Open 4.
Shut REFERENCE System Descriptions Figure 11.1 ANSWER B.11 (2.00) i 1.. Heats the primary coolant if its temperature is too low. (1.0) 2.' Provides steam to clean heat exchanger tubes which become obstructed by mineral deposits. (1.0)
REFERENCE System Description 5.3.3 ANSWER B.12 (1.00)
Continuously renewing the water by blowing down and replacing the lost
-water with fresh weter.
REFERENCE System Description 5.3.7 1
t t
.-.pe.
-,n.--n-
._n.e.,
e
G.
_GENEBO(_QPEBBIING_gHOB6GIEBlGIlGE PAGE 25 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER C.01 (3.00) a.
-5. 5 :: 10 exp -3 % dk/k/F b.
-1.0 % dk/k/% void c.
-0.25 % dk/k d.
-2.2 %dk/k e.
between 2.0 - 2.5 % dk/k f.
between 0.25 - 0.4 % dk/k REFERENCE System Description Table 2.3 ANSWER C.02 (3.00) a.
104 F b.
119 F c.
25 GPM d.
150 GPD e.
less than 5 micro mhot f.
between 5.0 and 7.0 REFERENCE System Descriptions 4.1, 4.2, 4.3 ANSWER C.03 11.00)
Greater hydrostatic head of the secondary coolant.
-or-The water level in the cooling tower sump is higher than the top of the reactor pool.
REFERENCE System Description 5.3.3 ANSWER C.04 (2.00) a.
1000 GPM b.
14 - 16,000 GPD c.
25 - 50,000 GPD d.
6.4 - 6.8 (5.0 - 7.0)
=
i PAGE 26 G___QENEBO6_QBEBOIING_QUGBGGIEBlEl1G@
ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
REFERENCE System Description D.3.9 and 5.4 ANSWER C.05 (2.00)
- 1. Hagatreat controls corrosion and scale formation. (1.0) 2.
Sulfuric acid maintains pH less than 7.
(1.0)
REFERENCE System description 5.3.9 ANSWER C.06 (1.00) a.
False b.
True REFERENCE OP106 steps 5.1.3 and 7.1.2 ANSWER C.07 (1.00) a.
Lead Reactor Operator b.
Control l ed access i
REFERENCE j
OP 106 steps 5.3.1 and 6.4 1
4 ANSWER C.08
(.50) j When loading fuel will not result in a core which is capable of going l
critical.
{
Never.
}
REFERENCE j
OP - 106 steps 7.1.4 t
ANSWER C.09
(.50)
Reactor Manager
'6
- - ma
G:__SENEB66_OBEBBIING_GH686GIEBl@IlG@
PAGE 27 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
REFERENCE OP -113 step 4.1 e
l
D __1 Ngl 8UMENI@_8NQ_QQNIBQL@
PAGE 28 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER D.01 (1.50)
The pressure on both sides of a flow orifice in the primary coolant' return line is compared. (0.75)
The drop in pressure from the upstream side to the downstream side of the flow ori.fice is proportional to the flow rate. (0.75)
REFERENCE System Descriptions 4.3.10 ANSWER D.02 (2.00) a., It is composed of two temperature sensors positioned 2 feet and 20 feet below the surface.cf the water.
b.
Multiply the coolant flow rate by the temperature difference between the inlet and outlet of the heat exchanger, the multiply this number by the heat capacity of the coolant.
REFERENCE System Descriptions 3.1 ANSWER D.03 (1.00)
The door is interlocked to the scram system.
REFERENCE System Descriptions 13.1.1 ANSWER D.04 (1.50) 1.
Individual beamport door scrams. (0.5) 2.
Thermal column door scram. (0.5) 3.
Shim range bypassed scram. (0.5) l REFERENCE OP-111 step 4 1
1 1
m PAGE 29 D&__INSIBUMENIS_AND_GQNIBQL@
ANSWERS --' UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER D.05
(.50)
Operation Schedule REFERENCE OP-102 step 4.2 ANSWER D.06 (1.00)
Tne red light illuminates (0.5), the amber light is extinguished. (0.5)
REFERENCE System Descriptions 13.1.1 ANSWER D.07 (1.50) i Control rod above the upper limit (0.5) ef 23.5 inches (.25) or belou the lower limit (0.5) of 5.0 inches (.25).
REFERENCE System Descriptions 13.1.1 l
t ANSWER D.08 (2.00) a.
Channel C,
or Log-N period channel. (0.5) b.
The compensated ion chamber consists of two separate chambers or 4
sealed concentric cylinders filled with nitrogen or ar gon gas. (0.5)
The outer cylinder is lined with baron and is sensitive to neutrons and gammas, while the inner one has no boron lining so is sensitive only to gammas. (0.5)
With opposite potentials on these cylinders, the ion current due to gamma flux can be cancelled out, l eavi ng a net ion current due to neutrons alone.
(0.5)
I REFERENCE System Descriptions 13.2.1 i
I t
a w
ri l
Dt__INSIBydENI@_6NQ_ggNIBQ6@
PAGE 30 ANSWERS - ' UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER D.09 (2.00)
- c. Fission Chamber.
b.
Pulse Height Discriminator.
c.
Maintain indication on scale. OR Prolong the detector's useful lifetime.
d.
Shim safety rods can not be. withdrawn'unless the LCR channel indication is greater than 5 cps.
REFERENCE System Descriptions 13.4.1 and 13.4.3 ANSWER D.10 (1.00) f f
a.
Channels A and B.
b.
These channels monitor the reactor at high power levels where the neutron flux is much greater than the gamma flux.
REFERENCE System Descriptions 13.2.1.and 13.13.4 t
5 y
.--e v
-e-.-~
-y-,,
-~v
E __@@EEIy_6ND_EdE6G@NCy_@y@lEMS PAGE 31 2
ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
l ANSWER E.01 (2.00)
(Any five of the following at
.4 each) 1.
Radiation monitoring equipment.
2.
Building lighting.
3.-Alarm systems.
4.
FNR ventilation system.
5.
Bridge drive circuit.
6.
Heavy water tank control unit.
7.
Telephone system.
8.
Pneumatic tube system.
9.
Backup reactor air compressor.
REFERENCE System Descriptions 14 ANSWER E.02 (1.00)
Provide a means for transferring highly radioactive samples, e:; peri ments and r.eactor fuel from the pool to a shielded hot cave.
REFERENCE System Descriptions 3.1 ANSWER E.03 (1.00)
Focus a large diameter neutron beam into a very narrow intense beam.
REFERENCE System Descriptions 3.2 ANSWER E.04
(.50)
Grid plug.
REFERENCE System Descriptions 3.3 4
E___S8EEIy_@ND_EMEBGENGy,,gySIEMS
'PAGE 32 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER E.05 (1.00)
The control element could subsequently drop back into the lattice (0.5) rapidly inserting positive reactivity (0.5).
REFERENCE System Descriptions 3.4 ANSWER E.06 (1.00)
Primary - liquid nitrogen tank. (0.5)
Secondary - nitrogen bottles. (0.5)
REFERENCE System Descriptions 3.6 ANSWER E.07 (1.00)
Yes.
Sufficient natural circulation cooling by air would be present.
REFERENCE System Descriptions 3.8 ANSWER E.08 (2.00)
The header is held up against the hopper when in forced circulation by the electromechanical header latching mechanism. (1.0)
When primary coolant flow ceases, the electromagnet is deenergized, allowing the header to pivot about a rotating flange and fall away from the hopper. (1.0)
REFERENCE System Descriptions 4.3 ANSWER E.09
(.50)
City Water.
REFERENCE System Descriptions 4.3.8 j
l
Ez__E8EEIY_6UD_ EMERGENCY _SYSIEMS PAGE 33 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER E.10 (2.50)
(Any five of the following at
.5 each) 1.
Period safety - 5 seconds or less.
2.
Level safety - 120% (2.4 MW) or greater.
3.
High power (above 100 KW)/no water flow -
a.
900 gpm or less.
b.
holding tank isolation valve not fully open.
c.
holdup tank static pressure 1 psig below the full power value.
4.
High power (above 100 KW)/ header down.
D.
Header up/no water flow - 900 gpm or less.
6.
Building exhaust radiation level - 1 mr/hr or greater.
7.
Bridge not clamped - when clamps released.
8.
Beamport door - opened when interlocked.
9.
Fuel vault criticality detector - 5 mr/hr or greater.
REFERENCE Tech Specs Table 3.1 System Descriptions 13.1.1 ANSWER E.11 (1.00)
(Any two of the following at
.5 each) 1.
Reactor coolant exit temperature - 129 F or greater.
2.
Pool level - 1 foot or more below pool overflow.
[
3.
Reactor period - less than 10 seconds.
4.
Linear power level - 115% of linear power range or greater.
5.
Control rod at lower limit with the reactor in servo control.
REFERENCE Tech Spec Table 3.1 l
System Descriptions 13.3.3, 13.5.3 i
l i.
ANSWER E.12
(.50) 55 psig REFERENCE System Descriptions 10.2
. Et__50EEIY_@ND_EME8GENQY_@Y@IEd@
PAGE 34
' ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
' ANSWER E.13 (1.00) 1.
Reactor thermal power. (0.25) 2.
Reactor coolant flow through the core. (0.25) 3.
Reactor coolant inlet temperature. (0.25) 4.' Height of water above the top of the core. (0.25)
REFERENCE Tech Spec 2.1 9
P
Ei__SIONQ8BQ_8NQ_EMEBGENCY_QBEB8IING_BBOCEQUBE@
'PAGE 35 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER F.01 (1.00)
'1.
Scram the reactor. (0.5) 2.
Immediately notify the Supervisor of Reactor Operations, the Assistant Reactor Manager or the Reactor Manager. (0.5)
REFERENCE OP-102 step 4.3' ANSWER F.02 (1.00) 1.
Shutdown the reactor. (0.5) 2.
Notify the Supervisor of Reactor Operations, the Assistant Reactor Manager or the Reactor Manager. (0.5)
REFERENCE OP-102 step 4.5 ANSWER
'F.03 (1.00) a.
2.5 inches.
b.
30 seconds.
REFERENCE OP-102 steps 4.6 and 4.7 ANSWER F.04 (1.00)
- a.. Lead operator, b.
1 MW.
REFERENCE OP-102 steps 5.4 and 5.5
E=__EIONQ88Q_8NQ_EMEBGENCY_QBEB811NG_BBQCEQUBES PAGE 36 ANSWERS -- UNIVERSITY OF MIbHIGAN
-86/10/07-HIGGINS, R.
ANSWER F.05 (1.00) a.
Supervisor of Reactor. Operations, Assistant Reactor Manager or Reactor Manager.
b.
Console operator.
REFERENCE OP-104 steps 7.4 and 7.6 ANSWER F.06 (1.00) 1.. Shutdown the reactor. (0.5) 2.
Prop open all three personnel access doors. (0.5)
REFERENCE
-OP-101 step 6.4.3 ANSWER F.07 (2.00) 1.
Push the console scram button. (0.4) 2.
Place the rod drive switches in the insert position. (0.4) 3.
Verify that a scram has occurred. (0.4) 4.
Turn off the pneumatic blower. (0.4) 5.
Remove the magnet key and retain it and the logbook. (0.4)
REFERENCE OP-101 step 7.3.1.1 ANSWER F.08 (2.00) 1.
Go to the beamport floor. (0.4) 2.
Verify that all personnel have evacuated and that all beamport floor exit doors are closed. (0.4) 3.
Close the stack 2 exhaust damper. (0.4) 4.
Exit through the first floor door and verify that it is closed. (0.4) 5.
Verify that all personnel have evacuated the first floor of the PML.
(0.4)
REFERENCE OP-101 step 7.3.2
Et__EIGNQ6BQ_6NQ_EMEBGENQY_QBEB@llNG_EBQCEQUBE@
PAGE 37 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER F.09 (1.00)
The first operator can retrace the second operator's route and britig him to the lobby.
REFERENCE OP-101 step 8.1 ANSWER F.10 (2.00) o.
(.5 each) 1.
Whether the radiation levels were normal prior to the fire.
2.
Location of any high level radiation sources.
3.
Whether the MAP monitors were alarming at the. time of the building evacuation, b.
Issue film badges to fire department personnel. (0.5)
REFERENCE OP-101 step 8.2.3 ANSWER F.11 (1.00)
- c. False b.
True REFERENCE OP -104 steps 11.1 and 14.3.3 ANSWER F.12 (1.00) a.
6 inches.
b.
10 seconds.
REFERENCE OP-106. step 5.1.2 OP-108 step 3
Gi__BBDIGIJ,gN_CgNIBg6_8UD_@@EEIY PAGE 38 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER G.01
(.50)
Tank 3.
REFERENCE System Descriptions 9.1 ANSWER G.02
(.50)
Yellow.
REFERENCE System Descriptions 9.1 ANSWER G.03
(.50)
.5 REFERENCE System Description 9.1 ANSWER G.04 (1.00) a.
Eith,er of the following:
1.
Neutron absorption by deuterium.
2.
Ternary fission.
b.
Any one of the following:
1.
Hard to detect.
2.
Can combine with oxygen to form water.
1 3.
Impossible to filter out.
4.
Easily enters the human body.
REFERENCE Tech Spec 3.5 ANSWER G.05
(.50)
Neutron absorption by the argon which comprises 1% of air.
Ga__B8Q1811gN_CgNIBQ6_@ND_S@EEIY PAGE 39 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
REFERENCE Tech Spec 4.6 ANSWER G.06 (2.00)
(.4 each) 1.
Bridge 2.
Northwest column 3.
North wall 4.
Northeast column 5.
Hot D.
I.
REFERENCE System' Description 13.9.1 ANSWER G.07 (2.00)
-(Any four of the following at
.5 each) 1.
Initiate building evacuation _ alarm.
2.
Scram the reactor.
3.
Shut down the FNR supply and exhaust dampers.
4.
Close the BHF dampers.
5.
Shut down the FNR ventilation fans.
6.
Shut down the PML supply and vent fans.
7.
Actuates the " radioactivity in building air" annunciator.
REFERENCE System Descriptions 13.9.1 ANSWER G.08 (1.50) a.
100 mrem.
_b.
.75 rems.
c.
Receive beta radiation exposure.
REFERENCE 10CFR20.101 and 104
Gz__B691011gN_CQNIBg6_@NQ_S8EEIY PAGE 40 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER G.09
(.50)
Area where an individual could receive a dose in excess of 100 mrems to a major portion of the body in one hour.
REFERENCE 10CFR20.202 ANSWER G.10 (1.00) a.
Nitrogen 16.
b.. Neutron / proton reaction with oxygen.
REFERENCE System Descriptions 4.3.3 ANSWER G.11 (1.00)
Prevent radiation streaming through the annular space between the plug and the port shell.
REFERENCE System Descriptions 3.2 ANSWER G.12 (1.00) a.
Reactor' Manager or Assistant Reactor Manager. (0.5) b.
Anyone. (0.5)
REFERENCE Tech Spec, p 14 OP-101 step 6.2.4
Gz__B0918I1QN_QQNIBQ6_6NQ_SOEEIY PAGE 41 ANSWERS -- UNIVERSITY OF MICHIGAN
-86/10/07-HIGGINS, R.
ANSWER G.13 (2.00) s.
Investigate the cause (0.5).
If the cause can not be determined, chutdown the reactor (.25) and notify the Reactor Manager, Assistant Reactor Manager or Supervisor of Reactor Operations (.25).
b.
Shutdown the reactor by inserting all rods (0.5).
If the reactor shutdown does not result i n cessation of the alarms, put the building smergency procedure into effect (.25).
If the shutdown does stop the alarms, immediately notify the Reactor Manager, Assistant Reactor Manager or Supervisor of' Reactor Operations (.25).
REFERENCE OP-101 step 6.2 1
,e
-,nn,
.n--
~ -