ML20203H565
| ML20203H565 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 02/11/1998 |
| From: | Isaac P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20203G100 | List: |
| References | |
| 50-020-OL-98-01, 50-20-OL-98-1, NUDOCS 9803030263 | |
| Download: ML20203H565 (17) | |
Text
_m U. S. NUCLEAR REGULATORY COMMISSION
- OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-020/OL-98-01 FACILITY DOCKET NO.:
50-020 FACILITY LICENSE NO.:
R 37 i
FACILITY:
Massachusetts institute of Technology EXAMINATION DATES:
January 30,1998 EXAMINER:
Patricid ac, Chief xaminer lc 8
SUBMITTED BY:
s Paph Isaa ef Examiner
' Ddte
SUMMARY
During the week of January 26,1998, the NRC administered a retake of Section B of the written examination to one Reactor Operator candidate. The candidate passed the
- examination.
REPORT DETAILS 1.
Examiners:
Patrick Isaac, Chief Examiner 2.
Rasults:
RO PASS / Fall SRO PASS / Fall TOTAL PASSIFAll Written 1/0 N/A 110 Operating Tests N/A N/A N/A Overall 110 N/A 1/0 ENCLOSURE 1 9803030263 900219 PDR ADOCK 05000020 V
m-NRC RESOLUTIONS WRITTEN EXAMINATION QUESTION (B.03) Facility Comment:
Question B3 does not appear to have a correct answer, We think the answer is 56 ft.
NRC Resciution:
Comment Accepted.- The answer key will be modified to accept 56 ft as the correct answer.
l QUESEON f B.131 Facility Comment:
Ques: ion B13 could have two answers if the evacuation is due to high radiation the answer is B.
If it is due to a fire, the answer is D.
NRC Resolution:
Comment Accepted. The answer key will be modified to accept both "b" and "d" as correct
- answers, t
QUESTION (B.171 Facility Comment:
Both action 8 and action D cre required by the procedure.
NRC Resolution; Comment Accepted. The answer key will be modified to accept both "b" and "d" as correct answers.
ENCLOSURE 2 a
l U. S. NUCLEAR REGULATORY COMMISSION NON POWER REACTOR LICENSE EXAMINATION FACILITY:
MIT REACTOR TYPE:
MITR-Il DATE ADMINISTERED:
1998/01/30 g.
REGION:
1 CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach any answer sheets to the examination. Points values are indicated in parentheses for each question. A 70% is required to pass the examination. Examinations will be picked up one (1) hour after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE
'lOTAL SCORE VALUE CATEGORY 20.00 100.00
- 8. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature ENCLOSURE 3
..B....NR?MAUEMERG PROCEDURES & RAD CON ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
MULTIPLE CHOICE 001 abcd 002 a b c d 003 a b c d g
004 a b c d 005 a b c d 006 a b c d 007 a b c d 008 a b c d 009 a b c d 010 a b c d 011 abcd 012 a b c d 013 a b cd 014 a b c d _..
015 a b c d 016 a b c d 017 a b c d 018 a b c d 019 a b c d 020 a b c d
("*" END OF EXAMINATION *"")
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.
i 2.
After the examination has been completed, you must sign the statement on the cover sheet indicating that the work la vour own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.
3.
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.
4.
Use black Ink or dark pencil onIV '* facilitate legiola reproductions.
5.
Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer sheet.
6.
Mark your answers on the answer sheet provided. UCE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
7.
The point value for each question is indicated in (brackets) after the question.
8.
If the intent of a question is unclear, ask questions of the examiner only.
9.
When tune;ng in your examination, assemble the comple:ed examination with examination questions, examination aids and answer sheets. In addition turn in all scrap paper.
10.
Ensure all information you wish to have evaluated as part of your answer is on your answer sheet.
Scrap paper will be disposed of immediately following the examination.
11.
To pass the examination you must achieve a grade of 70 percent or greater in each category.
12.
There is a time limit of one (1) hour for completion of the examination.
13.
When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked.
I EQUATION SHEET
= ac b T = a bH = UA b T (p-3)2 p
P"* " = 20(k)f
(* = S x 10~* seconds SCR = S S
=
-P 1 - K,,f 0.1 econds^1 h
=
err 3 = 0.0075
~P
'P I 1
1 2
2 1-K "*
h P
SUR = 2 6. 0 6 M=
err Qp 1-g err, 1
CR 3
p=p losuatti M=
=
0 1-K,,,
CR, (1-K,,)
.i SDM =
P=P e'
K,,,
n t'
D(1-p) p, p"
p-3 B-P err, - K,,, t g,
g_
g9,
k,,, x K,,,
p A,,,p 0.693
( K,,, - 1 )
T
=
A P_
err DR =DR e 'ht DR,d,* = DR,d,'
n 6CIE(n)
(P -0)
(P -0) 2 1
DR -
=
2 p
- Peak, Peak, I=I,e' 1 Curic = 3.7 x 10 dis /sec 1 kg = 2.21 lbm i BTU = 778 ft-lbf "F = 9/5 "C + 32 1 gal (H O) = 8 lbm C = 5/9 ( F - 32) 2 cp = 1.0 BTUllbml*F c, = 1 callsec/gml C
~
9 Section B: Normal /Emera. Procedures & Rad Con Page 1 Question- (B.1)
[1.0)
The maximum power level allowed without primary coolant pumps operating is:
a.
100 Watts-b.
.10 kW c.
100 kW d.
1MW 1
Question (B.2)
[1.0]
The basis for the D, concentration limit in the Helium gas cover blanket for the D O reflector 2
system is to; a.
minimize personnel radiation exposure.
b.
limit the disassociation of D 0 in the reflector.
2 c.
minimize the contamination of the Helium cover gas.
I d.
prevent a flammable concentration of D, gas in the Helium blanket.
i Question (B.3)
[1.0) i A small radioactive source is to be stored in the reactor building. The source is estimated to.
contain 2 curies and emit a 1.33 Mev gamma.
' Assuming no shielding was to be used, a Radiation Area barrier would have to be erected from the source at a distance of approximately:
a.
56 feet b.
12 inches c.
21 inches b
d.
4 feet k
2 1
4 Seg16pnB: Normal /Emera Procedures & Rad Con Page 2 Question (B.4)
[1.0)
Before any change is made in the core configuration (refueling), the proposed change must be reviewed and approved by:
a.
the Operator in charge and a Senior Reactor Operator.
I b.
a Senior Reactor Operator and the Reactor Superintendent.
c.
the MIT Reactor Safeguards Cornmittee and the Reactor Superintendent.
d.
the MIT Reactor Safeguards Committes and the Director of Reactor Operations.
Question (B.5)
[1.0)
A radiation survey performed 30 minutes after shutdown from a week of full power operation indicated 1500 mR/hr on contact with the main heat exchangers. Which one of the following is l
l true?
This reading is abnormal, most likely caused by fission produce.
a.
h.
This reading is abnormal, most hkely caused by tritium, 1
c.
This reading is normal, most likely caused by N 16.
d.
This reading is normal, most likely caused by Na 24.
Question (B.0)
[1.0)
In order to ensure the health and safety of the public,10CFR50 allows the operator to deviate from Technical Specifications. What is the minimum level of authorization needed to deviate from Tech. Specs?
a.
USNRC l
b.
Reactor Supervisnr c.
Licensed Senior Reactor Operator.
d.
Licensed Reactor Operator, m
4 Whn B: Normal /Emera. PrMadurou & Rad Con I
Page 3 Question (B.7)
[1.0]
What are fivt (5) requirements which must be observed gyhen
- locking out' facility equipment after permission is granted?
SRO will witness lockout, person performing work will perform lockout, person a.
performing work will retain the key on their persc~, the system must be tagged out, a notation as to the system being locked out thatl.)e made t n the status board, b.
SRO will witness lockout, SRO will verify safe system condition, Superintendent must be notified, the system must be tagged out, a notation as to the system being locked out shall be made on the status board.
SRO will verify safe system condition, any membor of the NRURRPO will witness c.
lockout, person performing work will perform lockout, person performing work will retain the key on their person, the system must be tagged out.
d.
SRO will witness lockout, any member of the NRURRPO Staff will perform lockout, the SRO Nill retain the key, the system must be tagged out, a notation as to the system being locked out shall be me.ds 9n the status board, t
Question (B.8)
(1.0)
Which one of the following states the radiation exposure limits in Rem deep dose equivalent that may be authorized by the Emergency Director during an emergency?
Establishing the Protection of Major Nuclear Safety Equipment Not Vital of the Reactor for Nuclear Safetv Life Savina Action a.
15 25
>25 b.
25 16 100 c.
15' 10 75 d.
25 10
>25 dbT
Section B:-Ijorma!!Emera. Proceduros & Rad con Page 4 Question (B.9)
[1.0) l A room oontains a source which, when exposed, results in a general area dose rate of 175 millirem per hour. This source is scheduled to be exposed continuously for 35 days. Select an
[
acceptable method for controlling radiat:0n exposure from the source witt,in this room.
- s.
Post the area with the words " Danger Radiation Area".
- b.
Equip the room with a device to visually display the current dose rate within the room.
c.
Equip the room with a motion detector that will alarm 1.i t.ie control room.
d.
Lock the room to prevent inadverten', entry 1..s the room.
Question (B.10)
[1.0)
Which one of the following is the definition for " Annual Limit on intake" (All)?
The concentration of a radionuclide in air which, if inhaled by an adult worker for a year, a.
res As in a total effective dose equivalent of 100 millirem, b.
10 CFR 20 derived limit, based on a Committed Effective Dose Equivalent of 5 rems whole body or 50 rems to any individual organ, for the amount of radioactive material inhaled or ingested in a year by an adult worker.
The effluent concentration of a radionuclide in air which, if inhaled continuously over a c.
year, would result in a total effective dose equivalent of 50 millirem for noble gases, d.
Projected dose commitment values to individuals, that warrant protective action following a release of radioactive material.
Question (B.11)
[1.0)
The for the MIT Rc--~h Reactor is taken to be a 100 meter zone that forms an annulus about the facility's containtr, ant building.
Which one of the following terms fits in the blank?
a.
Restricted Area
' b.
Site Boundary c.
Emergency Planning Zone d.
Operations Boundary
~_
Sestion B: Normal /Ernero Procedures & Rod con PageS Qvustion (B.12)
[1.0)
Which one of the following may be described as a ' Credible Accident Possibly Leading to an Off Site Radiological Emergency" at MIT7 a.
Loss of reactor shielding b.
Blockage of fuel element channels c.
Loss of coolan( above the 16 sel of the anti siphon valves.
d.
Occurrence of a severe storm, flood, or earthquakt Question (0.13)
[1,0)
In the event of an NW12 evacuation, where is the assembly area?
a.
Operations Oifice NW12110 b.
Rear of building NW13 c.
NW13 Receiving Room Area d.
Across Albany Street (from main entrance to NW12).
Question (B.14)
(1.0) in the event that a single plenum radiation monitor becomes inoperative due to a plugged flow line and the containment isolates, reactor ope. ration...
a.
is not allowed.
b.
may continue provided that the plugged flow line is replaced and ventilction restarted.
c.
may continue provided that the affected channel is bypassed using key switch and ventilation restarted.
d.
may continue provided that the affected channel is bypassed by selecting a different plenum channel and ventilation restarted.
Section B: Normal /Emera Procedures & Rad Con Page6 Question (B.15)
[1.0) in accordance with Standard Operating Procedure for Normal Reactor Startup, what should be your immediate response if the reactor goes critical at a position more than 0.5 iriches below the ECP?
a.
Shutdown b.
_ Stop and recalculate the ECP c.
Lower shim bank to subcritical interlock d.
Lower the shim bank at last one inch.
Question (B.16) l1.0]
An emergency shutdown was initiated from the control room console. Reactor power failed to decrease after the minor scram pushbutton was depressed.
Which ONE of the following actions should be taken first?
a.
Initiate a major scram.
b.
Insert the control rods.
c.
Dump the reflector.
d.
Evacuate the reactor buikting.
Question (B.17)
[1.0}
During a fuel transfer, the indicated risutron level increases by a factor of 2.5 while an element is being lowered into a core position. 'Which one of the following operator actions is required to be taken?
Evacuate personnel from the rea':. tor top.
a.
b.
Dump the reflector, if not akeady a Jmped.
Notify personnel on the reactor top tb position the element into the correct core position c.
and discontinue the fuel transfer.
d.
Notify personnel on the reactor top to irisert a dummy element in place of the fuel element just removed.
r k
i
Section 8: NolmalEmera. Procedures & Rnd Con Page 7 Question (8.18)
[1.0)
What 16 the basis for the Technical Specification that, ' Prior to transferring an irradiated element from the reactor vessel to the transfer flask, the element shall not have been operated in the core et a power level abova 100 kW for at least four days?
a.
To reduce in core radiation level before doing a refueling.
b.
To allow for the radioactive fission products to decay to an acceptable radiation level.
c.
To have time to prepare the fuel storage pool to accept the spent fuel element.
d.
To prevent melting of the fuel element from decay heat when it is being transferred.
Question (0.19) l1.0]
The MITR ll is operating at 4.9 MW. Due to higher than normal radioactivity in the c'f gas system, the space above the primary water poolis isolated. Which one of the followlog describes subsequent operations?
H, analysis shall be performed every hour. When greater than 1.5% [H,], reactor power a.
should be reduced to less than 1 MW to prevent H, concentration from exceedin) the T.S. limit of 3 5%.
b.
H, analysis shall be performed every 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. When greater than 1.0% [H,], reactor power should be reduced to less than 200 kW to prevent H, concentration from exceeding the T.S. lime of 3.5%.
c.
H, analysis shall be performed every hour. When greater than 1.5% [H,], reactor power should be reduced to less than 1 MW to prevent H, concentration from exceeding the T.S. limit of 4.1%.
d.
H, analysis shall be performed every 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. When grt ter than 1,0% [H,], reactor power should be reduced to le% than 200 kW to prevent H, concentration from exceeding the T.S. limit of 4.1%.
0 Section B: Normal /Emera. Procedures & Rad Con Page 8 Question (B.20)
[1.0)
Which one of the following is a rule to be observed by personnel performing experiments in the MIT reactor Combustible shall not be brought into the reactor building, a.
b.
The Operations Superintendent shall minimize the amount and concentration of Hydrochloric acid (hcl) Irradiated in the reactor, Corrosive liquids will not normally be irradiated in the reactor except when allowed by c.
the Operations Superintendent.
d.
The total worth of all non secured experiments is limited to 1.5% AK/K.
1
"*" END OF EXAMINATION *""
l l
= _
=
=
-m_----_---
Section B: Normal /Emera. Procedures & Rao con Page 9 ANSWER (B.01)
-c REFERENCE TS 2.2 ANSWER (B.02) d REFERENCE TS 3.3 ANSWER (B.03) a REFERENCE MIT Exam Bank #B-8 (modified); Glasstone & Sesonske, 9.41, p 525.
DR= 6CE/(f)(f) = 0.005 = 6(2)(1.33)/x, x' = 3192, x = 56.5 feet 8
ANSWER (B.04) b REFERENCE PM 1,15, p 1.
ANSWER (B.05) a REFERENCE AOP PM 5.0 ANSWER (B.06) c REFERENCE 10CFR50.54(y)
ANSWER. (B.07) a REFERENCE PM 1.14 ANSWER (B.08) d
-REFERENCE E Plan PM 4,7.5 Pg. 2 of 2 ANSWER (B.09) d REFERENCE 10CFR20.1601(a)(3)
L/AStI
y l
Section B: Normal /Emera Procedures & Rad Con Page 10 ANSWER (B.10) b REFERENCE Chapter 4 (E Plan) PM 4.2 pg.1 of 6 ANSWER (B.11) c REFERENCE Chapter 4 (E Plan) PM 4.6 pg.1 of 1 l
ANSWER (B.12) b REFERENCE Chapter 4 (E Plan) PM 4.5 pg. 6 of 11 ANSWER (B.13) b, d REFERENCE PM 4.4.4.15 pg. 8 of 17 ANSWER (B.14) c REFERENCE AOP PM 5.6.3 ANSWER (B.15) d REFERENCE SOP PM 2.3.1 ANSWER (B.16) e REFERENCE MIT PM 2.5, Section 2.5.2(2), p 2.
ANSWER (B.17) b, d REFERhi4CE PM 3.3.1.1, Step 39, p 3.
ANSWER (B.18) d REFERENCE T.S. 3.10
u 6
0 l
l wtan B: Normal /Emera. Praradures & Rad con
- Page 11 ANSWER (B.19) l b
l.
REFERENCE T.S. 3.4 RSM 3.4-(3.2.5)
ANSWER (B.20).
c
-REFERENCE T.S. 6.1 -
PM 1.14.2 l
i 1
"*" END OF EXAMINATION '""
I l
-