IR 05000193/1987001
| ML20237C654 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 12/14/1987 |
| From: | Keller R, Norris B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20237C638 | List: |
| References | |
| 50-193-87-01OL, 50-193-87-1OL, NUDOCS 8712220055 | |
| Download: ML20237C654 (55) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO.
50-193/87-01(0L)
FACILITY DOCKET NO.
50-193 FACILITY LICENSE NO.
R-95 LICENSEE:
Rhode Island Atomic Energy Commission Narrangansett, Rhode Island FACILITY:
Rhode Island Nuclear Science Center EXAMINATION DATES:
October 20-21, 1987 CHIEF EXAMINER *
b 4:?/ P77
~
t tiarry ^.'Norris
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Date '
Senio perations Engineer APPROVED BY:
ll.//Md7 Robert M. KelTer,~0'hief Date Pressurized Water Reactor Section Operations Branch, Division of Reactor Safety SUMMARY: Written and operating examinations were administer ed to one Senior Reactor Operator (SRO). One SRO license was issued.
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REPORT DETAILS TYPE OF EXAMINATIONS:
Replacement EXAMINATION RESULTS:
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1/0 l
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l EXAMINER'AT SITE:
R. G. Clark (PNL)
1.
There was only one candidate; therefore, no generic weaknesses or strengths could be identified.
2.
The written examination was reviewed by the facility after the candidate had completed the examination. Comments were submitted to the Region I office.
The facility comments and the NRC resolution are enclosed as Attachment 2.
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Attachments:
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1.
SRO Written Examination and Answer Key
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2.
Facility Comments on Written Examination and NRC Resolution l
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U. $. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
RHODE ISLAND & PROV. P AEC
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REACTOR TYPE:
TEST
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DATE ADMINISTERED: 87/10/20 EXAMINER:
CLARK, R.
CANDIDATE:
ANSWER KEY INSTRUCTIONS TO CANDIDATE:
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 passing 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 VALUE TOTAL SCORE VALUE CATEGORY 20.00 20.00 H.
REACTOR THEORY 20.00 20.00 I.
RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS 20.00 20.00~
J.
SPECIFIC OPERATING CHARACTERISTICS 20.00 20.00 K.
FUEL HANDLING AND CORE PARAMETERS 20.00 20.00 L.
ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS 100.00
%
Totals final Grade All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature
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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 black ink or dark pencil only 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.
Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
8.
Consecutively number each answer sheet, write "End of Category
" as appropriate, start each category on a new page, write only on oiie side of the paper, and write "Last Page" on the last answer sheet.
9.
Number each enswer as to category and number, for example,1.4, 6.3.
10. Skip at least three lines between each answer.
11. Separate answer sheets from pad and place finished answer sheets face dova on your desk or table.
12. Use abbreviations only if they are commonly used in facility 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.
'5. 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 examiner 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.
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l 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, i
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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PAGE
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H.
REACTOR-THEORY
. QUESTION H.01 (1.00)
IF the initial neutron flux in a reactor was 10 neutron cm**-2 sec**-1-and if the reactor was on a 30-second, constant, positive period, WHAT would the flux be after 90 seconds?
SHOW your work.
(1.0)
QUESTION H.02 (2.00)
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Fuel Core Distribution k
Across Core Reflector At Startup
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a.
Use the above figure to show the fuel distribution at end of fuel load life.
(0.5)
b.
On this same figure, DRAW the thermal neutron flux distributions (radial variations) for this fuel load-for both the start and end-of-life conditions.
(1.5)
QUESTION H.03 (1.50)
When operating the RINSC reactor at 1.0 MW, IDENTIFY the modes of
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heat transfer by which heat is removed from the fuel.
INCLUDE the major components in the heat removal process starting with l
the fuel and ending at the ultimate heat sink.
(1.5)
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(***** CATEGORY H CONTINUED ON NEXT PAGE *****)
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L H.
REACTOR THEORY PAGE
QUESTION H.04 (1.00)
Under steady-state operation, WHAT would be the difference between the control rod positions at 100 kW and 1000 kW7 EXPLAIN.
(1.0)
QUESTION H.05 (1.00)
Assume a uniform distribution of fuel exists in the reactor during operation at 1 MW with a unifonn coolant flow through thereactor(noblockage). EXPLAIN WHAT could cause a fuel
. hot spot to develop.
(1.0)
QUESTION H.06 (1.00)
ANSWER TRUE or FALSE.
a.
-The Doppler effect in the RINSC reactor is due to the broadening of the resonance absorption cross-section peaks for Xe and other fission fragments.
(0.5)
b.
For a reactor, the effective multiplication factor k-eff equals k-in#inity times P, where P is the total nonleakage probability.
(0.5)
QUESTION H.07 (2.00)
WHY is the pool temperature coefficient negative in the RINSC reactor.
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(2.0)
QUESTION H.08 (2.00)
DESCRIBE HOW and WHY the power level will change during the first 5 minutes into a scram ending an operating period of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 2 MW.
(2.0)
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(***** CATEGORY H CONTINilED ON NEXT PAGE *****)
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THEORY REACTOR l
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H.
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reactor
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reactivity to a t best (3.00)
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with a descriptor thaeach of three y
H.09 of positive QUESTION ulation for Considersource small additionCOMPLETE the table bes low addition.
TH a
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ASSUME a of the (3.0)
occurs.
of K.eff that resuof K-eff with N0 sour description describes the values best each value associated with theeach case.
in place.
opulation in SELECT the letterensuing neutron p
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Neutron Population
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increases linearly equilibriumexponentially is in
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increasesdecreases linearlyexponentially With Source
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c.
d.
decreases Present No Source
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e.
Present
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K.eff
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<1
1
>1
if (1.00)
suberitical reactorand
f rom 100 cps to 150 cps a
added to H.10 QUESTION s been HOW much reactivity ha ed count rate has increasof k-eff was 0.957 the initial value operations 7 (200)
routine QUESTION reactivity needed for H.11 excess four (4) reasons.
WHY is GIVE pppp
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H.
REACTOR THEORY PAGE
QUESTION H.12 (1.50)
If B-eff'for the RINSC reactor was reduced from the actual
.0.077% to 0.055%,.HOW and WHY would the reactor respond to a small addition of positive reactivity.
(1.5)
QUESTION H.13 (1.00)
DISCUSS the production and removal process for Xe in the reactor.
(1.0)
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RADI0 ACTIVE MATERIALS' HANDLING DISPOSAL AND HAZARDS PAGE
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- QUESTION' I.01
.(2.00)
'According to the Radiation Safety Guide and the Technical Specification, IDENTIFY the individual primarily responsible, for each of.the following:
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a.
Who has the primary responsibility for radiation safety
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at the Rhode-Island Nuclear Science Center?
(0.5)
b.
During routine reactor operation, who on shift is responsible for all activities involving radiation hazards?
(0.5)
c..
Who is responsible for ensuring that radiation surveys
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in the vicinity of radioactive sources and the reactor are accomplished?
(0.5).
d.
Who is responsible for management of the waste disposal service?
(0.5)
l QUESTION I.02 (1.50)
According to the Radiation Safety Guide:
a.
STATEthelimitations(s).ondisposingofradioactivewaste by incineration or burial.
(0.5)
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b..
STATE the method (s) to be used to dispose of radioactive liquid. wastes.
(1.0)
QUESTION I.03 (1.00)
i DEFINE the following terms a.
Transport Index (0,5)
b.
Biological Half-life (0.5)
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RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE
i (2.00)-
QUESTION I.04'
In each instance below, GIVE the external radiation exposure level-to a major portion of the body that is associated with defining or that is limiting in each of these four areas.
.a.
radiation zone (0.5)
b.
the contributing dose rate in an unrestricted area from a radioactive source in an adjacent (adjoining) permanent storage area (0.5)_
c.
high radiation zone.
(0.5)
d.
unrestricted area (0.5)
QUESTION I.05 (1.50)
A radiation source emits 0.9 HeV gamma protons and produces a reading of 10 rad /hr on a detector which is 3 feet away. WHAT thickness of lead shielding will be required to reduce _ the reading to 5 mrad /hr at that point?
[ ASSUME tenth value layer (TYL) for lead equals 1 inch.]
(1.5)
QUESTION I.06 (1.00)
According to the Radiation Safety. Guide, in an event where an injured person is contaminated, WHAT should be done prior to loading and subsequent transportation in the ambulance to the hospital?
(NAME two (2) steps.)
(1.0)
QUESTION I.07 (2.00)
EXPLAIN HOW and WHY the determination of dose rates from a point source may not be valid in the following a.
.for distances that are relatively close to the source.
(1.0)
b.
for distances that are especially far from the source.
(1.0)
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RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE
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QUESTION I.08 (3.00)
Assume the reactor is operating at 1 MW. WHAT would an alarm,
on each of the fixed gamma monitors indicate? Consider the condition at each monitor as an. independent event (unrelated).
(3.0)
a QUESTION I.09 (1.00)
Briefly explain WHY the constant '(1.8 x 10**-12 delta C/t) used during emergencies to establish-limits on air particulate at ground level is LOWER than the constant (2.6 x 10**-12 delta C/t)
used during normal conditions.
(1.0)
QUESTION I.10 (2.00)
From 10CFR20, WHAT are the maximum allowable exposure limits (whole body, extremities, and skin) for a radiation worker who has an NRC Form 4 on file.:
(2.0)
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QUESTION I.11 (1.50)
ESTIMATE the dose rate 5 feet from a small aluminum vial con-taining about one-third (1/3) curie of Co-60.
Express your answer both in mrad /hr and mrem /hr. Co-60 emits two gammas of 1.37 MeV and-1.19 MeV.
You may ASSUME a reasonable single average energy MeV gamma from this source for this question. SHOW your work.
(1.5)
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I. ' RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS'
PAGE
QUESTION I.12 (1.50)
SELECT from the decay modes listed below, the closest to that,of EACH of the following (1.5)
a.
AR-41 Half Life Decay Mode
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1.
1.8 hr
- beta decay /no gama 2.
1.8 hr
- beta decay /1-2 MeV gamma 3.
7.3 sec
+ beta decay /608 MeV gama 4.
21.7 min
- beta decay /no gama b.
N-16 1.
7.3 hr alpha decay /no gamma 2.
7.3 hr
- beta decay /1-2 MeV gamma 3.
7.3 see
- beta decay /6-8 MeV gamma 4.
7.3 min
+ beta decay />-6 MeV gamma c.
Na-24 1.
15 min
- beta decay /no gamma 2.
15 hr no beta decay /1-3 MeV gama 3.
15 hr
- beta decay /no gamma 4.
15 sec
- beta decay /1-3 MeV gamma
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SPECIFIC OPERATING CHARACTERISTICS PAGE 10 QUESTION J.01 (2.50)
a.
NAME the reactor safety system protective functions which are bypassed when the Power Level Selector Switch is in the 0.1.MW sosition.
INDICATE:those bypassed functions that would 1 ave provided trip signals.
(2.25)
b.
WHAT would be the effect of switching the Power Level Switch to the 5 MW position inadvertently during a reactor startup?
(0.25)
QUESTION J.02 (2.00)
WHAT functions should occur automatically if_the evacuation l
button is depressed? GIVE four (4).
(2.0)
QUESTION J.03 (3.00)
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WHAT three (3) automatic actions will occur if normal electrical power is lost when the reactor is at 500 kW7 (1.5)
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. HAT electrical loads should be automatically energized b.
W following a loss of normal power 7 (1.5)
QUESTION J.04 (2.00)
Assuming the reactor is operating at 95% power, INDICATE for each of the following situations whether the reactor should be SCRAMMED, SHUT DOWN, REDUCED IN POWER, or could be MAINTAINED AT POWER.
Consider each situation separately.
(2.0)
a.-
Reactor power drops unexpectedly to 92%.
b.
Reactor power increases to 96% as the pool water inlet temperature increases to 110 degrees F.
c.
The alarm for the high neutron flux on one of the compensated ion chamber safety channels becomes inoperable due to a faulty relay.
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The temperature of the coolant leaving the core during forced convection cooling reaches 120 degrees F.
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SPECIFIC OPERATING CHARACTERISTICS PAGE 11 QUESTION J.05 (2.50)'
Refer to the accompanying figure depicting the power history of the RINSC' reactor for 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br />. Assume the RINSC reactor has been shut down for a week prior to this operation. On the same
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figure and time scale DRAW the resulting xenon reactivity curve.
-(2.5)
QUESTION J.06 (2.50)
,
IDENTIFY key changes to the reactor X the secondary circulating pump fails while the reactor is at 100% power with all rods in manual control. Assume that systems operate normally and no operator action is taken.
(2.5)
i QUESTION J.07 (2.00)
Given the reactor parameters below, DETERMINE the reactor power in MW.
(2.0)
Inlet: temp primary coolant:
108 degrees F Outlet temp primary coolant:
117 degrees F Flow rate primary coolant:
1500 gpm.
QUESTION J.08 (1.50)
i ANSWER TRUE or FALSE.
!
a.
Inverting an irradiated fuel element would have no effect on core reactivity or differential control rod worth.
(0.5)
b.
Evacuating the aluminum cladding on the graphite reflector logs enhances heat transfer to the pool water.
(0.5)
c.
The volume of water transferred from the pool into the primary is controlled primarily by flow paths in the control blade shrouds.
(0.5)
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SPECIFIC OPERATING CHARACTERISTICS PAGE 12 QUESTION J.09 (1.00)
EXPLAIN the design feature of the coolant circulation system in the core that minimizes the radiation level at pool surface from N-16.
(1.0)
QUESTION J.10 (1.00)
ANSWER TRUE cr FALSE.
a.
The RINSC fully reflected reactor will not' go critical even if the entire 7 x 9 grid of the core were filled with fuel elements.
(0.5)
b.
Full flow through the fuel elements will probably not-be turbulent at lower temperatures.
(0.5)
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FUEL HANDLING AND CORE PARAMETERS PAGE 13
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-QUESTION K.01 (1.50)
a.
Briefly DESCRIBE a procedure necessary to obtain an on-scale reading on-the linear level safety channel compensated ion
]
chamber during an initial core loading.
(1.0)
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b.
HOW many vacant' fuel element positions within the periphery of the active section of the core can exist in a fully loaded core?-
(0.5)
QUESTION K.02 (2.50)
The initial count rate for a RINSC reactor core with fuel elements and source installed is ten (10) counts per second.
For the following loading sequence and corresponding count rates, PREDICT the number of fuel elements for a critical loading.
(USE the attached graph paper for a 1/H plot.)
LABEL the axis. SHOW your work.
(2.5)
No. Fuel Count Elements Rate, cps
........
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13
17
25
50 QUESTION K.03 (1.50)
a.
GIVE the maximum total RESIDUAL reactivity permitted in the core during core loading.
(0.5)
b.
HOW is this level of reactivity assured?
(1.0)
QUESTION. K.04 (1.00)
When loading for CRITICAL EXPERIMENTS,
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a.
WHAT should be the status of the core cooling system?
(0.5)
b.
WHAT is the minimum water level in the pool?
(0.5)
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' FUEL HANDLING AND CORE PARAMETERS PAGE 14 QUESTION K.05'
.(2.25)
In accordance with Rhode Island Operating Proceedures, FILL in the following blanks regarding required reactivity values.
,
a.
The shut-down margin required for. movement of any fuel is-(0.75)
.
b.
MANUAL changes-in experimental equipment which can affect reactivity by more than prior to the move-ment _of the equipment require a shut-down margin of (1.5)
.
QUESTION K.06 (2.00)
WHAT four (4) systems and/or instrumentation must be operable prior to preparing and shipping of spent fuel elements to reprocessing?-
(2.0)
QUESTION' K.07 (1.25)
STATE two (2) reasons why white cottca gloves are to be worn when handling the plates of new fuel elements.
(1.25)
QUESTION K.08 (2.00)
HOW is inadvertent criticality prevented during irradiated'
fuel handling and storing? GIVE four (4) means.
(2.0)
QUESTION K.09 (3.00)
STATE four (4) of the limitations that exist on the experiments conducted at the RINSC reactor.
(3.0)
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FUEL HANDLING AND CORE PARAMETERS PAGE 15
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QUESTION X.10 (1.50)
ANSWER TRUE or FALSE regarding reactivity limitations or core conditions, a.
For any core in the reactor, the cold clean excess reactivity shall not exceed 0.047.
(0.5)
b.
All reactor cores used shall be such that they must be subcritical by at least 1% with the least reactive element withdrawn.
(0.5)
c.
Pool water temperature shall not exceed 150 degrees F.
(0.5)
QUESTION K.11 (1.50)
WHAT are the consequences to a fuel loading procedure if the detector is too close to a neutron source.
(1.5)
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(*****ENDOFCATEGORYK
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L.- ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS, PAGE' 16
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QUESTION L.01 (3.00)
FILL in the blanks in the following statements with the proper term (according to the Operating Procedures) selected from the listing i
below.
)
J
... Director
'
Assistant. Director
Senior Reactor Operator Reactor Operator a.
The
, under the is responsible for the operation.of the reactor according to the approved operating procedures.
(1.0)
i b.
For.a given shift, the is designated by and reports directly to the (1.0)
{
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c.
The or the is authorized to make minor changes to the operating procedures.
(1.0)
QUESTION L.02 (1.25)
ANSWER TRUE or FALSE if each of the following ABNORMAL conditions requires a reactor shut down or a reactor scram.
Consider each independently.
(1.25)
1.
regulating blade sticks 2.
high magnet current reading, > 430 ma 3.
stack monitor reading low 4.
startup counter sticks 5.
high conductivity alarm on delay tank QUESTION L.03 (2.00)
According to tne Operating Procedures, the SRO has several post-scram responsibilities and options. NAMEfour(4).
(2.0)
t
.
(***** CATEGORY L CONTINUED ON NEXT PAGE *****)
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_ - _ _ _ _
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_ - _____- ____ -_-_
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L i
L.
ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 17
-
l QUESTION L.04 (2.25)
a.
An ex)erimenter calls to say contents of an irradiated vial las leaked onto him. WHAT basic immediate action should be taken.
NAME two (2).
(1.5)
b.
HOW would the reactions be different if the radiation monitor at the rabbit receiving station alarmed.
(0.75)
QUESTION L.05 (2.00)
Assume you are emergency coordinator. WHAT two (2) conditions must exist for you to authorize re-entry into a radiation area?
(2.0)
QUESTION L.06 (1.50)
According to the RINSC Technical Specifications, at WHAT three (3)
times is the SR0 required to be at the facility?
(1.5)
i QUESTION L.07 (3.00)
a.
HOW is the facility notified of an off-normal condition after working hours?
(1.0)
b.
SPECIFY four (4) off-normal conditions that should trigger this notification.
(2.0)
QUESTION L.08 (1.00)
Assume two (2) Remote Area Monitors are alarming and you are the i
SRO on shift. WHAT is your response assuming no other procedures
have been initiated? GIVE two (2).
(1.0)
1
,
e (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
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ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 18
'
QUESTION L.09 (1.50)
ANSWER TRUE or FALSE relative to emergencies at RINSC.
4-a.
The Emergenc3 Coordinator has the authority to initiate recovery operations.
(0.75)
b.
The Emergency Coordinator must have the concurrence of the Emergency Director to terminate an emergency classification.
(0.75)
QUESTION L.10 (2.50)
'
You are on shift SRO at 2 a.m. and the operator receives a phone call of a bomb threat, WHAT five (5) actions must be taken?
(2.5)
'
,
.
(*****
END OF CATEGORY L
- )
,...............-er ev.........n.,
...............s
- - _ - - - - - - - - - - - - - - - _. - _ _... _ _. -
_
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_
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.
..
'#
~ H.
REACTOR THEORY PAGE 19
-
ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
t ANSWER-H.01 (1.00)
,
,
t i
N = (10) (e 90 sec/30 sec) = (10) (e**3)
[+0.5]
'
.AND N = (10) (20.1) = 201 N cm**-2 sec**-1
[+0.5]
REFERENCE i
1.
'Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, p. 112.
ANSWER H.02 (2.00)
_
"
[N
]
'N j Distribution N
C Startup Fuel
/
'
Distribution End
--
At Startup
!
l
- +1.0; if neutron flux at end is greater than at startup j
_ 0.5. for shape of curves relative to fuel distribution
!
+
REFERENCE 1.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, pp. 197-199.
.
___ - _ _ _
- _ - _ -
,
..;
..
.
~~
H.
REACTOR THEORY-PAGE 20
-
ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
. ANSWER H.03 (1.50)-
.
conduction through the fuel conduction through the cladding
.
natural convection away from core to ultimate heat sink (pool)
A ~ '" # " ' ' ' "" ' "
"' ' ' ' ' ' ' ' "
' " ' " ' ' ' ~
""'Y ?"'# ]
[+0.5] each J' < n. d n) lo::] n ) e r k" Q- [ o..c ~]
- cor e o REFERENCE-1.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 4.
ANSWER H.04 (1.00)
i No difference [+0.4] because the reactor is below the power level at which the power coefficient begins adding negative reactivity
-[+0.6].
REFERENCE 1.
Rhode Island: Safeguards Report, 1962, p. 44.
, ANSWER H.05 (1.00)
,
a peaking of neutron flux [+0.75] which could result from a partially dropped control rod [+0.25]
--0R--
a faulty experimental rig near fuel which moves to make a positive reactivity change [+0.25], etc.
[+1.0] maximum i
REFERENCE 1.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 4, p. 87.
l j
!
.
i
- - _ _ - _ _ _ - _ - _ _ _
- _.
(
.
_ _ _ _ _ _ _ _ _ _
'. *
,
.
..
-
H.
REACTOR THEORY PAGE 21 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
ANSWER H.06 (1.00)
a.
False (the Doppler effect is provided by U-238 atoms primarily)
[+0.5]
b.
True [+0.5]
REFERENCE 1.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, p. 190 2.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, p. 73.
ANSWER H.07 (2.00)
As pool water temperature increases, the water becomes less dense (reducing the atom density of hydrogen H2/cc) [+0.5].
This results in less thermalization (and ;;he neutron spectrum hardens) [+0.5].
Neutron leakage thus increases [+0.5], thereby reducing net reactivity [+0.5].
REFERENCE 1.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 2.
i ANSWER H.08 (2.00)
Due to a loss of prompt neutrons E+0.5] an immediate substantial (>85%) drop in power occurs [+0.5?. After the initial drop the power level will continue to drop with a -80 second period [+0.5]
due to the effects of delayed neutrons [+0.5].
REFERENCE 1.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, p. 131.
-
- _ _ _ _ _ _ _ _
-__ _ _ _ _ _ - _ - _ _ _ _ _ - _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _. _ _ - _ _
_
. _ _
_,..
ld
- *, a
' '
H.-
REACTOR THEORY PAGE 22
'
ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
'
ANSWER H.09 (3.00)
No Source With Source K-eff Present-Present
........
.........
...........
1.
<1 e.
b.
2.
b.
a.
3.
>1 c.
c.
[+0.5] each REFERENCE-1.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, pp. 81 and 82.
ANSWER H.10 (1.00)
CR1/CR2 = [1 - (k2)]/[1 - (k1)]
i 100/150 = - (1 - k2/(1 - 0.95)
k2 = 0.967
[+0. 5)
Change in reactivity = (1 - k1)/k1 - (1 - k2)/k2
= k2 - k1/k2 x kl
= 1.8%
[+0.5)
REFERENCE 1.
Rhode Island: Equation Sheet.
2.
Rhode Island: Reactor Operator Study Handbook, ORNL-TH-2034, Vol. 3, p. 134.
.
I
!
_
_ __
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
__
- _.
.-_ ____ _
_ _ - _ _ _ - - _
_ _ _ _ _
_
_ _ _ _ - _ _ - _ - _ _ _ _ _ _ _
_ _ _ _ _ _ _ - _ -
,. '..
..
,
' ~
'H.
REACTOR THEORY PAGE 23
. ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
ANSWER H.11 (2.00).
.
1.
to overcome negative power coefficients 2.
'to overcome neutron losses (poisons / leakage)
3.
to give operating flexibility rate; (i.e., permit power increases at a reasonable rate)
4.
to_ compensate for fuel burn-up 5.
to accommodate negative reactivity of experiments Any four (4) -[40.5] each, +2.0 maximum.
REFERENCE 1.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, pp. 55 and 56.
ANSWER H.12 (1.50)
The reactor would respond faster [+0.5], because of the shorter average neutron lifetimes
[+1.0].
REFERENCE 1.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, pp. 134-136.
.
- _ _ _ _ _ -. - - _ - - - _ - ~ _ _ _. _ _ _ - - _ _ - - -
- - _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
_ _ _ _ _ _ _ _
_
_
_
.
...
.
'
,H.
REACTOR THEORY PAGE 24 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
ANSWER H.13 (1.00)
Production xenon is produced as a direct fission product during operation
[+0.25)
xenon is produced from the decay of another fission product I-135 (5.6f; of all fission products) generated during reactor
'
operation [+0.25]
Removalxenon-135 is removed by absorption of thermal neutrons [+0.25]
xenon-135 is removed by its own radioactive decay [+0.25)
REFERENCE 1.
NUS, Vol. 3, p. 10, 2-1.
.
A
_ _. _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ __
__
_
_ _ _ _ _ _ _ -
- _ - _ _ _ _ _ _ _
e.
F
' ' ~
I..
RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 25 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
ANSWER I.01 (2.00)
.
a.
theindividual(s)-utilizing. radiation b.
the SRO on duty c.
theRadiationSafetyOfficer(R50)
d.
the Radiation Safety Officer (R50)
[+0.5]each REFERENCE 1.
Rhode Island: Radiation Safety Guide,Section I, paragraph 3.C, parts a.,
c., and d, p. 4.
2.
Rhode Island: Technical Specifications, Section J, paragraph 3, part b, p. 20.
ANSWER I.02 (1.50)
a.
Under N0 circumstances shall materials be disposed of by burial or by incineration.
[+0.5]
b.
Use approved drains and the laboratory sink system.
[+0.5]
Convert to solid and release to waste disposal contractor.
[+0.5]
REFERENCE 1.
Rhode Island: Radiation Safety Guide,Section IV, p. 17.
2.
Rhode Island: Radiation Safety Guide, Sections C1 and C2, pp. 18 and 19.
- l
-
..
_. __
_
,
.
..,
.
' ' '
I.
RADI0 ACTIVE MATERIALS HANDLING DISPOSAL'AND HAZAR_D_S PAGE 26 S
ANSWERS -- RH00E ISLAND & PROV. P AEC-87/10/20-CLARK,. R.
ANSWER I.03 (1.00)
.a.
dose in mrem /hr [+0.25] at 3 ft [+0.25]
b.
time required for 1/2 of an isotope to be removed from critical organ (body is acceptable) [+0.25] by biological processes [+0.25]
REFERENCE 1.
Rhode Island: Radiation Safety Guide, Opening Statements, paragraph 2, p. 14.
2.
Rhode Island: Radiation Safety Guide, Appendix F, Table 1.
ANSWER I.04 (2.00)
a.
more than 5 millirems /hr b.
0.5 millirems /hr c.
more than 100 millirems /hr d.
less than 2 millirems /hr
[+0.5] each REFERENCE 1.
Rhode Island: Radiation Safety Guide,Section V, paragraph C.2.a, p. 30.
2.
Rhode Island: Radiation Safety Guide,Section III, paragraph D.I.a, p. 16.
3.
Rhode Island: Radiation Safety Guide,Section V,
{
paragraph C.2.b, p. 30.
i
-
- _ _ _ - _. - _ _ _ - _ _ _
l
-
3......
- ~
I.
RADIOACTIVE-MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 27 ANSWERS -- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
!
ANSWER.
I.05 (1.50)
I 10 rad /hr x 1/10 x 1/10 x 1/10 = 10 mrad /hr [+0.5]
half value layer = 0.3 x TVL = 0.3 inch
[+0.5]
!
Therefore 3.3 inches of lead required [+0.5]
l REFERENCE 1.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, 1968, Volume 2, p. 108.
ANSWER I.06 (1.00)
1.
' DECONTAMINATE ANY VICTIM as thoroughly as possible [+0.5]
2.
ContaminatedCLOTHINGSHOULDBEREMOVEDIFPOSSIBLE[+0.5]
d4 M '"
"'""
"' " " " " 6 b## 3 REFERENCE 1.
Rhode Island: Radiation Safety Guide, 1954,Section VIII.A, p. 41.
ANSWER I.07 (2.00)
a.
The calculated dose rate may be LOWER [+0.5] than the actual dose rate when close to the source because the source will show characteristics of a plane source rather than a point source [+0.5].
b.
The calculated dose rate may be HIGHER [+0.5] than actual dose rate when far from the source because the inverse square law does not include a factor for attenuation by air [+0.5].
REFERENCE 1.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Volume 2, pp. 123-127.
.
______._.m._._._-_.._.__.________m_____
. _ _ _
_ _ -
.__
_
_
____.m _ _ _ - _ _ - _ _ - _
_ _ _ _ - _ _ _ _ _ _ _ _ _ _ - - _ _ - _ = - - - -.
- _ _ - _ _ _ - - _ _ _ _ _ - _.
. - _ _.
_,
'*
..
..
i
.
- *
I.
RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 28 ANSWERS'-- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
)
.
ANSWER I.08 (3.00)
L 1.
At the bridge monitor [+0.5], radioactivity in the pool (such as N-16, leaking fuel elements or experiments, radioactive
crud, etc.) has developed and exceeds the technical i
specification of < 10 mrem /hr at 1 meter above the surface.
[+0.5]
,
2.
At the biological shield between beam port and thermal column l'
[+0.5], protection of personnel is inadequate from plugs, shutters, and doors not in place [+0.5].
3.
Above storage container for new fuel elements [+0.5], elements are not in place and may be in a critical array [+0.5].
REFERENCE 1.
Rhode Island: Technical Specifications, Section IC, paragraph 3, p. 26.
2.
Rhode Island: Safe Guards Report, p. 38.
ANSWER I.09 (1.00)
The sampling point for normal operation is stack air sampling point in horizontal duct inside the EPZ [+0.5].
The sampling point during emergencies is un stack DOWNSTREAM of air clean-up system
[+0.5] (of absolute t.nd charcoal filters with the assumption made that the filters are effective).
Op r, ea n /)ps esor12. ().o 0)
A ' ' " ' T' "' ' ' ' ' ' "
W
,)
REFERENCE
[p g,
,,. m,, g,,,,
.,,
.
,,
1.
Rhode Island: Emergency Plan, Appendix 2.1.
con m e d,
ANSWER I.10 (2.00)
Whole Body: 3 rem / quarter [+0.5], not to exceed 5 (N-18) [+0.5]
where N = workers age Extremities:
18.7 rem / quarter- [+0.5]
Skin: 7-1/2 rem / quarter [+0.5]
)
)
.
_ _. -. - - - -. - _ _ - _ _
_ _. - -. - - - _ -
-
\\
- - _
_ _ _ _ _ _ _ _.
.
...
,
' '
I.
RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 29 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
.
REFERENCE 1.
Rhode Island: Radiation Safety Guide, Appendix C.
-
\\
ANSWER I.11 (1.50)
Dose in R/hr at 1 ft = 6 CE Dose in R/hr at i ft = 6 (1/3) ti-2ft (acceptable value for 5 /2 gamma energy 1.25 +/-
a
= tift R/h at 1 ft 0.05 Mev)
{
[+0.5]
-
Dose in R/hr at 5 ft - D/2.5 (distance)**2 5, / 2-cc /2I t te n a
= t d R/hr/25
=NR/hr [+0.5]
=hhmR/hr zoo
= 40& mrem /hr [+0.5]
REFERENCE 1.
Rhode Island: Reference Sheet, Radiation Safety Guide, Appendix E, paragraph B.1.
2.
Rhode Island: ORNL-TM-2034, Vol. 2, p. 58.
ANSWER I.12 (1.50)
I a.
b.
c.
[+0.5] each REFERENCE 1.
Rhode Island: Radiation Safety Guide, Appendix F, Table 1.
2.
Rhode Island: Safeguards Report, p. 52.
- - _ - __-_-- -______ _ ____-__________________-___.---_______.-____ ______._ ______._.-----_-_.-__.-___.______.._--_________-_-__ _ - --
- _ - _ _ - _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _
_ - _ _
.;..
J.
SPECIFIC OPERATING CHARACTERISTICS PAGE 30
ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
ANSWER J.01 (2.50)
.
a.
Hi Temp - Primary Coolant Entering Core [+0.25]
Hi Temp -] Primary Coolant Leaving Core [+0.25] - Reactor Trip
[+0.25 Primary Coolant Low Flow Rate [+0.25] - Reactor Trip [+0.25]
Bridge Misalignment [+0.25] - Reactor Trip [+0.25]
Coolant Gates Open [+0.25] - Reactor Trip [+0.25]-
b.
the reactor scrams
[+0.25]
REFERENCE l
1.
Rhode Island: Reactor Technical Specifications, Table F.1, p. 12.
l ANSWER J.02 (2.00)
1.
the evacuation horn blows 2.
the air conditioning and normal ventilation (fans) turn off 3.
the dampers on all ventilating ducts leading to the outside close l
4.
the building cleanup system air scrubber and fresh air blower l
comes on l
J 5.
Off Gas Blower and Rabbit System Blower have shut off
'
[
Any.four (4) [+0.5] each, +2.0 maximum.
l REFERENCE 1.
Rhode Island: Technical Specifications, K.3.b.(2), p. 24.
2.
Rhode Island: Operating Procedures, p. 10.1.
i
.
I
-
-__ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
.,.
J.
SPECIFIC OPERATING CHARACTERISTICS PAGE 31
..
ANSWERS -- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
ANSWER J.03 (3.00)
a.
reactor scrams [+0.5]
propane gas generator unit starts
[+0.5]
automatic transfer switch operates
[+0.5]
- '
f#' 'O m[r nc'y 11ghts
' 0. 5'
Sv r4 e /"o b.
+
b'd.
auxi$iaryblower
' 0. 5'
M d d d '3
- N '2-btri4 ding cleanup is be/ f*0$J
/e c'"'c b e e /"" ' 2 '" "^ '" c e
+
/ tX (o r 19/t tf) tw To t/H F f > &0 REFERENCE h" ' '3 "'" ' T Jo k e'
0"""
D 0 1.
Rhode Island: Operating Procedures 10.lc,d, 10.2a.b, 10.3, pp. 10-1 and 10-2.
ANSWER J.04 (2.00)
a.
shut down b.
maintainedpower(CAF)
c.
maintained at power d.
maintained at power
[+0.5] each REFERENCE 1.
Rhode Island: Operating Procedures, 8.2, p. 8-2.
2.
Rhode Island: Technical Specifications, p. 12.
.
--- - - _ - _ - - ~ _ _ _ _ _ _ _ _ _ _ _ _.. _ _ _ _ _ _ _ _, _ _ _ _ _ _ _ __ _ _
__
____
_ _
_
_ - _ _ ___ _ _
_ _ -.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _.
. _ - _ _ _ _ _ _ _ - _.
_ _ - - _ _ _.
.. :
.,
'~
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SPECIFIC OPERATING CHARACTERISTICS PAGE 32 ANSWERS -- RHODE ISLAND &~PROV. P AEC-87/10/20-CLARK, R.
ANSWER J.05 (2.50)
/cd bwett LEytt-O
,
.
SM /PE fD 5)
fnw/UIJ
,
/]m:.t - /Sg r /]s n l' f t p r L - D e u o, /2py - Lew a
'
f- 0
-
4~
.,j
.
..
(O*S
'
'
,
q femN r
- '^%
7;,, a v
,.
(
i-
,
r, ( 0' 5 }
~~
\\
eni >> er
. hWM'Y nyalp (0,y )
'
y
!
s rga 3:
co.:)
r
f Q,$^~
O AS
JS
/to
/25 (s o
/Gise -
/ (25 REFERENCE 1.
Rhode Island: Reactor,0perator Study Handbook, ORNL-TM-2034, J
_ - _ - _ _ _ - _ _ _ _ _ _ _. _ _ _ - _ - _ _ _ _ _ _ _ _ -
_ _ _ _ _ _ - _ - _ - _ - _ _ _ _
_-
[.:..
.
'
'J. SPECIFIC OPERATING CHARACTERISTICS PAGE 33
-
ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
Vol. 3, Reactor Physics, pp. 165 through 169.
l ANSWER J.06'
(2.50)
'
Pool inlet temperature increase raising pool temperature [+0.5] adding negative reactivity [+0.5].
Primary coolant inlet temperature goes up, alarm set point reached [+0.5].
Primary coolant exit temperature goes up to alarm pt [+0.5].and then reactor scram set point [+0.5].-
REFERENCE 1.
Rhode Island: Technical Specification, p.12, Table F-1.
2.
Rhode Island: Safeguards Report for Rhode Island Open Pool Reactor, paragraph 2.2.3, p. 26.
ANSWER J.07 (2.00).
h=mCp(deltaT)
[+0.5]
m = 1500 gpm x 8.345 lb/ gal x 60 min /hr [+0.25]
Cp = 1 BTU /lb-degree F [+0.25]
delta T = 9 degrees F [+0.25]
Thenh=6.76x10**6 BTU /hr [+0.25]
6.76 x 10**6 BTV/hr
.
Q
............----------
[+0.25]
3.41 x 10**6 BTU /hr/MW h=1.98MW [+0.25]
REFERENCE 1.
Rhode Island: Safeguards Report, 1962, 3.2.2, p. 53.
2.
Rhode Island: Operating Procedures, 1984, 8.1.2, p. 8-1.
3.
Rhode' Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 4, p. 14.
4.
Rhode Island: Reactor 0perator Study Handbook, ORNL-TM-2034,
,
_.-__.__._____________o
- --
.- (*...
,
~'*J.
SPECIFIC OPERATING CHARACTERISTICS PAGE 34
-
ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
Vol. 4, p. 64.
I ANSWER J.08 (1.50)
-
a.
False (control rod worth could change)
b.
True c.
False (controlled by cleanup loop pump)
[+0.5] 'each REFERENCE 1.
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, pp. 197 through 202.
l 2.
Rhode Island: Safeguards Report for the Rhode Island Open Pool
'
Reactor, Section 2,. paragraph 2.1.3, p. 7.
I 3.
Rhode Island: Safeguards Report.for the Rhode Island Open Pool Reactor, Section 2, paragraph 2.2.2, p. 19.
_
ANSWER J.09 (1.00)
Forced coolant flow containing N-16 returning to the core is directed downward so that only by diffusion around the core cover plates can any of-this water reach the pool surface to contribute to the dose rate at the surface.
[+1.0]
REFERENCE 1.
Rhode Island: Safeguards Report, paragraph 3.1.1c, p. 52.
ANSWER-J.10 (1.00)
a.
True [+0.5]
b..
False [+0.5] (the flow through fuel element has a Reynolds number > 6400)
REFERENCE 1.
Rhode Island: Safeguards Report, paragraph 3.2.1, p. 53.
.
- _ - _ _ _ - _ - _ _
)..
.
K.
FUEL HANDLING AND CORE PARAMETERS PAGE 35
ANSWERS.- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
A ANSWER K.01 (1.50)
a.
Move the linear level safety channel compensated ionization chamber from the corner post [+0.5] and hang it in the grid Ir box above position B-1 [+0.5].
b.
one [+0.5]
REFERENCE
'
1.
Rhode Island: Operating Procedures, 2.2.9, p. 2-3.
2.
Rhode Island: Technical Specifications, Operating Limitations,
'
paragraph 2.12, p. 24.
-
ANSWER K.02 (2.50)
See Figure on next page.
No. Fuel Count Elements Rate-CPS 1/M
........
........
....
.
10 1.00
13 0.77
17 0.59
25 0.40
50 0.20 REFERENCE 1.
Rhode Island: Operating Procedures, 2.2.9.e, p. 2-3.
\\
ANSWER K.03 (1.50)
a.
0.05% delta k/k
[+0. 5]
b.
By using new or irradiated fuel elements in which the effect of xenon poisoning has sufficiently decayed (to 0.05% delta k/k or less).
[+1.0]
REFERENCE
~
1.
Rhode Island: Operating Procedures. 2.1, p. 2-1.
.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. - - _ _ _ _ _ - _ _ _ _ _ _ _ _. _ _ _ _ _ _.....
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SECTION K ANSUER K.02 RHODE ISLAND
.
C/20 7A'f"'
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K.
FUEL HANDLING AND CORE PARAMETERS PAGE 36
ANSWERS -- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
ANSWER K.04 (1.00)
a.
For critical experiments the core cooling system should NOT be operating [+0.5].
b.
The water level in the pool must be at least high enough to permit shock absorber action for falling control blades
[+0.5].
REFERENCE 1.
Rhode Island: Operating Procedures, 2.2.1, p. 2-1.
ANSWER K.05 (2.25)
a.
3% delta k/k
[+0.75]
b.
0.8 % delta k/k [+0.75]
3% delta k/k [+0.75]
REFERENCE 1.
Rhode Island: Operating Procedures, paragraph 3, p. 3-1.
2.
Rhode Island: Operating Procedures, paragraph 4, p. 4-1.
l ANSWER K.06 (2.00)
All operations pursuant to the preparation and shipment of spent fuel require that the BUILDING CLEANUP SYSTEM [+0.5], BUILDING VENTILATION SYSTEM [0.5], AREA MONITORS [+0.5] and AIR MONITORS
[+0.5] be operable.
REFERENCE 1.
Rhode Island: Operating Procedures, 11, p. 11.1.
.
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. ~...
' **
K.
FUEL HANDLING AND CORE PARAMETERS PAGE 37
- ANSWERS -- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
ANSWER.
K.07
~(1.25)
'
to avoid contaminating hands [+0.5]
to avoid fingerprints [+0.25] on the plates that could possibly affect heat transfer characteristics [+0.5]
REFERENCE 1. -
Rhode Island: Operating Procedures, 2.2.2, p. 2-1.
ANSWER K.08 (2.00)
1.
only one fuel assembly moved at a time 2.
the number of' assemblies per storage rack is limited 3.-
adequate spacing between racks'is required-4.
each rack shall be covered with a cadmium lined aluminum cover
[+0.5] each REFERENCE 1.
Rhode-Island: Technical Specifications, pp. 17 and 31.
.
- _ _ _ - _ _ _ _. _ _.. -. _ _. _ _
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K.
FUEL HANDLING AND CORE PARAMETERS PAGE 38
- -
ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
ANSWER K.09 (3.00)
1.
Absolute worth of any single experiment or the combined worth of connected or otherwise related reactivity that could result in a simultaneous addition shall not exceed 0.006.
2.
For single or combined connected experiments NOT RIGIDLY FIXED in place, their single or combined worth shall not exceed 0.0008.
3.
Experiments shall not be installed so that it could shadow nuclear system monitors.
i 4.
Free movement of control rod shall not be compromised by interference from installation failures of experiments.
5.
Fuel element damage must not result if installation of experiments fails.
6.
No experiment shall permit materials to contaminate reactor pool water to cause corrosive action on reactor components OR 7.
that can credibly result in an explosion.
Any four (4) [+0.75] each, +3.0 maximum.
REFERENCE 1.
Rhode Island:
Technical Specifications, p. 24.
ANSWER K.10 (1.50)
a.
True [+0.5]
b.
False [+0.5]
(the most reactive element withdrawn AND the servo regulating element must also be withdrawn)
c.
False [+0.5]
(must not exceed 130 degrees F)
REFERENCE 1.
Rhode Island: Technical Specifications, pp. 27 and 28.
.
m______ _ _.. _. _ - _ _. _ _ _ _ _ _ _
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'K.
FUEL HANDLING AND CORE PARAMETERS PAGE 39 ANSWERS -- RHODE ISLAND & PROV P AEC-87/10/20-CLARK, R.
ANSWER K.11 (1.50).
The source. output will dominate the shape of the.1/M plot [+0.5],
making it concave downward [+0.5], overestimating critical mass
'
'[+0.5] resulting in a non-conservation [+0.5] estimate of fuel required for criticality.
Any.three (3), +1.5 maximum.
REFERENCE 1..
Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Volume 3.
,
e I
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ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 40 ANSWERS -- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
I l
ANSWER L.01 (3.00)
)
b.
Senior Reactor Operator; Assistant Director, on, 2t#'7#d O'
a, g )].,,7,, h a.
Reactor Operator; Senior Reactor Operator
/
c.
Director; Assistant Director j
[+1.0] each REFERENCE 1.
Rhode Isisnd: Operating Procedures, Section 1, " General,"
paragraph 1.14, p. 1-3; paragraph 1.4, p. 1-1; and paragraph 1.31, p. 1-4.
ANSWER L.02 (1.25)
I 1.
False (switchtomanual,notifySRO)
'
2.
True 3.
True 4.
False (lower power, inform SRO, check drive)
5.
True
[+0.25] each REFERENCE 1.
Rhode Island: Abnormal Procedures, Nos. 11, 5, 6, 15 and 3.
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L.
ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 41
ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
ANSWER L.03 (2.00)
.
.1. -
Assure actions required for the safety of personnel or protection of equipment have been taken.
2.
Determine cause of scram.
3.
Assure correction of the abnormal condition.
4.
Assure applicable portions of the checkout procedures are repeated.
5.
' Authorize a startup under his (SR0's) direct supervision.
6.
Assure that actions taken are recorded in the log.
Any four (4) [+0.5] each, +2.0 maximum.
REFERENCE 1.
Rhode Island: Operating Procedures, Section 9, paragraph 9.2, p. 9-2.
ANSWER L.04 (2.25)
a.
rinse contaminated skin area [+0.75], call-wait for health physicist to arrive [+0.75]
b.
leave the area immediately [+0.75]
REFERENCE 1.
R'hode Island: Operating Procedures, Section 12, paragraph 12.4, p. 12-4.
ANSWER L.05 (2.00)
1.
'an immediate need exists to save a life [+1.0]
2.
the emergency director is not available [+1.0]
I REFERENCE 1.
Rhode Island: Emergency Plan, paragraph 3.1.1.2, p. 4.
.
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ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 42
ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
ANSWER L.06 (1.50)
l 1.
initial. start up and approach to power 2.
. recovery from an unplanned shutdown or power reduction
3.
refueling
[+0.5] each REFERENCE 1.
Rhode Island: Technical Specifications, J.3.b.2, p. 20.
ANSWER L.07 (3.00)
a.
By an alarm [+0.5] at a continuously manned control station in Providence, Rhode Island. [+0.5]
b.
1.
a fire in the reactor room 2.
a fire in other than the reactor room 3.
a decrease of 2 inches in reactor pool water level 4.
a power failure in the reactor building 5.
an alarm condition from the radiation monitors with readings in the control room 6.
an alarm condition from any other selected feature Any four (4) [+0.5] each, +2.0 maximum.
REFERENCE 1.
Rhode Island: Technical Specifications, paragraph 2.b, p.10 and paragraph f., p. 29.
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ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 43 L.
ANSWERS -- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
l l
ANSWER L.08 (1.00)
1.
shut down the reactor 2.
conduct or direct a survey of the area 3.
replace any faulty monitor with portable instrumentation-Any two (2) [+0.5] each, +1.0 maximum.
REFERENCE 1.
Rhode Island: Abnormal Procedures, No. 17.
ANSWER L.09 (1.50)
a.
True [+0.75]
False [+0.75]
(the Emergenc initiate recovery operations)y Coordinator has authority to b.
REFERENCE 1.
Rhode Island: Emergency Plan, Section 3, paragraph 3.1.1, pp. 4 and 5.
.
h
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L.
ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 44
ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.
ANSWER L.10 (2.50)
1.
notify the Director, Assistant Director or Reactor Supervisor i
2.
notify the NRC l
3.
shutdown the reactor 4.
evacuate facility 5.
notify Site Security (campus police, etc.)
6.
notify Narragansett Police and State Police 7.
arrange for search of facility buildings 8.
notify FBI Any five (5) [+0.5] each, +2.5 maximum.
REFERENCE 1.
Rhode Island: Emergency Plan Implementing Procedures, Appendix 1.1.
.
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _
.g.
p
,
,
.o.
.....................__........___..________..................__...._____.
EQUATION SHEET
..._____....______..___..._____......____..___......___....___..............
.
.
Where mi = m2 l
(density)1(velocity)1(area)1 = (density)2(velocity)2(area)2
_______...........__............______.....____.. ___.........._______....
KE=*{2 where V = specific PE = mgh PE + KE +P V 1 1 = PE +KE +P Y22 l
l
2 volume P = Pressure
.....__._____............._______.____________....._.____.....__________._
Q=mcp(T-Tin)
Q = UA (T-Tstm)
Q = m(hl-h2)
out ave
________....__........... __..__....._______.._____..._________..........__
P = P 10(SUR)(t)
P = P e /T SUR = 26.06 T = (B-p)t t
o o
T p
..................................__________......__......__________.......
delta K = (Keff-1)
CR1(1-Keff3) = CR (1-Keff2)
CR = S/(1.Keff)
(1-Keff1)
(1-Keff) x 100%
M=
SDM =
1-K K
eff2 eff
.....________...___...........__....__......______________.......__________.
decay constant = In (2) = 0.693 1 = A e-(decay constant)x(t)
A t
t g
1/2 373
..__.....__...........................__..____.........................___..
Water Parameters Miscellaneous Conversions
1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 1 f t3 = 7.48 gallons 1 hp = 2.54 x 103 Btu /hr Density = 62.4 lbm/ft3 1 MW = 3.41 x 106 Btu /hr Density = 1 gm/cm3 1 Btu = 778 ft_lbf Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft.lbm/lbf-sec2
.._..__............__.....______..........________..............__.........
N = No e /T t
Dose (D) in R/hr at l',
D = 6 CE [C in curie, E in gamma energy in MeV]
_ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
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f)1 7/7CMn?&s'7
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EXAM REVIEW Question No.
Facility Comment Examiner Comment / Resolution H.03 As stated, this cuestion will Agree. Answer key changed prompt the candic ate into prior to grading to provide a an explanation of the primary description of primary-secondary and secondary coolant loops cooling tower system.
with the ultimate heat sink being the atmosphere through
.the cooling tower. A correct description-is an acceptable answer.
H.07 An alternative acceptable Disagree. Answer key not answer is "so as to limit changed.
the power level reached during the temperature increase associated with an excursion by(because ofdecreasing reactivity temperaturecoefficient)".
H.12 The stated betas are not Comment is correct. Answer correct. This would not, key not changed.
however, necessarily affect answer.
I.05 There is a typographical Comment is correct. Answer error in the first line of key not changed.
the question.
" Gamma should read " gammas." protons" This is probably not serious enough to affect the candidate's response.
I.09 The correct answer is "because Agree. Answer key modified to the flow rates are different include this comment, as an under these conditions."
option, prior to grading.
1.11 There is an error in the Agree.
The answer key corrected answer key. The gamma rays prior to grading.
from Co60 are each emitted per disintegration.
Therefore, E in the equation i
is the sum of 1.17 and 1.33
!
MeV.
.
.
-_____m-__.__m_
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Question J
No.
Facility Comment Examiner Comment / Resolution
)
!
I i
I.12.c There is no correct answer.
Disagree--Answer key not l
changed.
J.03 The building cleanup blower Agree. Answer key changed for is not energized following grading to reflect this a loss of normal power.
information which was not ONLY if an evacuation button available (or not noted) during has been pressed. Other loads exam preparation.
automatically energized are the sump pump, chem lab blower, reactor room electric door lock, air compressor to valves and several emergency duplex outlets.
i
J.06 The word "is" in the first This typo pointed out during line should be "if".
An exam to candidate.
The additional key change (in additional key change; namely Answer Key) is "a decrease a decrease in reactor power, in reactor power."
is not an additional key change but an alternative way to note
.
" negative reactivity added."
Answer key not changed.
J.09 It should be noted that this Disagree.
Reference material reactor has never operated does not note the operational with cover plates over the conditions, only the design core. An acceptable answer feature.
No change to answer to this question is "down key.
draft cooling and the depth of the pool."
K.01 Position B-1 is an appropriate Disagree.
Reference material position for the critical is explicit as to position B-1 experiment used as an example being preferred and not merely in the operating procedures.
an optional location.
Answer for an intended, different, key not changed.
final core configuration the appropriate position may be at a different location.
i e
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Question No.
Facility Comment Examiner Comment / Resolution
,
K.02 The first line of the question Agree. Answer key changed.
(based on the answer) should read "The initial count rate for a RINSC reactor
-
core with N0 fuel..." A correct answer which ignores the first sentence is acceptable.
K.03.a This question is ambiguous Comment has merit.
However and does not lead to a wording for the question quoted discussion of the performance directly from reference material, of critical experiments l
with a dirty (Xe containing)
Answer key not changed.
core. An acceptable answer is "4.7% delta k/k."
K.03.b Based on the answer to Answer to K.03a not changed.
K.03.a., an acceptable answer Answer to K.03b not changed.
is "by rod calibrations using inhour method."
L.01.b An acceptable answer is Valid comment.
Answer key
" Reactor Operator" and " Senior changed.
Reactor Operator."
L.04 This question is confusing Disagree. Answer key not
,
because the candidate knows changed.
that an experimenter at the pneumatic irradiation facility can only communicate with the reactor operator in the control room.
Therefore, answer contains the directions most likely provided by operator, not senior operato 'i ; '?
.c
,
-
-
N
,
Question No.
Facility Comment Examiner Comment / Resolution L.09.a While it is true that the Disagree. No change to answer Emergency Coordinator does key.
have the authority to initiate recovery operations, the authority is severely limited as described on pages 4 and 31 of the emergency plan.
Therefore, false is also an acceptable answer.
l
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