ML20205A610
| ML20205A610 | |
| Person / Time | |
|---|---|
| Site: | San Onofre, University of Virginia |
| Issue date: | 06/30/1986 |
| From: | Brockman K, Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20205A568 | List: |
| References | |
| 50-062-OL-86-01, 50-62-OL-86-1, NUDOCS 8608110407 | |
| Download: ML20205A610 (52) | |
Text
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A Mot UNITED STATES
^o NUCLEAR REGULATORY COMMisslON
['
REGION 11 3
y Ij 101 MARIETTA STREET, N.W.
t ATLANTA, GEORGI A 30323
%,...../
ENCLOSURE 1 EXAMINATION REPORT 62/0L-86-01 Facility Licensee:
University of Virginia Charlottesville, VA 22901 Facility Name:
University of Virginia Facility Docket Nos.
50-62 and 50-396 Written and oral examinations were administered at the University of Virginia near Charlottesville, Virginia.
(bMeks.cW YA3/84 Chief Examiner:
i K/ E.
rockmarV Date Signed Approved by:
., o Jeg O d /,,
h/3e/(C iUffn F. Munro, Acting Sectich Chief Date'51gned O
Summary:
Examinations on May 13, 1986 An oral examination was administered to one candidate, who passed. Two candidates were administered written examinations, one of whom passed.
8608110407 860708 PDR ADOCK 05000062 V
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REPORT DETAILS 1.
Facility Employees Contacted:
J. P. Farrar, Operations Manager 2.
Examiner:
- K. E. Brockman
- Chief Examiner 3.
Examination Review Meeting At the conclusion of the written examinations, the examiner provided J. P. Farrar with a copy of the written examination and answer key for review. The following comments were made by the facility reviewers.
I 3
a.
SR0 Exam 4
(1) Question H.08 Facility Comment: The solvency of gases in water is not relevant to reactor operations. Recommend delete question.
I NRC Resolution: Disagree. Gas content is a factor in the corrosion process. The concept is valid exam material. Question l
retained.
(2) QuestionH.14(a) study at the University of Virginia (UVA) presented as a topic of Facility Comment:
" Power Defect" is not Recommend delete question.
NRC Resolution: Accepted.
Since the terminology is not taught, it is unfair to ask for this definition. Question deleted from exam.
(3) Question J.08 Facility Comment: The new storage facility makes this caution no longer valid. The procedure has yet to be updated.
Recommend delete question.
NRC Resolution: Accepted.
Caution is now invalid as per examiner inspection. Deleted from exam.
2 July 8, 1986 (4) Question K.06 Facility Comment: UVA does not have pressurized fuel rods.
Recomnend delete question.
NRC Resolution: Not accepted. Concepts investigated are heat transfer mechanisms and materials sciences. Question retained.
(5) Question K.08 Facility Comment: The term " cold clean, excess" is not used at UVA.
Recommend delete question.
NRC Resolution: Not accepted. Clarification was provided during the exam. Question retained.
(6) Question K.12 Facility Comnent: The procedure addresses " refueling" activities, vice " fuel handling" activities. Recommend answers be graded, allowing for potential confusion.
I NRC Resolution: Acknowledged. Answers will be evaluated with attention to this possibility.
4.
Exit Meeting At the conclusion of the site visit, the examiner met with representatives of the plant staff to discuss the results of the examination. There were no generic weaknesses noted during the oral examination.
The cooperation given to the examiner was noted and appreciated.
The licensee did not identify as proprietary any of the material provided to or reviewed by the examiner.
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- M A S T E T< -
ENCLOSURE 2 U.
S.
NUCLEAR PEGt4.ATORY C O M MIS'310 N SENf00 PEACTOR OPERATOR LICENSE EXAMINATIO"
' ACILITY :
UNIVERSITY O' VIRGINLA REACTOR TYPE:
TEST DATE ADMINISTERED: 86/05/13 EXAMINER:
- BROCKMAN, K.
APPLICANT:
INSTRUCTIONS TO APPLICANT:
Use seperate paper for the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at 1 east 80%.
Examination papers will be picked up six (6) hours after the examination starts.
- . OF CATEGOPY
% OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY l _ _. 5 4____
________ H.
REACTOR THEORY 10 19.60
_'O 50I_1____ _'I_I_0
________ I.
RADI0 ACTIVE MATERIALS HANDLING O 6 DIGPOSAL AND HAZARDS 18.50 18.50
________ J.
SPECIFIC OPERATING CH AR AC TER ES TICS
_I__.50____
'O
_'O.60[____
________ K.
FUEL HANDLING AND CORE PARAMETERS l
i I
________ L.
tDM NI"TF AT rTOLEDUfES, 99.50 100.00 TOTALS CINAL GRADE _________________%
All work done on this enamination is my own. I have neither given nor received aid.
APPL 5CAUT 5~555UAiURE~~~~~~~~~~~~~~
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s H.
C:E ACT OR Tl!EORY
^ V; c 2
QUESTION H.0L (1.00)
Using the UVAR core as the basis for yavr discussion, EXPLAIN why the average thermal neutron f i v:: is LOWER for z WATER REFLECTED ore than for a GRAPHITE REFLECTED core of the same thermal power level.
QUESTION H.02 (1.00)
Which one of the following describes the HOTTEST CHANNEL in the UVAR?
a.
The channel where a control rod was just withdrawn leaving a large water gap.
b.
The channel next to the rod with the highest reactivity worth with that rod INSERTED 60% to 70%.
c.
The channel adjacent to a large water gap where a rod was just withdrawn.
d.
The channel adjacent to a rod that was just INSERTED.
QUESTION H.03 (2.50)
SMETCt: the following two (2) curves on attached Diagram t 692.
USE THE SAME SCALES FOR EACH CURVE.
a.
. XENON Concentration buildup on a startup from a clean core to 100% pouer.
(1.0) b.
XENON Concentration variation after a scram from 50% power for an extended period'of tima.
(i.e.,
50% equilibrium Xenon)
- (1.5)
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e s
M.
REACTOR f t:EoRY
- AGE 3
QUESTION H.00 (3.00)
Using the attached integral rod worth corve for a three-rod reactor, answer the following:
a.
Assuming that criticality is achieved with Rods A and B 80%
withdrawn and Rod C 45% withdrawn, STATE the SHUTDOWN REACTIuITY was present - AND - the PRE-STARTUP K-EFF.
(1.0) b.
If Rod C is moved to 55% withdrawn, from the critical positions in (a) above, STATE what the STADLE PERIOD meter indication would be. (1.0) c.
An A - B - C cod withdrawal sequence is used.
Rods can only be WITHDRAWN TO 90%.
Shutdown K-eff is 0.88 with counts of 15 cps.
CALCULATE the Rod Position necessary to attain counts stable at 60 cps.
-(1.0)
GUESTION H.05 (1.00)
Which of the following is the correct definition of microscopic cross section?
a.
The actual target area of the nucleus, b.
The effective target area of the nucleus.
c.
The total actual target area of all nuclei within the core.
d.
The to! I effective target area of all nuclei within the core.
QUESTION H.06 (1.00)
Which of the fellowing can be defined at "the number of neutrons causing fission that were originally born delayed divided by the total number of neutrons causing fission *?
a.
Lambda effective b.
Rho c.
Beta effective d.
Tau
( * * * *:* CATEGORY H CONTINUED ON NEXT PACE
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H.
REACTOR THEORY P At;E e
GUESTION H.07 1.00)
In a soberitical reactor, Keff is increased frcm.80 to.965.
Which of the following is the amount of reactivity that was added to the core?
a.
.085 (8500 pcm) b.
.10 (10000 pcm) c.
.125 (12500 pcm) d.
.220 (22000 pcm)
OUESTION H.08 (1.00)
One of the characteristics of water is that it will hold gases dissolved in solution.
Which of the following will INCREASE the concentration of dissolved gases in a quantity of water?
a.
INCREAGING.the pressure and LOWERING the temperature.
b.
DECREASING the pressure and LOWERING the temperature.
c.
INCREASING the pressure and RAISIMG the temperature.
j d.
DECREASING the pressure and RAISING the temperature.
QUESTION H.09 (1.00)
The reactor is being started up after shutdown for two weeks with the startup source installed.
The rod withdrawal is stopped at the -0.2,%
^k/k position and power level stablizes.
Which of the following state-ments concerning how power level will respond in the next hour if no other actions are taken is correct?
a.
Reactor power will remain essentially constant.
b.
Reactor power will slowly decrease due to being suberitical.
c.
Reactor power will repidly decrease to initial prestartup level.
d.
Reactor power will slowly increase due to lans-lived delayed neutrons.
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i H.
R"ACTOP THEORY
' AGE S
GUESTION 4.10
(*,00)
The -1/3 DPM SUR f o l l o w i r.g a reactor trip is caused by which of the following?
a.
The decay constant of the longest-lived group of delayed neutrons.
b.
The ability of U-235 to fission with source neutrons.
c.
The amount of negative reactivity added on a trip being Greater than the Shutdown Margin.
d.
The doppler effect adding positive reactivity due to the temperature decrease following a trip.
QUESTION H.11 (1.00)
With the reactor initially at a keff of 0.99, a certain reactivity change causes the count rate to double.
If this same amount of reactivity is again added to the reactor, which of the following will be the status of the reactor?
a.
Suberitical b.
Critical c.
Supercritical d.
Prompt Critical QUESTION H.12 (1.50)
Indicate uhether the follouing statements are TRUE or PALSE, a.
A positive 100 pem reactivity addition and a negative 100 pcm addition produce the came value of startup ratesi only the signs are different.
(0.5) b.
A delayed neutron has a higher probability of causing fission than does a prompt neutron.
(0.5) c.
If a reactor is supercritical, tha fraction of delayed neutrons shifts to the shorter lived pts... sors and the value of the average decay constant (lambda) d :reases.
(0.5)
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'1, REACTOR Tite 0RY c A r, L s
OllESTION h.13 (2.00)
Indicate how (INCREASE, DECREASE, or Rif. MAIN THE 9AME) an increase in moderator temperature will effect the following parameters.
a.
Resonance Escape Probability (0.5)
- b.
Thermal Utilization Factor (0.5) c.
Fast Non-Leakage Probability (0.5) d.
Fast Fis.sion Factor (0.5) n eo OlJEGTION H.14 f14tTI For the following definitions, give the term that is defined.
i.-
The-amount -o f--t-eset-ivi ty-thebi+-needed te ge # " om-hoPr ere- -
p o~e r-ta.r-ha t f u11
..:n u m D E.'ET E::
10.r57 3
b.
The fractional change in neutron pop'ulation per generation.
(0.5) c.
The decay of a neutron into a proton with the simultaneous ejection of an electron (and antineotrino) from the nucleus.
(0.5)
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013PO,A'. AND !MZnODS PAGE 7
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G I.T S T IO N I,0' i1.00)
'4 h i c h one of the follouin3 statements desertbes the correct sction(s) to t, e t&en, if a film bedqe is lost?
a.
Until a new film badge is obtained, no entry into a radiation area is allowed.
b.
A direct-reading dosimeter is used in lieu of the lost film badge, until a new film badge is obtained, c.
The individual dose is estimated by processing the Film badges of individuals with similar work f u n e '.. i o n s, then a new film badge is issued.
d.
A direct-reading dosimeter is issued, but entry into high radiation areas is not allowed until the next quarter to ensure quarterly exposure limits are not exceeded.
OUESTION T.02 (1.00',
Which one of the following statements regarding the release of pond water into Meados Creek is NOT CORPECr?
a.
The Reactor Supervisor must approve al.1 pond water releases.
b.
If the pond water reaches a level less then two feet below the top of the spillway, three samples must be taken.
c.
If the pond water activity is greater than 3E-8 ve/ml, the outer must be diluted prior to r e l e e tie.
d.
One week prior to discharge, thr23 samples must be draun to determine the pond water activity.
QUESTION I.03
( 2. 'io )
Coneecni.ng Effluent Releases a.
If a release from a waste hold-up tank is to be performed in con-junction with pond water, LIST the four items of information which should be present on the " JOINT RELEASE OF WASTE TANK AND PONO WATER AUTHORIZATION
- Form for release approval to be given.
(2.0)
S.
STATE who may perform the actual release.
(0.5)
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I.
R AOIC ACTIVE M Al e!?I ALS H ANDLING D3 GPOG AL ANO 1%Z A!cOS
- ' A G E G
90EG110N I.04 (2,00)
When a person becomes contaminated and the area of contamination on his body is large or not easily decontaminated, then certain personnel at the University are to be immediately contacted for the purpose of recommending decontamination procedures.
LIST the Job Titles for the four (d) persons who are to be immediatelty notified.
QUESTION I.05 (2.00)
A segment of Amendment i to the UVAR SAR analyzes AR-41 exposure problems at the facility.
The following questions pertain to that analysis.
a.
DESCRIBE the event which is postulated as the most severe NORMAL,
case of AR-41 release to the environment.
(1.0) b.
LIST the alarm setpoint(s) for the AR-41 monitors in the ductwork.(0.5) c.
GTATE the type of detector used for AR-41 this monitoring.
(0.5)
GUESTION I.06 (1.00)
Which of the following is a 10 CFR 20 exposure limit?
a.
5 rem / year - whole body, b.
1 iem/ quarter - whole body.
c.
10.75 rem / quarter - hands, d.
7 rem / quarter - skin of whole body.
(*****
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^2 DIG ACTIVE h A rgI ALS !4 Ae.0LINC O '_ '3 r' O C A L AND uAI MeOS cAct 9
OtlESTION 12 07 (1,00)
What would be the act.tvity of 20 3r ams of Al-20?
(Al-29 has a half-life of 2.24 minutes).
a.
1.95 E24 dps b.
1.06 E23 dps c.
3.25 E22 dpn d.
3.10 E21 dps QUESTION I.00 (1.00)
If a point source of samma radiation gives an exposure rate of 10 mR/hr at 1 meter, what would be the exposure rate a 5 meters?
a.
2.0 mR/hr b.
1.0 mR/hr c.
0.4 mR/hr d.
0.2 mR/hr GUESTION I.09 (2.00)
For the following radiation detector typest indicate whether the output intensity (current or pulse height) is proportional to the incident radiation energy; i.e.,
if the incident energy increases, will the out-put intensity increase?
(Answer YES or N0 to each part.)
a.
Ion Chamber (0.5) b.
GM (0.5) c.
Proportional Counter (0.5) d.
Scintillation (0.5)
(***** CATECORY I CONTINUED ON NEXT PAGE
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I.
GTOI0 ACTIVE ii AT E"I ALS H ANDLING 018POS AL AND HAZAPOU
~ AGE 10 QUESTION I.10 (i.50)
Match the isotopea in Column A with the principal type of radiation exposure hazard in Column B.
COLUMN A COLUMN B a.
Ar-41 1.
Alpha 2.
Beta b.
Tritium 3.
Neistron 4.
Gamma c.
N-16 5.
Proton GUESTION I.11 (1.00)
When frisking in the step-down area of the UVAR reactor room, at what level are you considered contaminated?
a.
10000 dpm (absolute) b.
5000 dpn fabuolute) c.
10000 dpm (above background) d.
3000 dpm (above b a c k.g r ou n d )
GUE5110N I.12 (1.50)
Match the radiation detector in Column A to the detector type in Column B.
COLUMN A COLUMN B a.
Control Room 1.
Ion Chamber t<(,,,,
\\
O rm ii-
.<.os 2.
Proportional Counter b.
S t ec h--G movs-3.
GM q, s u, h '. ', c v.\\ d t 4.
Scintillation c.
4 4,e ek-W r + i e+%%
UULbl10N 1.13 (2.00)
List, in order of severity (from lowest to highest), the FOUR Emergency Action Levels (EAL's) specified in the Emergency P1en Implementing Procedures.
(*****
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R A010 AC TI'1E M ATERI ALS H ANDLING DItiPut:. AL AND H AZ4,909 PACE 11 i
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90ESTION I.14 (1 00)
DESCRIBE how exposure to a member of a TOUP GROUP is deter uned.
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SPECICIC OPERATING CM A ;..t
! c 1STICC PAGE 00ES1I0tl J.0t (4.00)
Assume that the UVAR in being oper3ted at 2 riW e when a TOT AL ' 00S OF POWER (Electrical) to the Facility ocents.
EXPLAIN the effect of this
" blackout
- on EACH of the rollowing:
a.
Shim Rod Position b.
R e.3 u l a t i n.3 Rod Position c.
Core Spray System d.
Reactor Room Containment e.
Catch Tenk Level (Pool Makeup System) f.
Pool Water Temperature 3
Constant Air Monitors h.
Primary Coolant' System (0.5 each)
QUESTION J.02 (1.00)
For the purpose of making required reactivity measurements, STATE how an operator would determine that a.
The UVAR core is XENON FREE (0.5) b.
The UVAR core is COLD (0.5)
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305CIFIC OPC 9 AI D'G CH AP AC 1 & lS I LCS o A r;c 13 OUED: ION J,03
/t.00)
Regar ding U AR Primary and
'l e c o n d e r y Chemictr>
a.
LIST the applicable LIMITS (or ranges) for Conductivity and/or pH for:
(1.0)
(i)
Primary Water (2)
Secondary Water b.
LIST the two (2) reasons stated in the Technical Specifications which necessitate Primary Water control.
(1.0) c.
TRUE or FALSE The necessity to regenerate the primary water system demineralizer resin is indicated to the CONSOLE OPER-ATOR by an alarm.
.(0 5) d.
STARE the reason for adding Chromate compounds and detergent chomicals to the secondary water system.
(0.5) 00'! rron J,04 (1,50)
') 5 "> C '11 D I h o w N-?6 i-f o r nied dur t ng reac tor operation and SLATE what provi.lonq are made to a s s u r r>
ihat the affects cre minimized in the
'Ju Ao,
nUECTION J.05 (2.00)
Indicate whether the Actval Critical Position (ACP) would be HIGHER THAN, THE CAME AS, or LOWER THAN the rstimated Critical Position (ECP) for the following conditions.
Consider each separately.
a.
A Deam Tube is inadvertently filled aftor the ECP is calculated.
(0.5) b.
The reactor la started up 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after S/D for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at 1.0 MW instead of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ofter shutdown.
(0.5) c.
The ACP is taken at 100 W instead of 10 W with other parameters as calculated on ECP.
(0.5) d.
The primary pump is secured just prior to startup.
Note: the reactor has been shutdown all weekend.
(0.5)
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J jjtcIcIC 0 DArI40 CH A A AC I E.:lS i LL S r A C..;
L4 04ESTION J,06 (1.00)
STATE the tuo /. 2 ) flow requirements which the UVAR Core Spray System meets to satisfy its design basis (Flow Rates and Timing).
QUESTION J.07 (2.00)
DESCRIBE how the manimum excess reactivity is achieved on the CAVALIER without exceeding the Shutdoun Margin required by the Technical Spec-ifications.
Consider a fuel loading procedure where the reciprocal multiplication data indicates that the reactor will go critical with the next addition of a normal fuel element - thus a partial element has been loaded first.
QUESTION J.08
'DE.MTE Co,carrar,3 UNLOACIFC th CA;LIEP :are'
'Immediately after monitoring,. ear e.ement shall be moved to the Fuel -
p.,
scom...
etT ted prior to the move and WHY rnost this person OUESTION J.09
(.50)
STATE which annunciator comes in when the ' temporary electric eye
- system annunciates while it is being used as a Radiation Zone Entry Alarm.
GUESTION J.10 (1.50)
LIST three (3) symptoms (indications) which you could enpect to see as a result of a Dropped Rod.
QUESTION J.11 (1.00)
Per the UVAR SOP, DESCRIDE what indications would constitute INCONSISTENT READINGS of the Reactor Power Monitors (for power operations).
(*****"END OF CATEGORY J
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K.
FUEL HANDLING A'IO CCRE oARAMETC;'3 oACC 15 QU E L T I']N K.01 i.00)
Sh.tn r o d t, were last inspncted on April 30, 1904.
Which of the following dates would be the latest date to inspect them again without violating a UUAR surveillance requirement?
a.
December 10, 1904 b.
April 30, 1985 c.
May 30, 1905 l'
d.
August 31, 1905 OUESTION K.02 (1.30)
LIST the three (3) criteria which must be met in order to keep a Shim Rod in service, after an inspection.
QUCGTION K.03 (2.00)
Assume the following dato was obtained during a core loading:
Count Rate (CPS)
Number of Fuel Elements Rods In Rods Out 0
20 20 4
25 27 6
29 32 8
35 40 10 43 53 12 55 79 a.
Using the attached graph paper, PLOT a 1/H curve for the above data, and PREDICT when criticality will occur.
SHOW ALL CALCULATIONS (1.5) b.
Analytically PREDICT when criticality will occur.
(0.5)
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CATECORY K CONTINUED UN NEXT PAGE wassu)
K.
FUEL HANDLING AND CORE PARAMETERG PAGE 16 OUESTION K.04 (2,50)
MATCH the Fuel Element parameter listed in Column A with the type of Fuel Element listed in Column B.
(ANSWERG FROM COLUMN B MAY SE USED MORE THAN ONCE)
COLUMN A COLUMN B a.
18 Fuel Plates 1)
Standard Flat Plate b.
165 grams of U-235 2)
Standard Partial Element c.
0.4 Metal to Water Ratio 3)
Standard Control Rod Element d.
6 Fuel Plates 4)
MTR Curved Plate c.
0.211' Water Gap between Plates 5)
MTR Rod Element QUESTION K.05 (2.50)
Concerning Refueling activities a.
STATE the bases for the precaution that no reactor core shall be taken critical with Shim Rod positions below 10 inches and the Regulating Rod fully withdreun.
(1.0) b.
LIST the log entriet which are required when unloading fuel.
(1.5)
GUESTIDH K.06 (1.00)
Which of the following is NOT a reason for pressort:ing the fuel rods with helivm?
a.
Minimi e clad creeping inwards toward fuel pellets.
b.
Increase gap (pellet to clad) thermal conductivity.
c.
Allow dutection of clad failure by helium analysis of the coolant.
d.
Maintain lower fuel centerline temperature.
(sea ** CATECORY K CONTINUFO ON NEXT PAGE
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K.
CUEL HANDLING AND CORE PARAMETERS PAGE 1,
00ESTION K.07 (1.00)
Following a reactivity insertion of +50 pcm to a suberitical reactor, the new count rate will take longest to reach elvilibrium i f :
a.
The new keff is.997 and source strength is 50 N/sec.
b.
The new keff is.999 and source strength is 50 N/sec.
c.
The new keff is.997 and source strength is 100 N/sec.
d.
The new koff is.998 and source strength is 100 N/sec.
QUESTION K.08 (1.00)
'The Shutdown Margin is correctly calculated by which of the following?
a.
Total Rod Worth - Highest Rod Worth + Cold, Clean Encess b.
Highest Rod Worth - Cold, Clean Excess + Total Rod Worth c.
Cold, Clean Excess - Highest Rod Worth - Total Rod Worth d.
Total Rod Worth - Highest Rod Worth - Cold, Clean Excess GUEGTION M.09 (1.00)
The following are the boiling phases associated with nucleate boiling and departure from nucleate boiling.
1)
Transition Dolling 2)
Sulk Boiling 3)
Film Dolling 4)
Sub-cooled (Local) Boiling Which of the following is the order in which they would occur in_a channel with normal flow and high heat flux?
a.
2 4.
3, 1
b.
2, 4,
le 3 c.
4, 2, 3, 1
d.
4, 2,
1, 3
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CATECORY K CONTINUED ON NEXT PAGE *****)
e w.
CUEL HANDLING Atl0 CORE FA!'it"EIEPS
'N G E 10
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QUESTION K.10
(.1 *i 0 )
In the event of an Evacuation signal during fuel movement. STATE what actions are to be taken by the fuel handling ereu?
OUESTION K.11 (1.00)
LIST the TWO Technical Specification design limits for fuel storage locations at the UVAR.
QUESTION K.12 (1.50)
LIST the minimum radiation monitoring detectors that must be in operation during fuel handling evolutions on the UVAR, without entering into an LCO.
QUESTION K.13 (1.00)
EXPLAIN why the CAVALIER Log N Instrument uses a Compensated Ian Chamber (CIC) while the Gamma Ray Power Range Instrument uses an Ian Chamber (IC).
QUESTION K.14 (1.00)
LIST two (2) times when Control Rod CALIDRATION ts required.
QUESTION K.15 (1.00)
STATE what a c t i o n ( -3 ) must be taken prior to removing TWO (2) Control Rods from the core.
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(
.50)
LIST the three (3) conditions which must be satis'ied, per the Tachnical Specifications concerning the Alternate Reactivity Insertion System (ARIS), for the CAVALIER to be operated.
GUESTION L.02 (2.00)
LIST four (4) of the forces which the Restraining Force on SECURED EGUIPMENT must be able to withstand.
QUESTION L.03 (3.50)
SKETCH the Thermal Power vs. Coolant Flow Rate operational curve (Safety Limit Curve) for the FORCED CONVECTION MODE of the UVAR.
De sure to annotate axes parameters, critical and end points, and all other epplicable core parameter limitations.
QUEST 70N L.04 (1.00)
Which ona of the following conditions is NOT REOUIRED to allow removing a jumper from the control console of the CAVALIER?
a.
No Safety System is compromised.
b.
Reactor Supervisor's approval.
c.
Reactor Log Book entry.
d.
Reactor hotdown.
GUESTION L.05 (1.00)
Answer TRUE or FALSE to the following, a.
The Itcensee (you) shall notify the NRC within 15 days after the occurrence of a disability.
(0.5) b.
If a licensee (you) have not been actively performing the functions of a senior operator for a period of five months, you can NOT resume licensed activities without NRC concurrence.
(0.5)
(*****
CATEGORY L CONTINUED ON NEXT PAGE
- )
e o
o L.
AC M DiIS T ' A T IV C 'C OCC nt"":3 C O':0 D I G H 3 ANO LIMI~ATIONS 0 AGE 20 m!ES T ION L,Co
' 1
'5 0 )
Per the UUAR TS, LIST the minimum required operating crew with the reactor at 1.0 MW, steady state conditions.
STATE whether each individual must be at the facility or may be on call.
QUESTION L.07 (1.00)
LIST the requirements which mus t be met to process " minor' procedural changes (Iricl ude in your response a definition of " minor").
QUESTION L.08 (1.00)
The Power Leve~. LSSS for the CAVALIER is 100 W, much greater than the average of the Maximum Average Power Limit of 200 W-hr/ day.
STATE the basis for allowing this higher power (i.e.,
how was the limit deter mined?)
DUESTION L.09 (2.00)
You are told at escort a v2sitor through the UVAR reactor room.
The visitor is a reporter on a local newspaper, but personally unknown to you or your supervisor.
DESCRIDE your responsibilities and required actions, per UVAR 30P 13.
(*****
CATEGORY L CONTINUED ON NEXT PAGE
- )
O L.
AOMINISTRATIVE PROCEDUPES, CONDITIONS AND LIM IT..T I C rP2 pag 21 QUESTION L.10 (1.00)
Given:
"A Ovalitative verification of acceptable performance by observation of behavior.
This verification should include comparison with other independent indications or methods of measuring the same variabler where this capa-bility exists."
Which of the following does this statement most accurately DEFINE.
a.
Channel Calibration b.
Channel Check 2.
Functional Test d.
Functional Check OUESTION L.11 (2.00)
With respect to the UVAR Natural Convection Safety Limit a.
DEFINE
'P' and STATE its SPECIFICATION.
(1.0) b.
DEFINE
'T and STATE its SPECIFICATION.
(1.0)
I QUESTION L.12 (1.50)
Per the CAVALIER SOP, when maintenance is performed whereby operation of a system or component could result in personnel injury!
a.
STATE what action must be taken on the controlling device (s) for that system.
(1.0) 6.
STATE who can " undo' the above action (s).
(0.5)
OUESTION L.13 (1.50)
Per the UVAR TS, LIST the three (3) requirements which must be met when an individual is ON CALL.
(*****
END OF CATEGORY L
- )
(************* END OF EXAMINATION ***************)
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H.
REACTOR TilEORY PAGE 22 ANSNERS -- UNIVERSITY OF VIRGINIA
-8 6 /05/13-BROCI'M AH r K.
ANSWER H.01 (1.00)
Critical loading is less for graphite (2.31 ks vs. 2.97 kg)
For same MW, if the amount of U-5 goes down, then the flux must So up to maintain the same fission rate
- OR -
More neutrons are reflected back into the core because water is a better neutron absorber.
(1,0)
REFERENCE
'UVA: UVAR SAR, pp 26 - 275 DPCr Section 3.3 ANSWER H.02 (1.00)
C REFERENCE UVA:
UVA SAR, p 136 ANSWER H,03 (2.50)
See At'?ched Graphs REFERENCE UVA:
DPCr pp 161 - 164; NUS, Module 3, pp 10.2-2/3, 10.3-1/3
H.
?'i A C T 3 R THEORY
- A O '.
23 A N S L' E RS -- UNIVERSITY OF '!1P GINI A
-06 / 0 5/13 - 3% J ;d e r V-ANSuER H.04 (3.00) a.
Rod A 5
^k/k Rod B 3.9 %
^k/k Rod C 3.55%
^k/k Shutdown Reactivity ~
12.4'5%
^k/k
=
(0.5)
- A (K-eff - 1)/K-eff
.1245 -> k - 1 =
.1245
- k -> k= 0.34 (0,5)
=
s b.
Rod C Inserts = 0.45 ^k/k a:Deta-eff - rho)/ lambda
- rho = (.007 -.0045)/.08 *.0045 T =
= 6.94 seconds
- ( 1. 0 )
c.
C2/C1 = (1-ki)/(1-k2) 60/15 = (1 - 9gg)/(1 - k2) -> k2 =.97
-> 10.5% ^k/k (0.5)
Rod A w/d 0 90% = -5.15 % ^k/k Rod B w/d 0 90% = -4
% ^k/k Rod C needs 1.35% ^k/k (10.5% - 9.15%)
24% Withdrawn (0.5)
=
REFERENCE UuA' NUSr Module 3r Unit 6 ANSWER H.05 (1.00) b REFERENCE CPF.Lr Nuclear Reactor Theoryr P.
5-2 ANSWER H.06 (1.00)
C REFERENCE NUSr Reactor Theory
P.
REACTOR THEORY oaGr 24 ANSWERS -- UNIUcoSITY Of UERGIr1To
-96 /0"; /10- 9 r'OC;:M AM - -
ANSWER H.07 (1.00) b REFERENCE NUS, Vol 3, pp 6.1-3 ANSWER H.08 (1.00) a REFERENCE General Physics, HT & FF. Chapter 1 ANSWER H.09 (1,00) a REFERENCE Basic-Reactor Theory, Suberitical Multiplication ANSWER H.10 (1.00) a REFERENCE VEGP, Training Text, Vol.
9, p.
21-47 Westinghouse Reactor Physics, pp. I-3.17 & 19 DPC, Fundamentals of Nuclear Reactor Enjlou ' - i 19,
p.
106 001/000-M5,49 (2.9/3.4)
ANSWrIR H.11 (1.00)
C REFERENCE HBR, Reactor Theory, Session 42, pp. 3 &4 DPC, Fundamentals of Nuclear Reactor Engineering 004/000-K5.08 (2.6/3.2)
a.
- c. ear, Toe Tntogy w,.-
A N S W ':R S -- U:JIVERSITY Oi Ul f:' GI N I A
-86 / 05 / ' 3 --BROCMii AN -
ANSWER H.12 (1.50) a.
FALSE (0.5) b.
FALSE (Power Reactor): TRUE (Research Reactor)
(0,5) c.
FALSE (0,5)
REFERENCE Westinghouse Nuclear Training Operations, pp. I-3.9 - 15 ANSWER H.1 '3 (2.00) a.
DECREASE (0.5) b.
INCREASE (0,5) c.
DECREASE (0.5) d.
INCREASE (0,5)
REFO<ENCE Westinghouse Nuclear Training Operations, pp. I-2.31 - 36 g. co ANOWER H.14 fM a.
Power Defect (-0. 2'5 -f or rewerecef ficient )
T t LN 14rST b.
Reactivity (025) c.
Deta (minus) Decay
. (0.5)
R EF E7:ENCE NesttnJhouce Reactor Physics, pp. I-5.26, I-3.2r and I-1.18 NSR, Reactor Theoryr Gession 32, p.
3 and Gension 217 p.
2 and Sessicn 4r p.
2
I.
R ADI0 ACTIVE r A TET:I ALS H AN0llilO DISPOCi L
- W' LZ4'RDS PAGE 2a ANSuERS -- UNIVERSITY OF '!I OINI A
- rf /.
n' /1-OPOCUM AH -
?'
ANSWER I,01 (1,00) b REFERENCE UVA:
UVAR SOP 10-3 ANSWER I.02 (1.00) d REFERENCE UVA:
UuAR SOP, pp 10-9 & 10 ANSWER I.03 (2,50) 3.
Specific activity from the Waste Hold-up Tank Specific activity of the pond Volumetric flow rate of the pond and tank Calculated activity of the mixed release (0.5 each) b.
The Facility Staff or Environmental Health 2nd Safety Office Staff (0.5)
REFERENCE UVA:
UVAR SOP, pp 10 12 ANSHER I.04 (2.00)
Reactor Health Physicist Environmental Health and Safety Officer Facility Director Reactor Supervisor (0.5 each)
REFERENCE U"At UVAR SOP, p 10-19
I.
RADI0 ACTIVE MATERIALS 9AMOLING DISPOSAL AND PaZARDC PAGE 27 ANSWERS -- UNIVERSITY Or
'J IP G I N I A
-06/05/13- 0 0 C tf M A N.
K.
ANSWER I.05 (2.00) a.
Flooding a Beam Port after a long period of operation (0.5) due to the large volume of irradiated air released (0.5).
(1.0) b.
800 cpm (700 cpm + 100 cpm background).
(0.5) c.
(Thin walled) G-M Tube.
(0.5)
REFERENCE UVA:
UVAR SAR, Amendment le pp 54 - 56 ANSWER I.06 (1.00)
C REFERENCE 10 CFR 20.101 000/060-K1.02 (2.5/3.1)
ANSWER I.07 (1.00) d REFERENCE NUSrNETr Volume 2 ANSWER I.09 (1.00)
C REFERENCE Rud Health Handbook, UO0 HEW, p.
56
I.
e0I0 ACTIVE -ATc71ALS
'0 HOLI% ; O I S P r)W -.
. :.' ' 0 0 Y;E 2"
,,pgyqqc -. firiigogI,
< i e t<!;IMI A n '. ' ' _.
' occi'M ys,
i ANSWER I.09 (2,00) a.
YES (0.5) b.
NO (0.5) c.
YEG (0,5) d.
YEG (0.5)
REFERENCE FNP, Health Physica and Radiation Protection Lesson Plans, pp. 41-46 William J.
Price, Nuclear Radiation Detection. pp. 43 - 46, 77, 138, and 196 UECPr Training Text, V e l v eie o r pp. 23-3? - 42 072/00-MS 01 (2.7/3,0)
AdGt:ER I.10 (1.50) a.
4 (0.5) b.
2 (0,5) c:
4 (0,5)
REFEREMCE Chart of the rJuclides AH9!'EP I.11 (1.00)
C FEFERENCE UVA: UVAR SOP 10-5 ANGWER I.12 (1.50) a.
1 (0,5) b.
3 (0.5) c.
4' '5 (0,5)
REFERENCE NCOU, Ops Manuale Table 7-1 u v A '. cAF t.
^ AOIC ACTIVE ti A T EF-:IALS l' ANDLING Olgrag u_
Ann ug:Ap99 angc
- n I.
ANSWECS -- UNIVERSI'1 7 11POINIA
- ;M J OS /13-GR OC1'M A N -
v, ANSWEP I.13 (2.00)
(0.3 for EALr 0.2 for order) 1.
Unusual Event (0,5) 2.
Alert (0,5) 3.
Site Emergency (0,5) 4.
General Emergency (0.S)
REFERENCE NCSur Emergency Procedure 4.0r p.
1 UVA:
CAF ANSWER I.14 (1.00)
The tour guide will wear two dosimeters.
The entire group is considered to be equally exposed to a level equel to the everage of the two dosi-meters.
REFERENCE UUA:
UUAR SOP 10-4 4
J.
SPEC DTIC OPER A TING CH A;: ACTERICTICS ACE On AMSWERS - UNIVERSITY Or o19g1914
_.g6 95, 3._q.:g gi y a,
ANSWER J.01 (4.00) a.
FULL IN (Loss of Magnet Current) b.
AS IS (Loss of Drive Mater Current) c.
Water Flow to Tanks STOPS d.
Ventilation Exhaust Duct Door & Personnel Access Door CLOSES e.
NO EFFECT (Mechanical Float Valve) f.
INCREASES (Decay Heat w/o Flow) 3 STOPS (Ceases to Function) h.
STOPS (Pump Stops -:: No Flow nor Indication)
(0.5 each)
REFERENCE UUA:
UVAR SAR, Various Sections ANSWER J 02 (1.00) a.
The reactor has not been operated at a power greater than 1 kW (0.25) during the previous 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> (0.25)
(0.5) b.
Pool Temperature less than 90 deg F.
(0,5)
REFERENCE UVA: U'AP SOP 5-24; UVAR TS, Definitions AMSuEP J.03 (3,00) c (1) Conductivity 1 - 2 umho/cn -OR-Poolwater s 5 umho/cm pH 6 - 7
-OR 7. 5 (0.25 each)
(2) pH CNLY 6 - 7.4 (0,5) 6.
Limit Corrocion of the Fuel Cladding Limit Inventory of radioactive nuclides (0.5 each) c.
TRUE (0.5) d.
Chromates - Corrosion Control Detergent - Algae Control (0.25 each)
grocIFIC gescATING cappAr_TEo191ICS t.u;r
- 1 Arts 9ERS --
19 - r ~ 4: " ' 1 r P t/IUGIN L A
- 8 6 ' 0 5 ' !. '2
~ 3 0 C !C M A N, '<'
REFERENCE UVAt UVAR SDP 0-14 TS 3-11 AMSWER J.04
( 1 > 'i O )
16 1
16 1
0
+n
- ~ > N
& P (0.5) 8 0
7 1
Flow water directs returning primary water at wall furthest from the reactorr thus minimizing N-16 gamma activity.
(0.5)
In forced convection-newly formed N-16 :. s drawn into the header instead of being allowed tu rise to the pool surface.
- ( 0.5 )
REFERENCE UUA:
12 VAR SAR, p 65 Ai!SWER J.05 (2.00) a.
THE SAME AS (0,5) b.
HIGHER THAN (0;5) c.
THE SAME AS
( O e 5.>
d.
TI!E SAME AS
( 0 > :i )
7ECERENCE NCSur PDG, Vol. II, p.
11 ANSWER J.06 (1.00) 1)
10 3pm (0.35) for the first 30 minut?1 (0.35)
(0.7) 2)
7.5 spm (0.15) for the next 60 minutes (0.15)
(0.3)
l J.
SC OPEpn rIr;g c!i AmacrcrIgTIcg r _; c t
___..__._'ECICIC_ _ _ _ _ _ _ _. _ _. _ _.. _ _ _ _ _ _ _ _ _ _. _.. _. _ _. _. _
g y r o :3 __ >
- p o-,,., ; 17
,r 91R0rn[A
._0 6./ 0 w 10 c "n c u n e.
ANSWER J.07 (2.00)
The pertial element will be replaced by an experimental +uel element with the m a x i na.i m number of fuel pletes removed.
Fuel plates will be added to the element, one at a time, and rod positions and shutdown margin checked after tha addition of each fuel plate until the maximum excess reactivity is achi.eved without exceeding t h.-
shutdoun margin requirements.
REFERENCE UVA:
C A') ALIER SO' 5-1 s.h A '.' C l! E R J.00 p
4.CL C'tE-9o..-
,-.a..
.1 t.
_ i n i,- c.
- r. m t+
n
.u u.
o
_m M 9 6,4 M 4
! ! ' ' ' ~'
C--
3i ef
' I -i ~' : d 1 -- t n. ~-
$ ] -- '" r n4 M_
J
- ^
REFERENCE UvA:
CAVAlI"? SAR 5-4.d A N n t'C R J.0?
(.50)
Meat Enchanger Radiation Zone Entev REFERENCE U t/ A :
UVAR SOP 11-4 AN09ER J: 10 (1.50)
Magnet Engaged Lites.
- OUT h tin 3 Lite
- OM Reector Pooer
- DECREASE l
l REFERENCE U ') A
Power Range Channel 5% (100 kN) below the pouer level i rid i c a t e d by the Core Differential Temperature.
i l
I l
E O
l l
1 T. p. t r, c '. >. t, r. c, C_ T '_.. T_ "; ', T. r_ n_
i,
~p. e_ r _T c.r. "
n.
c re.4
' " r_
,,t c
s y,g ym p g n,q g :m - v y 9:
i - ; o m ; q c3
. g (, f 9 5,
n.. n.. O r n ;. p. "
t
{
t o.cr re_fv e t.M.' A UVAR SOP 1-7 I
i
K, r '. ! E '- 'i A N 0'_ IiiC M8D COPL A M MET C P"
,sp 'me5
-- OH rtf ro0 TT Y f!E 'JIPCINIA
- 52 4 / 0 5 /1 '2 - 0 " 0 0' Ha', i' A M '31' E %
M.01 (1.00)
C REFERENCE UVA! U L,' A R S OP 7-10 ITS allous 15 norths)
ANSilER K.02
( 1. 5 0.'
1)
No crack greater than 1/4" in length.
2)
No obvious deterioration.
3)
Able to pass a 1"
feeler gaisge freely over the rod.
(0.5 each)
REFERENCE UVA:
6 M.
FUEL 'lANDLING AND CORE PARAMETERS
? AGE 35 ANSWERS -- UNIVERSITY Of VIRGINIA
-86/05/13-BRUCMMAN, K.
ANSWER K.03 (2.00) 1 a.
Calculate 1/M after each loading for the Rods Out Data Number of Elements CPS 1/M l
0 20 1.00 4
27 0.80 6
32 0.69 8
40 0.50 10 53 0.38 12 79 0.25 (0.5)
Plot 1/M vs. 4 of Fuel Elementsi Extrapolate the graph to 1/M 0.00;
=
You will get 16 Elements needed to go critical.
(1.0) b.
Using the Rods Out Data, choose any two points and construct the mathematical analogy to predict criticality.
e.g.r If 0 Elements and 8 Elements were chosen 1.00 / 0.50 -> N 16 for Criticality (0.5)
N/8 =
=
REFERENCE UVA:
UVAR SOP 5 ANSWER K.04 12.50) a.
4 b.
1 c.
1 & 2 d.
2 &3 e.
1r 2r & 3 (0.5 each)
4 M
d K.
FUC_ HAMOLitir, AHO CORE AP AHE T E ^:S
'Ari a.,
A tl S W C ri 'i - -- t J M I'J E o S I T 0F VI'?GIk!IA
-06/05/t:' - O C 5' M A N. n RECERENCE UVA: UVAR CAR-pp 2/26/22 - 30 ANSWER 4.05 (2.50) a.
This ensures that the reactor will not go critical when pulling shim rods two et a time during a reactor startup.
(1.0) b.
Nate of the Senior Operator in charge All operations and manipulations Fi..ie l e ' e m e n t numbers and storage locations (0.5 each)
REFE?ENCE UVA:
iluAR sort pp "5 9/10 5 ic ANGWER l'.n6 (1.00) c REFERE!!CE Cense 41 Physics. HT & FF, pp. 239 and 240 4 N M!ER K. 0 -'
(1.60)
^
b P EFE R EiJC E
- )! r,P r Training Textr Vol.
9, p.
21-17 AtlSWER K.09 (1.00) d REFERENCE NC3Ur Ops Manual, p.
3-36 UVA:
TS 3.1(1)
K, CUEL M ANDL ENG AND CORE P AR:'"hE1GS
' Ai;C 3:
I MG 4ERS -- UM E9C93ITY OF UlRGI!iln
- 8 6 / 01" ' E O QMAN-K ANS4ER K.09 (1.00) d REFEPENCE NUS, Vol 4,
pp 3,3-2 Turkey Pointe Thermal-Hydraulic Pr'nciples and Applications, pp. 13 20 i
ANSWER K.10 (1.50) 1.
Fuel actembly in transit stored in recorded location (0.5) 2.
Fuel hsndling tool disconnected from fuel (0,5) 3.
Evacuate Recetor Bay (0.5)
- CAF -
REFERENCE NSCU, Special Procedure 3.2, p.
1 UVAt CAF ANSHER K.11 (1.00) 1 ifeff less than 0.7 (0.5) 2.
Temperature less than 100 degrees C (0.5)
REFERENCE UVA; UVAR TS, S.3 ANSWER K 12
( 1. '5 0 )
Bridge Radiation Monitor Core Gamma Monitor Reactor Room Continuous Air Monitor'(CAM)
(0.5 each)
REFERENCE UVA:
i m
vm-w w
p.
3
-y-.---
7
j'
+c cyEL M ANnLFm ^ 'iD C O R E P A A"'. r g
p3gt y
A stEcc.- y u r.u.-
- i < '. Op u1RCIFIA
-86/05/13-OROCMHAHr K; ANS4ER K.13 (1.00)
The CIC is needed to compensate for background and decay sammas which can distort indications at louer Power levels; the IC does not discrim-inete for gammas, since at higher power levels the gamma signal is proportional to neutton pouer.
(AlSo, the direct umma sigreal is used in lieu of conducting reactor heat belances).
REFERENCE Detector Theory UVA:
U'/ AR SDP 7-3 : CAVALIER SAR 4.3.4.4-ANSWER K.14 (1,00) 1)
Change in core corif igur a tion is made.
2) 1200 MW-br since the last calibration.
(0.5 each)
REFERENCE UVA: UVAR GOP 7-4 ANSWER K.15 (1.00)
Remove at least four (4) Fuel Elements (0.5) from near the center of the core (0.5).
REFERENCE UVA:
e J
i a
5 L.
A0hlNISTRATIuE PROCEDURES. COHOETIONS AND LIMI'ATIONS
' ACE 30 A N S'E RG -- U M PJ E""311 ( OF "lCGINIA
-06/05 't 3-E 00C Knws. e ANSWER L.01 (1.50) 1)
Solution volume greeter than 24 gallons 2)
Boron Concentration greater than 0.129 lbm/ gal 3)
ARIS injection valve un' locked (0.5 each)
REFERENCE UVA:
ANSWER L.02 (2.00) 1)
Hydraulic 2)
Pneumatic 3)
Ovoyant.
J 1)
Other forces normal to the operating environe.ent 5)
Forces that can arise from credible malfunctions (4 9 0.5 each)
REFE9ENCE U ',' A UVAR TG, Definitions i
ANS9ER L.03 (3.50)
S:e Attached Curve cn the Next Page I
PEF 5ENCE l
UVA:
UVAR TS 2 1.2, Fi3ure 2.1 3
AusgEq L,o;
<1,00) d REFERENCE UUA:
I
}
d
. _ - - _ _.., ~ -,, _ - _ -..,, _
,,_._____,.,-.._.........J.
v L.
ADMlHISTRAFIVE PROCCDUM 4i C u a '> I r l. 3 m,n.;4 g 3 '_ c ; i c pg g ;.
- n ANSWERS -- UNIVERSITY O! 1! R Cli t1 A
- C / ' O i '.
W' C 'J % N -
ANSWER L.05 s1 00e n.
TRUE (0.5) 6.
TRUE (0.5)
REFERENCE 10CFR55.41 and 10CF?55 31(e)
ANSWER L.06 (1.50) 1.
DSRO (or RO) (0.3) - At the Facility (0.2) 2.
SPD (0.3) - On Cell (0.2) 3.
Anybody Else (0.3) - At the facility (0.2)
REFERENCE UVA: UVAR TG 6.1 ANStiCR L.07 (1.00)
Minor means that the original intent of the procedure is not changed (0.3).
The change can be approved by the c acility Director (0.3),
'n u s t be documented (0.2) and revieued by the Reactor Gafety Ccomittee (0.2).
REF ERElJCE UVA:
UVAR and CAVALIEP TS 6.3 ApgtsEP L,00 (1.00)
This.n a determined by the gnma radiation level above the Moderator Tank being minimel (
mR/ht) and the neutron level being nagligibler in those areas accessi.ble to personnel.
Ilhis u3s bssed on calculations and measurements,i REFERCHCE OVA
- CAVALIER SARr Sectico 3.2.3 i
_~.,
--- - - - ~ -
L, c.3 W I ! 5 1 R J,1 E U E V:O C d 9 W "J. C0dDITIOrC M D ! 1:* 1 '
U: c.
's.
4*-
MSWERS -- UNIVCQGITY OF v ? P1; i o r A
-r;4 / 0'3 /12 - n Oc'(w!,
V.
ANBt!ER L,OC (21 00)
People desiring entry into the reactor room who are not authorized I
to know the lock combination will require the assistance of someone authorized to know it.
This authorized person is responsible for obtaining the identity of the person desiring entry, determining that tlicy have a need to enter, and, if the identity of the person desiring entry is not known, searching any packages being taken into the reactor room and ensuring that he/she is escorted while in the reactor room.
d P acl< ages car r ied by visitor s which are larger than small hand carried i t e n. s will normally be left outside of the reactor room.
REFERENCE UVA:
UVAR SOP 13.3.2 ANSWER L.10 (1.00) b REFERENCE UVA:
UVAR TS, Definitions ANSWER L.11 (2.00) a.
. Reactor Thermal Power (0,5); 750 kWt (0.5) b.
Reactor Coolant Inlet Temperature (0.5); 111 des F (0.5)
REFERENCE UVA*
UVAR TS 2.1 ANSWER L.12 (1.50) a.
Controlling device (s) secured (0.5) and Danger Tagged (0.5),
b.
Person familiar with the maintenance and the danger asscoiated with it. (0.5)
~
REFERENCE UVA:
h
=
~
A9cENESTRAIIuE PPOCEDU U.91110 3.e r i O..i eAGL c
___ _____ __' __'_'.ciE0HS t,N'3 9 E R S - - U N [w:. R 3 L T v 0~ Ut-.:141 A
- 0 ' ' )'
/ t J 9,'O r MN. U ANSWER L.13 (1.50) 1)
Individual designated and DSRO informed.
2)
DSR0 Fept informed on the pertons location and Phone Number.
3)
Capability of getting to the facility in a reasonable amount of time
(~
30 minutes).
(0.5 each)
":EFERENCE UVA*
UVAR TSr Definitions a
i e
}
]
./ 3.T Tc79 9
I
{
D) s l
Ws)
L 119' Above Coreh,5, 5
T i Ill'F
, f) g y
4 4
hIo 3
~
r ui 1
l h-T)
Region to the left of 400 GPM applies only during loss of flow transient.
g2 "o
l M.5 A'G CQ.r) 0 izb0
=
a ghD 1000 g
ZOO 400 600 Reactor Coolant Flow Rate. W.
i Figure 2.1 safety limits' with forced convection flow I
i
3 100% -
a)
[Xe]eq (1.0) l I
I f
1 1
0 10 20 30 40 50 60 Time (Hrs) 125% -
b) 100% -
75%
(1.5)
[Xe]eq f
f t
f f
I I
f 0
10 20 30 40 50 60 70 Time (Hrs)
Ref:
DPC pp 161-164 NUS Module 3, pp 10.2-2/3, 10. 3-1/3 l
l l
. c4 T r e. T E R G ", '; C '. ' ' E " E d U_
1 rn'E9' rnn' t.'
t.i E
- EreqE1:c
!1,01 an v ': n000690 io m n000691 p,07 11. 0 3 2 50 ME200006?2 H 04 3.00 KE80000693 H.05 1.00 KEB0000/t2 M1 06 1.00 KEB0000713 H.07 1.00 V E.800 0 0 714 H.00 1.00 t!E80000715 11.00 1 00 KEB00007L6 H.10 1.00 VED0000717 H.11 1 00 KEB0000710 H.12 1.50 KED0000719 H.13 2.30
200000720 H.14 1.50 KLB0000721 19.50 I.01 1.00 KEB00006(74 1.02 1.00 KEE.0000695 I.03 2.50 KED0000606 1.04 2.00 l'EB0000697 I 05 2.00 KEB000069tt 1.06 1.00 KED0000/22 I.07 1+00 ML0000/23 I.00 1.00 KEB0000724 I.09 2,00 MED0000726 1.10 1.50 UEB0000727 I 11 1.90 KE00000/20 1.12 1 50 REB 0000729 I 13 00 V5U0000730 f<td 1.00
% 0000074?
I'0,50 J.01 4.00 KEB0000699 J.02 1.00 KE80000700 J.03 3.00 KEB000070t J.04 1.50 ME80000702 J.05 2.00 MEB00007~1t J.06 1.00 VE90000743 J.07 2.00 KED0000744 J.08 1.00 KE80000745 J.09
.50 KEB0000746 J.10 1 50 KEB0000747 J.11 1.00 MEB0000748 10.50 K.01 1.00 KEB0000703 K.02 1.50 KEB0000704
e we e
i l
T 1, 'f { 1] i:' Q C; y RF l_.' t,. 3 i' '
' ' 41,
(
3TE nUEST10ti t'OL UF r; i K 03 2 ' 0
' a " 0 0 :' 0 5 l'.
04 i:.50
'L.200007'M K.05 2.50
E 3 00 0 0 / 07 K.06 1.00 K E D 00007'33 K.07 1.00 K E B 0 000 ;' 31 l
K.00 1.00 ME80000735
(
K 09 1.00 KEB0000716 K.10 1.50 l'E 8 00007 3 7 K.11 1.00 M E B 00 001'10 K.12 1.50 MEB0000730 K.13 1.00 M E B 0 0 0 0 7 <' 9 K.14 1.00 KEB0000757 K.15 1.00 KEB0000758 20.50 L.01 1.50 UE80000708 L.02 2.00 K 00060700 L.03 3.50 MEB0000710 L.04 1.00 KEB00007tL L.05 1 00 KEB0000740 L.06 1.50 UEB0000711 L4 07 1.00 KEB0000750
._,08 1,00 KE00000751 l.09 2.00 t'..~.r.00007'i2 L.10 1.00
' E00000/'il L.11 2.00 KE00000/54 L,12 1 -10
" E E'0 0 0 0 l'i 5 L.13 1.50 K: 30000756 a.
k 4
Wea.eeug.e o9.50 1
-