IR 05000057/1988001
| ML20148M729 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 03/24/1988 |
| From: | Eselgroth P, Norris B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20148M717 | List: |
| References | |
| 50-057-88-01OL, 50-57-88-1OL, NUDOCS 8804060103 | |
| Download: ML20148M729 (60) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N /83-01(0L)
FACILITY DOCKET N FACILITY LICENSE N R-77 LICENSEE: State University of New York at Buffalo Rotary Road Buffalo, New York 14214 FACILITY: Buffalo Materials Research Center EXAMINATION DATES: February 9 and 10, 1988 CHIEF EXAMINER: // Yo Barfy S' tfp ris JJ V/at W Date Senior Operations Engineer APPROVED BY: 74 3 '2N~ N Peter W. Eselgfoth, Chief Date PWRSection,6OperationsBranch Division of Reactor Safety, Region I SUMMARY: Written and operating examinations were administered to two Reactor >
Operator (RO) candidates. Both candidates passed these examination lF3'880328 PDR ADOCK 05000057 M _ f5MBL
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REPORT DETAILS TYPE OF EXAMINATIONS: Replacement EXAMINATION RESULTS:
l R0 l l Pass / Fail l I l 1 1 I l Written i 2/0 l l l l l l l 10perating l 2/0 l 1 I I I I l l0verall l 2/0 I I l I CHIEF EXAMINER AT SITE: B. S. Norris, USNRC OTHER EXAMINERS: 0. B. Jarrell, PNL The following is a summary of generic deficiencies noted during the operating examinations. This informatior, is being provided to aid the licensee in upgrading license and requalification training programs. No licensee response is require Both candidates were weak with respect to evacuation procedures for a fire or radiological proble Both candidates were weak on radiation detector operation and on calculations for shielding and distance from a radiation sourc . The written examination questions and answer key were reviewed by L. G. Henry and P. M. Orlosky of your staff. The facility comments and the NRC resolution of those comments is enclose Attachments: R0 Written Examination and Answer Key Facility Comments on Written Examinations and NRC Resolution i
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U. S. HUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION l
i FACILITY: STATE UNIV. OF NEW YORK REACTOR TYPE: TEST i
DATE ADMINISTERED: 88/02/09 EXAMINER:
JARRELL, ANSWER KEY CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Write answers on one side onl . Use separate paper for the answer Points for each Staple question sheet on top of the answer sheet The passing question are indicated in parentheses after the question. Examination papers will grade requires at least 70% in each categor be picked up six (6) hours after the examination start % OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE CATEGORY VALUE_ TOTAL SCORE
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15.*N , PRINCIPLES OF REACTOR OPERATION 15.00 FEATURES OF FACILITY DESIGN 15.00 15.*N * _
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14.N Y GENERAL OPERATING CHARACTERISTICS 14,o* 1 4 .21 INSTRUMENTS AND CONTROLS 4&Mt_ E6_0 7 1/
13.'M 7 SAFETY AND EMERGENCY SYSTEMS 13.50 1/
13.60' STANDARD AND EMERGENCY OPERATING 13.50 PROCEDURES
,7/ ~ RADIATIONCONTROLANp. SAFETY 13.50 13.507
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Totals
.' .... Final Grade
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I have neither given All work done on this examination is my ow nor received ai A WA MM" '
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Candidate's Signature
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: Cheating on the examination means an automatic denial of your application and could result in more severe penalties, l 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 cheatin . Use black ink or dark pencil only to facilitate legible reproduction . Print your name in the blank provided on the cover sheet of the examinatio . Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answer . Print your name in the upper right-hand corner of the first page of each section of the answer shee . Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only o_n one side of the paper, and write "Last Page" on the last answer shee . Number each answer as to category and number, for example,1.4, 6.3.
( 10. Skip at least three lines between each answe . Separate answer sheets from pad and place finished answer sheets face down on your desk or tabl . Use abbreviations only if they are commonly used in facility literatur . 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 require . Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or no J'
15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE ~
, UESTION Q AND DO NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of the examiner onl . 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 complete _ _-- - - - _ . - . _
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18. When you complete your examination, you shall:
a. Assemble your examination as follows:
(1) Exam questions on to (2) Exam aids - figures, tables, et (3) Answer pages including figures which are part of the answe b. Turn in your copy of the examination and all pages used to answer the examination question c. Turn in all scrap paper and the balance of the paper that you did not use for answering the question '
d. Leave the examination area, as defined by the examine If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoke .
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. PRINCIPLES OF REACTOR OPERATION PAGE 2
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QUESTION A.01 (2.00)
On the curve of heat flux density versus temperature difference shown below, LABEL each of the four (4) indicated segments of the curve with its associated heat transfer regim (1.0) LABEL the point of DNB (departure from nucleate boiling). (0.5) INDICATE the portion of the curve where the SUNYAB reactor is allowed by Tech Specs to operat (0.5)
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, wall saturation QUESTION A.02 (2.00)- r Fuel assemblies are shuffled to move some of the peripheral ~
assemblies to the center and the central assemblies to the
' peri )hery. Assuming that only original fuel elements remain in t1e core, and no net fuel addition or subtraction took place, WOULO it be safe to assume that no change in core excess reactivity took place? EXPLAI (2.0)
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, PRINCIPLES OF REACTOR OPERATION PAGE 3
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QUESTION A.03 (1.00)
WHAT is responsible for the shape of a centrol rod's differential reactivity worth curve? (1.0)
QUESTION A.04 (2.50)
With the reactor operating at 2 MW, a moveable experiment with a positive reactivity worth equal to the maximum allowable is suddenly placed next to the core. Assuming that rho = 0.091/
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tau WHAT is the minimum period possible? (1.0) WOULD any automatic actions occur, and if so, WHEN relative to the insertion? (1.5)
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QUESTION A.05 ( gg WHAT is rod shadowin g (0.5) WHAT is its potential significance to reactor safety? (0.5) WHAT immediately available instrumentation can be used to verify a suspected shadowing problem and WHY is it reliable? (1,0)
! QUESTION A.06 (1.50)
i With increasing.burnup, the amount of avaflable U**235 l decreases and the Pu**239 content in the core increase r l Knowing that the delayed fraction for Pu**239 is approximately '
0.0021, WOULD you expect the reactor transient response time i 70 a given positive reactivity step to increase or decrease l from BOL to E0L and WHY7 (1.5)
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l QUESTION A.07 (2.00)
EXPLAIN the "prompt jump" phenomena resulting from of a small l
( beta) but rapid insertion of reactivit (2.0)
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. PRINCIPLES OF REACTOR OPERATION PAGE 4
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QUESTION A.08 (1.00) /((\,,s
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9 '4 Astrongneutronsource(=IE13n/cm**2/ec)isplaced adjacent to an exactly critical reacto . DESCRIBE (words or a graph) the behavior of the neutron population as a function of tim (1.0)
QUESTION A.09 (1.00)
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A step positive reactivity insertion is imposed on a critical reactor. WHAT is the first mechanism that will turn the power rise and HOW does it work? (1.0)
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. FEATURES OF FACILITY DESIGN PAGE 5
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' QUESTION B.01 (2.00) DRAW a simple cross-section diagram of the reactor including a fuel assembly, core support plate, lower plenum, flapper valve and plenum outlet pip (1.0) SHOW the coolant flow path during forced and natural convectio (1.0)
QUESTION B.02 (2.00)
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WHAT is the minimum number of fuel assemblies necessary to achieve criticality? (0.5) number of assemblies currently installed? (0,5) maximum number of assemblies that could be accommodated (geometrically)? (1.0) WHY are the excess holes plugged? (1.0)
i QUESTION B.03 (1.50)
! WHAT design feature (s) controls the release of Ar-41 from the beam tubes to the environment? HOW7 (1.5)
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QUESTION B.04 (2.00)
r WHAT eight (8) parameters can cause a reactor scram? "
(setpoints are not required) (2.0)
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. FEATURES OF FACILITY DESIGN PAGE 6
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QUESTION B.05 (2.00)
Regarding the purifick. :n system: WHY is the purification system needed? (0.5) WHY is there a filter before and after the resin column? (0.5) If during normal high power operation the demineralizer pump is deenergized, DOES flow through the demin unit cease? WHY7 (1.0)
QUESTION B.06 (1.00)
HOW MANY air subsystems does the facility have, and HOW MANY of these can be cross-connected? (1.0)
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QUESTION B.07 (1.50)
STATE the normal and emergency source of makeup water to the primary AND secondary loops, as appropriate. WHICH are manual and WHICH ere automatic? (1.5)
! QUESTION B.08 (2.00)
l Following a power outage, the motor-generator functions as planned. WHICH of the following equi > ment would still be energized? (ANSWER YES or N0 for eac1.) ,
(2.0) fume hood fans r evacuation alarm horn ' bridge radiation monitor
" reactor console instrumentation l QUESTION B.09 (1.00)
f l WHAT design feature associated with the pneumatic transfer systems
! helps to prevent inadvertent radiation exposure of the transfer system operator? (1.0)
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I 1 GENERAL OPERATING CHARACTERISTICS PAGE 7 ,
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A moveable experiment with a worth of 0.28% delta-k/k is inserted in a single stepwise fashion with the reactor stable at a power level of 100 W. Given no cperator or safety action, DRAW on the graph below the following parameters versus time: moderator temperature recctivity power reactivity power level STATE any assumptions made in drawing your grap (2.5)
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QUESTION C.112 (1.50)
WHAT is the primary (reference) method for determining reactor pover? BRIEFLY EXPLAI (1.5)
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QUESTION C.03 (1.00)
HOW LONG does it take to drive a control-safety rod full stroke?
STATE all assumption (1.0)
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. GENERAL OPERATING CHARACTERISTICS PAGE 8
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QUESTION C.04 (1.00)
WHICH two (2) control blades (by number) have the greatest differential reactivity worth? (1.0)
QUESTION C.05 (1.00)
An IF with a small sample and a voided container is to be loaded into the reactor core. IS it preferable to do this at low (approximately 100 W) power OR high (1.8 HW) power?
EXPLAIN WH (1.0)
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QUESTION C.06 ( . o)
,2.50) Briefly DESCRIBE control rod worth calibration by the Inhour M . W)
metho (.2,4) WHY must the calibration be performed at low power? (0.5)
l QUESTION C.07 (1.00)
A5out HOW long should it take from SCRAM initiation to full insertion of the scramable control blades? (1.0)
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QUESTION C.08 (1.00)
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Approximately WHAT is the combined total worth of all six (6) r control blades? (1.0) .
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QUESTION C.09 (1.00) DOES secondary coolant flow on the shell side or on the tube side of the heat exchanger? . (0.5) DOES primary side pressure ever exceed secondary side pressure in the heat exchanger? (0.5)
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. GENERAL OPERATING CHARACTERISTICS PAGE 9
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QUESTION C.10 (2.00)
A very small sample of low cross section materials is to be exposed in an IF, positioned in an area of maximum flu DESCRIBE the process by which the sample is suspended in the area of peak flu (2.()
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. INSTRUMENTS AND CONTROLS PAGE 10
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QUESTION D.01 (2.50) DRAW the graph of the relationship between the voltage differential across the electrodes of a radiation detection chamber and the log of the resulting charge collection. Be sure to name your axes; numerical values are not require (0.5) NAME and INDICATE the regions where the detectors in your plant operat (0.5) NAME and INDICATE IN WHICH region each of the five channels
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of the NSTF nuclear instrumentation system operate (1.5)
QUESTION D.02 (2.00)
WHICH detector (s) do (does) not have gamma compensation and WHY isn't it necessary for these channels? Give two (2) reasan (2.0)
QUESTION D.03 (1.00)
HOW can you be sure that the startup (log count rate) channel l is really seeing neutrons rather than noise or a test signal? (1.0)
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QUESTION G.94 (2.00)
LIST the control blade withdrawal inhibit signals and WHAT each
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is designed to prevent.- (2.0)
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QUESTION D.05 HOW is the effect of N-16 produced in the prbary coolant eliminated from the beta-gamma monitor? O T^TE .a (2) 1
--th d .) = (1.5)
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. INSTRUMENTS AND CONTROLS PAGE 11
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QUESTION D.06 (2.00) WHAT do the low and high reference voltages correspond to in the rod position indication circuit? (1.0) WHAT does the output of differential voltmeter measure and WHY is it required? (1.0)
QUESTION D.07 (2.00)
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The STATE Reactor Safety)
these two System (2 types provides of SCRAMS, two and (2) the HOW types of SCRAM safety circuit causes each type of SCRA (2.0)
QUESTION D.08 On a loss of commercial power, the emergency motor-generator
functions normall DESCRIBE HOW a) the alarm (s) and b) thefunction(s)
of the facility Engineered Safety Features are affecte .
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. SAFETY AND EMERGENCY SYSTEMS pAGE 12
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QUESTION E.01 (1.00)
WHAT two (2) safety criteria are considered to be a compromise of clad integrity by the Safety Evaluation Report? (1,0)
QUESTION E.02 (1.00)
WHAT two (2) systems are consiaered engineered safety features in the Safety Evaluation Report? (1.0)
a QUESTION E.03 (1.00)
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WHAT mechanical system is the most important to reactor safety (pertheSER)? (1.0)
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QUESTION E.04 (1.50)
WHAT design feature allows operation of ventilation system dampers under power failure conditions? (1.5)
QUESTION E.05 (1.50)
WHATsignalsarenecessarytoactuatethereactorbuilding)
ventilation damper closure system? (setpoints not required (1.5)
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QUESTION E.06 (1.50)
STATE the automatic actions that will occur upon actuation of the reactor building ventilation damper closure syste (1.5)
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. SAFETY AND EMERGENCY SYSTEMS PAGE 13
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QUESTION E.07 (1.50)
STATE the general locations of the fixed area radiation uonitor (1.5)
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QUESTION E.08 (2.50)
STATE the location of five (5) of the nine fire alarm boxe (2.5)
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QUESTION E.09 (2.00)
Drain lines from the containment buildino are constructed with a 24 inch loop seal (dip leg) to maintain containment integriif .
Assuming that due to evaporation only 14 inches of water remained, HOW MUCH internal pressure (in PSIG) would be necessary to cause
"blow-by" of this seal? STATE all assumptions and SHOW all wor (2.0)
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. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 14
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QUESTION F.01 (1.00)
WHAT a e the two (2) immediate operator actions following indica.:ons of an automatic reactor scram? (1.0)
QUESTION F.02 (2.50)
It is a hot Sunday August evening with imminent rain. Your duty is to perform a startup to a power of 2 MW following the reactor being secured at the end of a full-power run the previous Frida PLACE in proper order the following startup steps:
(2.5) energize the secondary circulation pump withdraw the fission counter to its upper limit announce your intention to start up the reactor
, complete and sign the reactor checkout form energize the primary circulation pump position the neutron detectors to the low residual xenon position take the reactor critical and commence the power increase f stabilize the reactor at near full power and approach 2 MW by your most conservative indication
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i adjust the linear-N recorder to correspond to delta-T and N-16 indicators
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10. record the appropriate information and announce the reactor .
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QUESTION F.03 (1.00)
DEFINE the word OPERABLE in a Technical Specification contex (1.0)
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. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 15
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QUESTION F.04 (2.00)
Of the items listed below, WHICH HUST be noted in the Reactor Log? (ANSWERYesorNo) (2.0) changing power from 1.5 MW to 1.7 MW completion of a reactor startup checklist water addition to the reactor pool operator relief to go to the lavatory
" routine transfer of liquid to the 10,000 gal holding tank changing the chart paper in a Log-N chart recorder opening a valve which was previously logged as open a check of the building radiation fields by visiting Russian scientists QUESTION F.05 (2.50)
I You are the reactor operator on backshift with the reactor at full power for isotope production. The fire alarm Klaxon sounds, followed five seconds later by the building air radiation alar WHAT are your five (5) required actions? (2.5) ,
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QUESTION F.06 (2.50)
During normal dayshift operation at 2 MW, a loss-of-flow scram is annunciated, followed by a report from the pump room that the primary pum) casing has disinte WHAT are your immediate '
, actions? (.IST ten (10) items) grate (2.5)
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QUESTION F.07 (1.00)
Do you normally expect high contamination levels in primary coolant? WHY7 Give two (2) reason (1.0)
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QUESTION F.08 (1.00) ,
With reactor power at 1 MW, and a workman troubleshooting the bridge radiation monitor (temporarily removed from service), an experiment is energized which causes a 5% increase in reactor
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power. WHAT action do you take and WHY? (1.0)
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. RADIATION CONTROL AND SAFETY PAGE 17
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QUESTION G.01 (1.00)
With the minimum amount of water covering the core per Tech Specs, WHAT is the neutron flux at the water surface due to attenuation only if you assume one-tenth thickness to be 2 feet of water and neutron flux at the core top to be 10**10 n/sec/cm**27 STATE all assumption (1.0)
QUESTION G.02 (2.00)
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A valve must be repaired in a 1 rem radiation fiel Two alternative methods are to be considered: Two men working on the job can complete it in 45 mi . Placing and removing shielding around the job, a one-man, 40-min. procedure, will reduce the radiation field to 300 mrem /h *
WHICHprocedureisbetterandWHY(stateprincipleinvolved)?
(SHOW all work) (2.0)
QUESTION G.03 (2.00)
During full power operation, a fuel pin fails and releases l several curies of radioactivity into the pool water. Assuming that this contamination was restricted to liquid form, WHAT '
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systems (subsystems) are in ) lace to warn or protect the reactor staff and general pu)1ic from radiation dangers?
NAMEatleastfour.(4). (2.0) i r
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' RADIATION CONTROL AND SAFETY PAGE 18
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QUESTION G.04 (2.00)
An undergraduate student is working in the dry irradiation chamber when the reactor is operating. The following radiation fields exist:
gamma radiation - 200 rad beta radiation - 50 rad thermal neutrons - 800 rad If his job lasts for 15 min, WHAT would be the total radiation dose in rem? WHAT are his chances for survival (better or worse
, than50/30)? (2.0)
QUESTION G.05 (2.50)
An undergraduate student, hurrying to finish his experiment, trips while running across the reactor bay and the shielded flask containing 0.5 Ci of radioactive liquid that he was
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carrying runs into the floor drai WHERE does the liquid go from there? (0.5) WHAT detection and hold-up barriers lie between the spill and its release from the facility? (1. 5)' If release limits are met, HOW does it leave the site boundary? (0.5)
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QUESTION .G.06 (2.00)_
A 3 Ci point source of Co60 is 21 ft from man A and 24 ft from/ man
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B. Han A, however, has positioned one HVL of lead between himself '
and the source. WHICH man is receiving the greater dose rate?
-STATE all assumptions and SHOW all wor (2.0)
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. RADIATION CONTROL AND SAFETY PAGE 19
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f QUESTION G.07 (2.00)
FILL in the table below with Federal Exposure Limit values for radiation workers (2.0)
- rem per calendar quarter
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Quarterly Quarterly Average Maximum
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Extremities X
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IMPORTANT MAlllDIATICAL RELATIONSilIPS
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The following equations may appear on a reactor operator's examinatio I In the pages that follow, a brief explanation of each equation is give .
, dji = -AN S.U.R. - 26/t dt L
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Ng = N,e IIVL = 0.693/p
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t is = 0.693/A N = S/1-K,gg A = AN P = P,c b
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rate g 1Ati
1d1 1 2"Id22 2
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R/hr 9 1 foot = 6 CE l
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(The important equations are boxed in the following explanations).
Since there are many R.P.D. equations, that part of th(s matefial is sectioned according to topic, i .
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- _ _ .
__
. - . - . - - - - . _ _ _ _ _ _ _ _ _ _ - -
A & -
.
. PRINCIPLES OF REACTOR OPERATION PAGE 20
'
AN,5WERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER A.01 (2.00)
!
l
[ (5)
l I
~
l l l
! l in Q l 4-- (1) -- +I p---(4)----
! ----(3)-----d
! k- ( 2) ---
i I I in (T -T )
i-- . wall saturation _._ ._ _ ._.. .. The segments are:
1. (natural) convection [+0.25]
2. j r 'r t: boiling transition boiling [+0.25] +0.25 ] film boiling [+0.25.J: 1 (5) point of DNB [+0.5]
' Region 1 is the allowable operating segment [+0.5] -
REFERENCE - SUNY: Training Outline Definition . SUNY: Technical Specifications, p. 5.
- _ - - . . . . - - - , ..- - , . . . _ _ _ _ - . - . - . . _ _ . _ - . - , _ _ _ _ _ . . - - _ . _ - _ _ . _ ~ _ _ _
,.
.
. PRINCIPLES OF REACTOR OPEPATION PAGE 21
'
AN,5WERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER A.02 (2.00)
No [+0.5] . Moving the fuel elements around might significantly affect core excess reactivity [+0.5]. This is because there may have been a net change in the macroscopic cross section for uranium, i.e., net fuel may have been shifted toward or away from regions of higher potential neutron flux [+1.0].
REFERENCE SUNY: OP No. 4, p. ANSWER A.03 (1.00)
The shape of the (local) axial neutron flux [+1.0].
(Discussion of reaction rate; rate = flux x cross section x number
,
density)
REFERENCE SUNY: Handouts, ANL 7291, p. 38 r
.
h I
. . .
.
.
.
. PRINCIPLES OF REACTOR OPERATION PAGE 22
'
AN,5WERS -- STATE UNIV. OF NEW Y0k.'.
-88/02/09-JARRELL, ANSWER A.04 (2.50) , rho 0.091/ tau => tau = 0.091/ rho and per Tech Specs, rho = 0.003 delta-k/k [+0.5] for a moveable experiment max Then tau = 0.091/0.003 which is approximately equal to 30 sec. period [+0. 5] . Yes [+0.5], scram setpoint is 2.4 MW and assuming no
'
temperature coefficient effects, the time to reactor scram would be P = P e**t/ tau [+0.5) P/P = 2.4/2.0 = exp (t/30s)
o o in 1.2 = t/30s 30(0.182)=t t = 5.47 sec [+0.5] (accept 5.5+-0.5 seconds)
REFERENCE SUNY: Technical Specifications, pp. 6 and . SUNY: Training Outline, Equations, pp. 11 and ANSWER A.05 (2.00) A local suppression of neutron flux incident on an ion chamber
[+0. 5] . It causes the shadowed chamber to read low relative to true '
.
,
thermal power [+0.5]. <
%
- % Two temperature channels (core delta T and primary temp) r
-
[+0.25] and the N-16 channel [+0.25] can be used since they are not directly dependent on neutron , level [+0.5]. h.) *[/
+
f('YN#, pf REFERENCE g / d SUNY: Tech Specs, p. 2 t
,.
_
.
. , PRINCIPLESOFREACTOROPERATIM PAGE 23
'
AN,5WERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER A.06 (1.50)
Decrease [+0.5]. Since the effective delayed neutron fraction is decreased, the time one must wait for completion of the previous neutron generation has decreased (smaller mean generation time),
yielding a quicker response time. (Alternatively,showingthatthe right hand term of the in-hour equation becomes less effective in determining reactivity response is acceptable.) [+1.0]
REFERENCE SUNY: Handouts, ANL 6701, Section 1.1 . SUNY: Training Outline, Equations, p. 1 . SUNY: Handouts, Physics, p. III-16-1 '
ANSWER A.07 (2.00)
Following a small rapid reactivity insertion, the fission rate increases generating additional prompt neutrons, and causing the reaction rate to begin to increase (diverge) on prompt neutrons alone[+1.0]. Since the system is actually suberitical on prompt neutrons [+0.5], it must wait for the delayed neutron groups to contribute their necessary fraction to continue the power rise
[+0.5].
REFERENCE SUNY: Handouts, Physics, p. III-1 . Lamarsh, J. R.,.."Introduction to Nuclear Reactor Theory,"
p. 42 r
.
_ _ ______ ______ ________ . PRINCIPLES OF REACTOR OPERATION PAGE 24
'
AN5WERS -- STATE UNIV. OF NEW YORK
,
-88/02/09-JARRELL, ANSWER A.08 (1.00)
Theneutronpopulationwillincrease[+0.5)inalinearfashion with time [+0.5] (the rate of increase is dependent on the source strength). # t: rut-'y (W = S*1/1 E:ff)
'
e
'
-
Nedron P,pdahm, H-
-
-. t ; ,n a _ y
--
REFERENCE
- SUNY: ANL-6701, "Approach to Critical,' p. 1 . ' M f'
, ed ANSWER A.09 (1.00) gg ie' g gS st ei The first (and only) mechanism will be the doppler or fuel \ ev8- t#Yd J I
I l
temperaturecoefficient[+0.5]. By increasing the temperature of the fuel, the resonance abso tion peaks are effective over a energy range (broadened) resu ting in a larger macroscopic
- g,e wider, # / ic ar df y/
,s
.
absorption cross section and hence resulting in a negative 4Ap s f)il reactivity effect [+0.5].
' p, r * * ,,3Qt( i**4
.
(Discussions of resonance escape probability would be acceptable.) [4' pN i REFERENCE y 4 ..g
' SUNY: Handouts, Physics, p. III-31, four factor formula, ps \ 3, te p
,
.. . --
..
. . .
.
..
. . _ . .
.
. FEATURES OF FACILITY DESIGN PAGE 25
ANSWERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, B.01 (2.00)
a / h /c d~
ANSWER
, prmde/ by h"UN
'
a-/kcW: fy A@
fue7eln --
A N
,fu l ass enebjy
'
, g e:Y
- '
Lh sturf cir u t.'eu (<*r c WPO)
t hsopecore r t Plate
- -
qrleru m
'
l
,
d
-
I f
he I assemb Y Fo r < e <l I
j ,
c b 46er w tLP
K ' cl'73:3 *~"*" m >
cJ++ d
/ foo r
..e
/ s L> ate P a %2-Grading: [+0.2) each for each cross-section element [+0.5] for each correct flow path REFERENCE SUNY: SER, pp. 4-16, 4- ,.
=
,. .
,.
d'~<-
hit e
'
I"*Y rr/o y r .re ,.e g o, l er~.b} olra w . .,c7
.
&c;h ly /t r/ss W/
t 60l
.-
'
Qb $hf
'
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.
.
Q, -
,_
rg> -
/
, ,
&& Q ,
-
uwc \\
< \\ J
..c,.,- -.
__
__
j
,
_ _ _ _
. FEATURES OF FACILITY DESIGN PAGE 26
'
AN,5WERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER B.02 (2.00) [+0.5] [+0.5) [+0.5] holes are plugged to confine coolant flow to core assemblies and experiment positions [+0.5]
'
REFERENCE SUNY: SER, pp. 4-2, 4- . SUNY: Handouts; Reactivity Sumary, Loading #14 ANSWER B.03 (1.50)
.
The ventilation system [+0.5] maintains the beam tubes under a slight negative pressure [+0.5] exhausting (through a filter) to the exhaust stack [+0.5].
REFERENCE SUNY: SF.R. p. 10- ANSWER B.04 (2.00) high reactor powe .
" low coolant flow low pool water level r flasper valve open ~ higt >ool/ core inlet temperature . dry lossctamber of safety door not high chamber fully voltage closed (#~(limit switch) h
[/hre operator (manual)
[+0.25] each REFERENCE SUN',' SER, p. 4-1 .
_-_____-_- __ ________-_ _________ __ __ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
. FEATURES OF FACILITY DESIGN PAGE 27
'
AN,5WERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER 8.05 (2.00) Minimize contamination (due to corrosion products and foreign matter) in the reactor pool [+0.5]. The inlet filter removes large debris prior to the demin bed preventing clogging; the outlet filter prevents possible resin discharge to the reactor pool [+0.5]. No [+0.5]; primary coolant pump pressure drop causes (about a
,
6gpm)flowthroughthedemineralizer[+0.5].
REFERENCE SUNY: OP-24, p. 1, System Prin . SUNY: OP-21, System Prin B.06
'
ANSWER (1.00)
three(3)][+0.5]
all [+ REFERENCE SUNi: SER, p. 9- ANSWER B.07 (1.50) cS
'
Primary normal - demin water ank, manual [+0.5]
emergency - city wa r, manual [+0.5] r Secondary ' *
normal - city water, automatic [+0.5]
(emergency - none)
REFERENCE SUNY: SER, pp. 5-4, 5-2, 6- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
. FEATURES OF FACILITY DESIGN PAGE 28
'
ANSWERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER B.08 (2.00) No Yes Yes No
[+0.5] each REFERENCE
' SUNY: SER, p. 8- ANSWER B.09 (1.00)
The transfer systems are equipped with shielded containers for
--
receiving irradiated specimens. [+1.0]
' '
REFERENCE SUNY: SER, NUREG-0982, p. 10- !
,
-
,
)*
l .
m 1.
I
,
'
I l
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
. GENERAL OPERATING CHARACTERISTICS PAGE 29
.
AKSWERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, od f I MA f0
- 4pr ANSWER C 01 (2.50)
'
. P*"*!
4 -
j 6p.;m e,$
a..d:ey ,
[~ ( _ ___ .__ 2
,
/
-
u.,
Read;M # p, d e a a+o e pna ,.
q b} #'" (MW)
O s b n - - -l 'm
, l ' :W+y y s1.M . - -
~ -
' . .
,y .
N ,._ -
'
.s
_. h O f;me m - _ _ _ . . _ . -
Key assumptions: power defect = 0.35% deltt k/k fo; 2 MW change [+0.25] temperature reactivity is approximately equal to 0 [+0.25]
Grading Key POWER REACTIVITY - starts at approximately 0 (-0.017% delta-k/k)j+0.5]andwindsupcompensatingforthe0.28% insertion
[+0 . 5, POWER - starts at 100 W (approximately 0), overshoots [+0.5],
then returns to slightly less than 2 MW [+0.5].
(2 MW/0.35% delta k/k * 0.3% delta k/k + 0.1 MW = 1.8 MW final power)
r REFERENCE , SUNY: SER, p. 4- . Telecon with P. Orlosky on 1/15/88 (clarification of SER values),
i l
l
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
.
. GENERAL OPERATING CHARACTERISTICS PAGE 30 .
t
'
AN,5WERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER C.02 (1.50)
Calorimetric on reactor primary coolant flow [+0.5]. Basically a heat balance on temperature rise of a known flow media using Power = mCp (delta-T) [+1.0] .
>
REFERENCE SUNY: OP-6, p. , SUNY: OP-78, p.1.
'
ANSWER C.03 (1.00)
Rod speed is 3 in./ min [+0.3] and full stroke is 26 in. [+0.3]
therefore stroke travel time is 8.7 min [+0.4].
REFERENCE
, SUNY: Technical Specifications, p. 27.
t
! ANSWER C.04 (1.00)
! ' blade blade 4 3[+ [+0.5]]
REFERENCE ! SUNY: Reactivity Loading Report #14 ' .
, ,,
ANSWER C.05 (1.00)
l ,
migh power [+0.5];
to counteract doppler reactivity the expected positivewill be immediately]available
- reactivity [+0.5 .
REFERENCE i SUNY: OP-49, p. 4.
,
l
,
l I
- _ . - , _ . . . _ . -_ _ _ _ . - _ _ _ . _ - - _ _ _ _ _ ,
- _ - - - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
'
. GENERAL OPERATING CHARACTERISTICS PAGE 31
'
AN,5WERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, .00 ANSWER C.06 43,007 Attain a low power, stable critical position, then withdraw the rod to be measured to achieve a slow (long; approximately 30 sec) period [+0.5]. Measure the time it takes power to change a specific amount [+0.5]. By recording the new position of the rod being calibrated (and relating that to the period produced, (seriod = power change /2.3), then reactivity .M
'
canbereadfromtiedecadetimeversus%(,deltak/kplot(orThe calculated from Inhour equation) [+0.5].
inch of rod travel for the entire rod can be determined from a piIg#j#
% delta k/k M* 6 8 per
'
sequence of measurements [+0.5].) W To avoid temperature effects [+0.5].
REFERENCE SUNY: OP-61, pp. 1 and ANSWER C.07 (1.00)
lessthanonesecond(0.65 seconds) [+1.0]
REFERENCE SUNY: SER, NUREG-0982, p. 4- ANSWER C.08 (1.00)
10%deltak/k-(9.932deltak/k) [+1.0]
REFERENCE r
' SUNY: Reactivity loading report, No. 14 ANSWER C.09 (1.00) tube side yes [+0.5][+0.5]
REFERENCE SUNY: SER, NUREG-0982, p. 5- .
_ ______________ _-__ ______-__ _ _ _ _ _ _ _ _ _
.
'
. GENERAL OPERATING CHARACTERISTICS PAGE 32
'
ANSWERS -- STATE UN!Y. OF NEW YORK -88/02/09 JARRELL, l
'
ANSWER C.10 (2.00)
The sample will exhibit sositive reactivit Reactor power should i
beloweredbyabout20%seforeinsertion(+0.5]. During insertion the power will increase, being compensated for by Doppler, so no rod motion should be necessary [+0.5]. As the If presses through the peak flux, power will start to dro) (+0.5]. The IF is then
.
pulled back through and suspended at t1e position corresponding to 1 the highest power level on the chart recorder [+0.5].
REFERENCE
,
, SUNY: OP 49, p. 3.
Y e
e
I
,
i -
Y
, .
b i
^
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
..
, .
, INSTRUMENTS AND CONTROLS PAGE 33
.
AN,5WERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER 0.01 (2.50)
4.), b)
'
(Conk s' M vou f l dhclona)
( f% podien I I
,
4,1 l R eq lo ")
Chsq e l Ge.,9 e e -
C* IIIi$t To n MuIIe e l I R a<jio n claa d e e R ecti o n l (, 2 gj
\ c.2s)
i _
(+0,5 t o r~
f 1 propse ca rve
. . . . ,
Sh*Y)
l l l
'
i
- - - _ _ . . . A erlied VoIfoge.
- . linear power (linear-N)
- log power (log-N)
, safety channels j N-16 F.wer 1 log count rate (startup)
All detectors operate in Ion Chamber Region r f '
I
,
[+0.3) each l REFERENCE SUNY: SER, p. 7- . SUNY: OP-71, 72, and 7 . SUNY: Training Outline, Definitions.
.
,
. . . . _ _ . . . _
sw v y
. i . ,
m .
e y, '
, ;
'
, ,_
'
2 INSTRUMENTS AND CONTROLS PAGE 34 !
,
- . ANSHERS - STATE UNIV. OF NEW YORK -88/02/09-JARRELL, l
! !
- ,
'
'
,
l- .
f ANSWER .D.02
. (2.00) ;
i Thetwosafetychannels(+0.5 are uncompensated because they only .
' function at high power levels)',+0.5;
'
- gama power is proportional to neutron power where and 2) t 1)he gama signal is j! small c zpared to the neutron signa ,+0.5,I [+0.5]. .
I j REFERENCE
' SUNY: SER, p. 7- .
'
.
2.' SUNY: OP-74, p., 1.
, t I
.
! ANSWER 0.03 (1.00) j
'
Movetheex-coreneutronsource(andverifyinstrumentresponse) l
(+1.0] .
'
i REFERENCE ;
r
! SUNY: OP-74, p. [
l fktt h D.04 (2.00) l
) ANSWER l Low neutron count rate (startup channel) [+0.5); prevent startup !
withoutavisibleneutronlevel[+0.5).
.
,
j
,
I N, Linear-N channels) .
[+0.5];topreventstartuporpoweresca chart recorders (startup, Loglation without on-line i j
8 monitoring and recording of reactor power (and period) (+0.5]. j
-
j REFERENCE r !
. (
i
- $UNY
- OP-74, pp. 1 and !
'
i 4 SUNY: SER, p. 7- t
!
., SUNY: OP-6, p. t j l
.
!
I
?
1 ,
i i
.
if ,
i i
'
_ , _ _ _ _ . . . _ . _ . _ _ . . _ . _ . . _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ - . -
._I
______ ____ ________ ________ ______ _________ . _ _ _ _ _ _ _ _ _ _
. ,
,
, INSTRUNENTS AND CONTROLS PAGE 35
ANSWERS -- STATE UNIV. OF NEW YORK -88/02/09 JARRELL, l
). *
ANSWER D.05 (L4ST 4 by locating)the (N-16 decay .[4ci9}detector downstream (after) the holdup tank u. . >-
C2. by dry i n g . . .. - . . . _ , y. . n o uo m on amotent (Dackgro g eu.ftions [+0.75)
REFERENCE
, SUNY: SER, p. 7- ANSWER D.06 (2.00) Lew ref voltage => corresponds to rod full in potentiometer position (voltage) [+0.5)
- High ref voltag)e (voltage) [+ => rod full out potentiometer position Differential voltmeter subtracts the position potentiometer
-
output voltage from low reference voltage to give a position
,
'
analog [+0.5]. This arrangement allows accurate measurement over the entire range (especially extremes) of rod travel
[+0.5).
REFERENCE SUNY: OP-73, pp. 1 and ANSWER D.07 (2.00) '
r \
.- +s fast SCRAM - by decreasing the DC holding current [+ slow SCRAM - by turning off the AC power supply [+1.0))
- I REFERENCE t SUNY: SER, NUREG-0982, p. 7-2.
!
,
. INSTRUMENTS AND CONTROLS PAGE 36
'
ANSWERS -- STATE UN!Y. OF NEW YORK -88/02/09-JARRELL, ANSWER D.08 (2:07 ke'y 0F,
. . l..?"i . . i . .i ,. o! E.. W.,. g..,......
,_ , . , _
...... m . m
. ,
o,Y T,,.
0 I"~';ti'a U C 2 N I*I' " ' 'I
?!E5}_3.E.3.I3 ..e.... . . .,3f./. .'S. E..$[CCI Ventilation system [+0.5]
a) building exhaust fan power is lost (exhaust blowers 7 eg; / -
shutdown, but the stack fan has its own generator and M cl p r would continue to operate) Jtod5-}* ,6 4; g a S b) actuation lineup would of alarms; auto(for be operative shift to emerg)ency 10-15 min since the ventilation (
(bridge and exhaust stack) radiation monitors are powered from the M-G and air bladaers provide damper hydraulic power M g ,
REFERENCE SUNY: SER, pp. 6-1, 6-2, 8-1, and 9-1.
(
f l
!
r
,
l h
i
- - , , .- . - - - , - , . , - n.-, ,
. SAFETY AND EMERGENCY SYSTEMS PAGE 37
.
AN,5WERS -- STATE UNIV. OF NEW YORK -83/02/09-JARRELL, ANSWER E.01 (1.00) -
1. Mi;;nterlin::ltin- departure from nud ea e boiling (DNB)
REFERENCE SUNY: SER, p. 4- '
ANSWER E.02 (1.00) y
'
Emergency C001:nt Rep! :::ent (pcel fill :ystem) (n frg J vered my Tcchnical Sp;;ificatiens' [:0.;] (containment) Building ventilation system [todr] p#'/ppC 3'
'l. o fp REFERENCE SUNY: SER, p. 6- ANSWER E.03 (1.00)
The (neutron-absorbing) control blades (rods) (and their asso:iated reactivity insertion scram devices). [+1.0)
l REFERENCE 1. . SUNY: SER, p. 3-1.
l l
ANSWER E.04 (1.50) r l
~
l Nydraulic system pressure is sustained for several minutes by air
!
tladders in the hydraulic system accumulators. [+1.5]
i
! REFERENCE SUNY: SER, p. 11-3.
l l
l l
l l
t
.
E. . SAFETY AND EMERGENCY SYSTEMS PAGE 38
.
AN,SWERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER E.05 (1.50)
Coincident alarms [+0.5] from the reactor bridge fixed area monitor
[+0.5] and the building air exhaust effluent monitor [+0.5].
REFERENCE SUNY: SER, NUREG-0982, p. 7- '
ANSWER E.06 (1.50)
the two inlet ducts and the two exhaust ducts will close the two exhaust blowers stop (the 6000 ft cubed per minute blower at the base of the stack remains in operation)
the damper in the 6" emergency exhaust duct opens
[+0.5] each REFERENCE SUNY: SER, NbREG-0982, p. 6- ANSWER E.07 (1.50)
-
Three are on the neutron deck, one is under the bridge, and one is
.in the hot cel [+1.5]
REFERENCE SUNY: SER, NUREG-0982, p. 7- r l .
-
l l
l l
l l
. SAFETY AND EMERGENCY SYSTEMS PAGE 39
'
ANSWERS -- STATE UNIV. OF NEW YORK -8S/02/09-JARRELL, ANSWER E.08 (2.50) control room (behind console) control deck (near airlock) gamma deck (near airlock) neutron deck (at base of stairs) office wing lower hall (near machine shop) office wing upper hall (near conference room) fan room (basement) general building evacuation (in elec equip room) outside, on side of office wing Any five (5) [+0.5] each, +2.5 maximu REFERENCE SUNY: EP No. 6, p. ANSWER E.09 (2.00)
Assuming rho = 62.4 lbm/ft**3 [+0. 5]
H2O Pressure = rho h = (62.4 lbm/ft**3) (1 ft**3/1728 in.**3)
= 0.4 0$* psi O. t 7-(C . to 0.5 95:g;;c;ptet,1sf+1.5]
REFERENCE 0I * /* # * *CC P b
,d A .', $ SUNY: Technical Specifications, p. 2 aI,.< ,,/. F siAt W* [/
.
pass e
,...p -
ras m' ~ h* I.
! v.f4 c.I=,
'4 u %4;l tb1 -
t___ .J, - _ n . an-
-.
-
. ~ .
, $a;;,;f 6p is < 12-h
.
,
'
2 4 ' ,_
I4' ( ) -
g V _
-
l
.
"'
"
,
,
1/
t I
l
. , . _ _ _ _ _ _ . _ _ . _ . . _ . , . , _ _ _ .__
- - -
_ _ - -.. .. -
. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 40
.
ANSWERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER F.01 (1.00)
Backup the automatic' scram by pressing the console SCRAM button
[+0.5] and verifying that all contro' blades indicate fully inserted [+0.5].
REFERENCE SUNY: OP-6, p. .
ANSWER F.02 (2.50)
6 ). NOTE: Steps 5. and 1. may be reversed without loss of point . '
. [+0.25] each 1 .
REFERENCE SUNY: OP-5, pp. 1, 2, and 3.
l i ANSWER F.03 (1.00)
l A component is OPERABLE if it is capable of performing its intended function in a normal . man
. . ._n_e.. _ ._ [+1.0]
..
,.
REFERENCE - - - - .
' SUNY: Technical Specifications, p. 2.
l l
l l
l l
l
- -
., .
.
. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 41
'
ANSWERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER F.04 (2.00) yes 2.Nayer no (primary coolant log)
4.He.pnr no (waste water log) no yes no
'
[+0.25] each REFERENCE SUNY: OP-8; pp. 1, 2, and ANSWER F.05 (2.50)
. SCRAM the reactor (and perfonn follow-up). Announce the reactor scram and the requirement to evacuate the reactor buildin . Monitor egress of personnel from the buildin \ . *>
.
[
- Notify suff supervision and go to Howe Research Buildin /# Stand by to assist (possible) firemen reentr , yt * ps
[+0.5] for each actio \ 4 #v REFERENCE - - -
,c caf , SUNY: EP-6, pp. 2 and t SUNY: EP-1, pp. 3, 4, and . SUNY: Emergency Plan, p. i
-. -
. STANDAR0 AND EMERGENCY OPERATING PROCEDURES PAGE 42
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ANSWERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER F.06 (2.50) scram the reactor - take the key turn off the primary pump turn off the secondary pump turn off tha demineralizer pump
, close pool isolation valves announce the situation over the PA and evacuate unnecessary personnel, if appropriate survey radiation levels in proximity to the reactor pool if necessary, activate the EPF system; or do not allow the pool to overflow post-off the airlocks and/or the machine room door, as appropriate 10. notify the highest available Emergency Director candidate
[+0.25] each REFERENCE i SUNY: EP-4, pp. 1, 3, and 4.
l l ANSWER F.07 (1.00)
l No [+0.5]; prima coolant has a very low level of radioactivity l due to no fuel le kage [+0.25] and primary system demineralizer '
[+0.25]
-
REFERENCE SUNY: EP-4, ,np. 1, 3, and 4.
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. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 43
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AN,SWERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER F.08 (1.00)
Immediately reduce power to 1 MW (or scram) [+0.5] since ?ersonnel are working in a potentially high radiation area without (nown radiation protection [+0.5].
REFERENCE SUNY: OP-26A, p. i i
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- . _ _ _ _ . _ _ _ . , _ . _ _ _ _ _ _ . - - _ _ - . . . _ _ _ _ _ _ _ _ _ . . _ _ _ - . _ _ - _ _ _ _ , _ _ _ . - . _ - _ -
_ - _ _ _ . . , _ _ _ _ . _ .
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. RADIATION CONTROL AND SAFETY PAGE 44-
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AN,5WERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER G.01 (1.00)
Minimum Technical Specification water level is 20 feet above the core top [+0.5], so ten tenth thicknesses would mean an attenuation factor of 10**10, therefore the neutron flux is 10**10/10**10 =
1 n/sec/cm**2 [+0.5] .
REFERENCE SUNY: Technical Specifications, p. ,
ANSWER G.02 (2.00) The first method requires 2 men x 1 rem /hr x 3/4 hr =
1.5 man-rem [+0. 5] Method 2 requires 1 man x 1 rem /hr x 40/60 hr =
0.667 man-rem (removal and replacement) AND
, 0.45 man-res i 2 men x 0.3 rem /hr x 3/4 hr = -------------------- [+0.5]
! total = 1.11 men-rem Method 2 [+0.5]; less radiation exposure [+0.5] (consistent i with ALARA guidelines).
l REFERENCE l
i SUNY: Radiation Protection Manual, pp. 52 and 78.
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1.
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l l ANSWER G.03 (2.00)-
! r area radiation monitors l primary coolant monitors l effluent monitors l primary loo) components (leak tight integrity)
! installed s11elding containment primary purification (demineralizer)
[+0.5] each, +2,.0 maximum.
l REFEREi4CE l SUNY: SER, pp. 4-2, 4-3, 5-1, 5-3, 6-2, and 12-3.
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_ . . - . - _ . . _ . _ _ . _ . _ _ _ _ . _ . , . _ _ _ _ _ . _ . . _ , _ _ _ _ _ . _ _ , _ _ _ _ , _ _ . . . _ _ _ . _ _ . _ _ _ . . _ . _ _ , , _
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. RADIATION CONTROL AND SAFETY PAGE 45
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AN,5WERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ANSWER G.04 (2.00)
gamma rem = 200 rad x 1 rem / rad x 1/4 hr = 50 rem [+0. 5]
beta rem = 50 rad x 1 rem / rad x 1/4 hr = 12.5 rem [+0.5]
n rem = 800 rad x 3 rem / rad x 1/4 hr = 600 rem o [+0.5]
total = 662.5 man-rem
Chances are less than 50/30 [+0.5] (L/D 50 less than or equal to 450 rem)
REFERENCE , SUNY: Radiation Protection Manual, pp. 12 and 3 ANSWER G.05 (2.50) A liquid entering the floor drain is routed to a (250 gal stainless steel) underground storage tank [+0.5]. The liquid in this tank will be sampled for activity [+0.5]
,
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then if requirements are met, the conter.ts are pumped to an above-ground (10,000 Again this tank is (stirred and) gal)sampled holding tank [+0.5].
[+0.5]. If release limits are met the contents are pumped to the (SUNYAB) sanitary sewer system [+0.5].
REFERENCE
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' SUNY: SER, p. 11- i r
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- -. - . . - _ _ _ _ _ - - - . _ . . _ _ _ -
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. RADIATION CONTROL AND SAFETY PAGE 46 AN5WERS -- STATE UNIV. OF NEW YORK
,
88/02/09.JARRELL, ANSWER G.06 (2.00)
The dose rate to each due to distance alone is:
at 1 meter (3 ft) the dose rate 3.96 rem (gamna value from Appendix IV)
Il = 4 rem D1=1 meter [6o,6)
for man A then 11/12 = d2**2/d1**2 i
so 12 = 4 rem (1**2/7**2)
= 4 (1/49) = 81.6 mrem /hr [+0.5]
For man B 12 = 4 (1/8**2) = 62.5 mrem /hr [+0.5]
Man A however has reduced this by shielding to 8.15 81.6 mR/hr divided by 2 = 40.8 mR/hr [ft0/37'
So man B is receiving the greater dose rate M .sf j REFERENCC SUNY: Training Handout, Equations, p. . SUNY: Radiation Protection Training Manual, Appendix I *
ANSWER G.07 (2.00)
rem per calendar quarter
.....................................
Quarterly Quarterly r Average Maximum
............ ........... ...........
- Whole body 1.25 3
............ ........... ...........
Skin X
............ ........... ...........
Extremities 18.75 X
.....................................
[+0.5] for each answer l
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.- _ - _ - _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _
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, RADIATION CONTROL AND SAFETY PAGE 47
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AN5WERS -- STATE UNIV. OF NEW YORK -88/02/09-JARRELL, ,
REFERENCE SUNY: Radiation Protection Manua'i, p. 4 >
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- _ _ - _ . _ - , - _ _ _ . . . - _ . _- .__ - _ , - - . _ _ - _ .
_____ _ _ - _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . _ _ _ _ _ _
b
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l j
f APPENDIX IV ~
~
REFERENCE DATA IVR SELECTED RADIOISOTOPES
I BETA----------------- -------------
HAX CAUMA-------------- ----
HALF ENERCY I NUCLIDE RANCE IN INCHES ENERGY TIN.COE EFFECTIVE LIFE HeV AIR I HVL PLASTIC HeV CRITICAL ORCAN, HALF-LIFE (cm Pb) cm /gm Pb BODY BURDEN (uC1) (d)
Calcium-45 163 d 0.257 (100) 20 .02 . - - --- ---
---
Bone, 30 17 5730 y 0.156 (100) 10 .01 ---
--- ---
{ Ces itun-137
---
Whole Body, 400 10 30.17 y 1. 173 (5.4) 150 .15 0.6616 (89.9) 0.33 0.536 0.114 Whole Body,30 Chromium-51 27.7 d ---
---
11 .3201 (9.8) 0.016 0.165 0.369 # *
e, 800 2 l Coba lt-60 5.27 y 0.318 (99.9) 25 1.17 (99.9)
,
.03 1.32 1.33 (99.98) 1.035 0.059 Wole Body, 10
- 9. 5 Copper-64 12.71 h 0.578 (37.2) 60 .06 1.346 (0.49') 0.12 1.11 0.055 Wole Body, 80 l Hydrogen-3 12.33 y 0.529 0.0186 (100) 0. 5 0.00 --- --- --- .
---
Wole Body,1000 10
60.14 d ---
--- ---
0.0355 (6.67) 0.07 0.0029 2 Thyroid, 0. 325
- Iodine-131 8.04 d 42 0.606 (89.4) 60 . 06 0.364 (81.2) 0.22
- 0.178 0.342 Thyroid, 0.140 0.636 (7.27) 7. 6
'o ta s slum-42 12.36 h 3.521 (82) 600 0. 6 1.524 (17.9) O. 14 1.996 (17.5) 300 1.174 0.052 *
i 0. 3 *
) hosphorous-31 14.28 d 1.71 (100)N 250 .25
]
i odium-22 2.60 y
---
--- --- - - >
Bone, 6 13. 5 I
0.546N(89.8) 55 0.05 i 1.274 (99.9) 1. 2 1.00 0.061 Wole Body,10 I ul fu r-35 87. 4 d -
l 0. 16 75 (100) 11 .01 --- --- ---
---
W ole Body,400 4 Testis,90 tnc-65 243.9 d O.329 (1.5) 30 .03 1.115 (50.8) O.27 0.925 0.066 W ole Body, 60 19 o Intensity h = hours . - = Rcentgena per hour at one meter per Curie
- - days y years i
- 125 - * Data not available ,
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .________-_______ __________ _ _____________ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __ ___-_ _-_
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APPENDIX IV '
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REFERENCE DATA IVR SELECTED RADIOISOTOPES
BETA-----------------
MAX -------------CAMIA-------------------
HALF ENERCY I NUCLIDE RANCE IN INCITES ENERCY A m .COE EFFECTIVE LIFE HeV AIR I NVL CRITICAL ORGAN, PLASTIC HeV IIA LF-LIFE (cm Pb) cm /gm Pb BODY BURDEN (uC1) (d)
Calcita-45 163 d 0.257 (100) 20 .02 --- --- ---
---
Bone, 30 17 5730 y 0. 156 (100) 10 .01 --- --- ---
Cesita-137
---
W ole Body, 400 10
30.17 y 1. 173 (5.4) 150 .15 .
O.6616 (89.9) O.33 0.536 0.114 Wole Body,30 Chromita-51 27.7 d ---
11 .3201 (9.8) 0.016 0. 16 5 0.369 "* * I'" #8 Intestine, 800 26 6
. Cobalt-60 5.27 y 0.318 (99.9) 25 .03 99 93 f* 1.32 1.035 0.059 99_93) uhole Body, 10 9. 5
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Coppar-64 12.71 h 0.578 (37.2) 60 .06 1.346 (0.49) 0.12 1.11 0.055 Whole Body, 80 Hydrogen-3 12.33 y 0.529 0.0185 (100) 0. 5 0.00 ---
--- ---
Iodinn-125
---
Wole Body,1000 10 60.14 d --- --- ---
,
0.0355 (6.67) 0.07 0.0029 2 :
Iodins-131 Thyroid, 0. 325 42 8.04 d 0.606 (89.4) 60 .06 0.364 (81.2) 0.22 0.178 0.342 Thyroid, 0.140 0.636 (7.27) 7. 6 Potessitn-42 12.36 h
,
3.521 (82) 600 .996 (17.5) 300 1.524 (17.9) 0.14 1.174 0.052 * *
0. 3 Phosphorous-32 14.28 d 1.71 (100).. 250 .25 --- --- ---
Sodissa-22
--5 Bone, 6 1 .60 y 0.546b (89.8)' 55, 0.05 1.274 (99.9) 1. 2 1.00 0.061 Wole Body,10 11 Sulfur-35 C7.4 d 0.16 75 (100) 11 .01 --- --- --- ---
n ole Body,400 4 Testis,90 Zinc-65 243.9 d 0.329 (1.5) 30 .03 1.115 (50.8) 0.27 0.925 0.066 whole Body, 60 193.2 i
I = Intensity h =^ hours , f. = RoentCens per hour at one taeter per Curie d - days y years
- 125 - * Data not avail.4ble p i
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A 7YAdfrWM7 2
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SUNY 2/9/88 RESOLUTION OF FACILITY C0lHENTS C0fEENTS ON OVESTIONS A.01 The answer should reflect the candidates' knowledge rather than require the specific terms give RESPONSE: Any adequate definition of the phenomena at hand is acceptable for full credi A.02 The answer does not allow for possible absorption effects overriding positive reactivity from shuffling U-23 , RESPONSE: The answer specifically states movement may be "toward or away from" higher neutron flu Both options are allowed - no change require A.04b The answer is incorrect in that a control rod run-in would occ::r at 1108s power yielding a time of 2.85 second RESPONSE: The facility is correct, full credit will be given for
,
the run-in response.
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A,05c The question did not ask for two response In the answer, change the word "level" to "core spatial distribution" since the instruments in question do in fact respond to changes in neutron leve RESPONSE: Either channel will receive full credit. The answer states "directly" dependent on level (like the fission chamber) - no change require A.08 arding a subcritical reactor, l
Thequestionshouldbeposedre!xhibitexponentialbehavior since a critical reactor would rather than linear response.
! RESPONSE: Not accepte The definition of criticality requires I that a constant neutron level (power) shall be maintained from one generation to the next. The question t6en
, superimposes a constant source term on the critical l
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condition resulting in the addition of the source l
strength to the constant neutron level for each generation. This would result in N = No + S neutrons for each generation, clearly a linear progression. The equation given sarenthetically is, as was pointed out, incorrect for t1e critical condition since it "blows up" (does not apply) to a critical reacto l .. -
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. A.09 If initial power is close to a protective system setpoint, a run-in might be the first thing to turn powe RESPONSE: Since initial power level was not stated, and protective system response was not disallowed, control rod reverse through activation of a control system setpoint is an acceptable answe B.01 An improved drawing for the answer key was provided by the facilit B.02c Accept 35 since a fission chamber is permanently mounted in one grid positio RESPONSE: The question asks for the geometrical maximum which is
, 3 No chang .04 An alternate term for loss of safety chamber high voltage is B- failur RESPONSE: Accepte .09 In addition to the stated answer, a permanently installed radiation monitor serves to prevent inadvertent exposure of personne RESPONSE: Not accepted. The question asks for design features of the transfer system. The monitor is desireable, but is not considered a design feature of the system by the SE C.01 The question should be restated to " draw the reactivity associated with moderator temperature" rather than draw the moderator temperature reactivity. Additionally, the curve in the answer key is wrong in that the power curve is i critically damped, i.e. it does not overshoot in responso to step inputs as indicated.
l
! RESPONSE: The semantics are clear as stated, no change in wording is required. based on your testing data, the curye shape given in the answer key for power and corresponding doppler reactivity were correcte '
C.05 This question should refer to loading an IF target; to load an actual IF (isotope facility) tube, the reactor must be l shut down by procedure.
I RESPONSE: The facility statement is correc If a candidate knows the procedure well enough to state that to load
! an IF tube a shutdown condition is required, full credit l will be given.
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C.06 The concept of sequential measurements to obtain worth over the rod length is not required by the questio RESPONSE: Accepte This portion of the answer is deleted and the point value was reduced accordingl .01 The charge collection versus voltage curve is discussed in training, but is not stresse Also, there are proportional counters in the isotope lab RESPONSE: The question is considered basic to personnel safety in a potential radiation environment since it is the foundation of all active detection devices. If proportional counters are listed in candidate's answers, appropriate credit will be give D.05 Alarm setpoint bias is set because the N-16 detector is near the demineralizer and does not reflect any elimination of N-16 gamma radiatio RESPONSE: The question did not ask for anything but N-16 elimination, so the point value will be reduced to and full credit will be given for the holdup tan c D.08 mergency Coolant Replacement (ECR) is no longer addressed by tech specs as an Engineered Safety Feature (ESF). This portion of the answer will be delete RESPONSE: Accepte Since the R0 is bound to observe tech specs, the ECR portion of the answer will be deleted, and the point value adjusted accordingl E.01 Similarly to 0.08, E.01 and E.02 require knowledge that is E.02 no longer required per tech spec .
RESPONSE: Accepted. Answer key and point valuation changed to reflect tech spec knowledge onl E.09 A 24" loop seal will develop a 24" water column if the equilibrium (static no differential pressure) water height is 12" or greater. The correct answer to this questi6n is 0.87" not the 0.5" indicated on the answer ke '
RESPONSE: Accepted. The answer key was changed to reflect the larger water colum .-- . - . _
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'F.02 Since several operators generally perform the startup checkout, steps 5 & 6 should precede step RESPONSE: Accepte Per OP-5, Routine Startup Procedure, step #
1 of this procedure states:
"Complete and sign the reactor checkout form."
To accomplish this task requires steps 5 and 6 to be performe It should be noted, however, that the "reactor checkout form" (OP-2) is actually the "reactor pre-operation checklist" and needs to have correct terminology and be cross referenced by number. Also, as the facility was aware, step 57 of OP-2 cannot be accomplished until performing step 4 of OP-5. One of these procedores needs modification to resolve this conflic F.04 Per facility common practice the following answers should be changed:
2 YES to NO 4 YES to N0 7 YES to NO RESPONSE: #2 Accepte The S/U stamp effectively serves this functio #4 Accepte The reactor will not be left unattended because the "last out" rule will administrative 1y prohibit it. This practice does leave the relieved operator liable for any mistakes committed by the relief operator in his (her) absence, and, in the case of a casualty, does not leave a single clear coordinator in charge of the control roo #7 Rejecte This would clearly violate OP-8 section II. F.05 Per EP-1 section IV.A.3 "take the reactor log book and evacuate the containment" are acceptable action #
,
RESPONSE: Accepte G.04 The question states radiation field, then gives gamma, beta, and neutron doses, not dose rates. The units should be in RAD /HR, not RA RESPONSE: The comment is correct, but candidates g> Mshould accepte not be confused, since radiation field was explicitly stated, and job duration was give AAA 4
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'G.05 A new radwaste system has been installed, which replaces the old system completely. A 1000 gal, aluminum lined tank in the primary pump room collects all drains. Following sampling this is pumped to a new 10,000 gal. carbon steel tank located in a water-tight vault. This tank is recirculated, sampled and, if below required limits, pumped to the SUNYAB sewer syste RESPONSE: Grading will be adjusted to account for this new syste G.06 Per PNL internal review, grading changed to explicitly allow credit for correct use of Appendix IV of radcon manual, r
=
5