IR 05000057/1986002
| ML20215N929 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 10/24/1986 |
| From: | Coe D, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20215N923 | List: |
| References | |
| 50-057-86-02, 50-57-86-2, NUDOCS 8611100084 | |
| Download: ML20215N929 (45) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 50-57/86-02(0L)
FACILITY DOCKET NO. 50-57
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FACILITY LICENSE N0. R-77 LICENSEE: State University of New York at Buffalo Rotary Road
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Buffalo, New York 14214 FACILITY: Buffalo Materials Research Center EXAMINATION DATES: August 18-22, 1986 CHIEF EXAMINER: b(f D. Coe /
/or B//6 /8- 22- f/fa Date Reactor Engineer ad Examiner REVIEWED BY:
R. Keller b /0[53/N Date Chief, Projects Section 1C APPROVED BY: M M Date'
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/[H. Chief, Projects Branch No. 1 B. 'KisteV SUMMARY: Three Senior Operator-(Upgrade) candidates were administered written and oral examinations. All three candidates passed both portions of the examination and were issued. license PDR ADOCK 05000057 V PDR
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REPORT DETAILS TYPE OF EXAMS: Replacement
' EXAM RESULTS:
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10ral Exam l 3/0 l .
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, CHIEF EXAMINER'AT SITE: Leo Defferding, PNL , CHANGES MADE TO WRITTEN. EXAM: - '
Question H.11 Add to the end of the question "and the primary pump is running."
The candidates were told during the exa Question J.12 Add to the end of the question "at the top of the tank."
j The candidates were told during the exa Question L.03 Change question to read "WHAT is the bases for having two (2) of three (3)
of the following delta T - RTD, delta T - TC, N16 ...."
The candidates were told during the exam.
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-6:13 m over fuels"or 20 ft" 52;deg C."or 126 deg F" c- 68 1ps."or 1080. gal / min" Answer'L.09'
< Add to thefanswer "or Ra'iation d Safety Officer;"
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' Attachments':
11.. Written Examination and Answer Key-(SRO) .
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U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: STATE UNIV. OF NEW YORK REACTOR TYPE: TEST DATE ADMINISTERED: 86/08/21 EXAMINER: HUENEFELD, J../DEFFERDING, CANDIDATE: AUSUER KEY I
[MMSTbk INSTRUCTIONS TO CANDIDATE:
Use separate paper for the answers. Write answers on one side onl Staple question sheet on top of the answer sheet Points for each question are indicated in parentheses after the question. _The passing grade requires at least 70% in each category. Examination papers will 4, be picked up six (6) hours after the examination start W
%.0 . CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY-20.00 20.00 __ REACTOR THEORY 20.00 20.00 RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS
29.00 20.00 SPECIFIC OPERATING c'
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CHARACTERISTICS 20.00 20.00 FUEL HANDLING AND CORE PARAMETERS 20.00 20.00 L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS 100.00 Totals Final Grade All work done on this examination is my ow I have neither given : ,
nor received ai l 7,
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 dental of your application
.and could result in more severe penaltie . 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-l$and 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 on o_ne 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, . Skip at least three lines between each answe ' 11. 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 . Partial credit may be given. Therefore, ANSWER ALL_ PARTS OF THE
' QUESTION AND 00 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
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-completing the examination. This must be done after the examination has -
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been completed.
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-18. When you complete your examination, you shall:
~ 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 TLen in your copy of the examination and all pages used to answer i the examination question 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 b'y the exaraine If after leaving, you are found in this area while the exa.nination is still in progress, your license may be denied or revoke l
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[ REACTOR THEORY PAGE 2
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QUESTION H.01 (2.00)
The reactor is made to be subcritical by a very small amount of reactivity- (less than the value of beta). WILL the resultant stable negative period approach -80 seconds? EXPLAI (2.0)
QUESTION H.02 (2.00)
SKETCH the log-countrate versus time for two (2) different instantaneous insertions of positive reactivity (rho):
1) rho ( the value of beta, 2) rho > the value of bet (Note: SKETCH both cases on the same sketch noting the same arbitrary scale.) (2.0)
QUESTION H.03 (2.00)
DEFINE Shutdown Margi (2.0)
QUESTION H.04 (2.00)
During forced convection operation, grid platefholes not occupied by fuel must be blocked by plugs, reflector elements, or experiment SHOULD this NOT be done, HOW would the critical heat flux be affected? (2.0)
QUESTION H.05 (2.00)
Under WHAT two (2) conditions of core reactivity will a linear scale trace of neutron countrate versus time be concave upward? (2.0)
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- H. REACTOR THEORY
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. QUESTION H.06 -(1.50)
Below is a graph of simulated reactor response to two' (2) simple reactivity manipulations. The first is a rod withdrawal from criticality. The second is a rod insertion. Assuming no reactivity feedback and negligible source effect .
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T illE Key: Dotted line is inverse reactor perio Solid line is neutron countrat ANSWER the following question a .- On the graph itself, INDICATE the periods and direction (1.0)
of rod motio Are the amounts of reactivity inserted-the same for both (0.5)
the insertion and the withdrawal?
QUESTION H.07 (1.50)
WHAT property of the thermal column allows it to be a filter for neutrons of a considerable range of energy and velocity? (1.5)
QUESTION H.08 (.50)
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Does varyin per second)g varythethe strength reactivity of theof source (amount the core? of neutrons (Note: generated do not consider the effects of the material comprising the source.) (0.5)
(*****CATEGORYH CONTINUEDONNEXTPAGE*****) REACTOR THEORY PAGE 4
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QUESTION H.09 (1.50)
WHERE should the antimony / beryllium source be placed relative to the fuel and the fission chamber? (1.5)
QUESTION H.10 (1.00)
WHAT prevents containment vacuum from being broken by the hot and warm drains?
(1.0)
QUESTION H.11 (2.00)- fp : A Y /N "' O " "" f WHY will about 6 gpm flow continue through the purification demineralizer even if the demineralizer pump is stopped] (2.0)
QUESTION H.12 (2.00) If the reactor has a Keff of 0.96, HOW MUCH reactivity, in dollars, must be added to make the reactor critical?
SHOW your wor (1.0) Once the reactor is critical, HOW MUCH time is required to increase the reactor power from I watt to 1 kilowatt on a 30-second period? SHOW your wor (1.0)
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(*****ENDOFCATEGORYH *****)
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. QUESTION I.01 (.75)
WHICH of the following conditions regarding the fixed area radiation monitors would uncondittoaally require the reactor to be shutdown?
(SELECTone.) (0.75)
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Two (2) of the monitors on the_ neutron deck are out of servic . The bridge monitor will be out of service for 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> .
The hot cell monitor is out of servic . The bridge monitor and one neutron deck monitor have been temporarily replaced by separate portable unit QUESTION I.02 (1.50)
WHAT must be done if the reactor is operating with the stack particulate monitor out of service? (1.5)
QUESTION I.03 (2.10)
There are six (6) specifications regarding the reactor containment building that must be met prior to reactor operation. STATE three (3) of these six (6). (2.1)
(.75)
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QUESTION I.04 A potential effluent contains several isotopes, including both identified and unidentified isotopes. WHICH statement below best describes the criteria for determining whether or not the effluent may be released to the sanitary sewer? (0.75)
(a.) Each isotope should be equal to or less than its individual MP (b.) The sum of the percentage of each isotope's concentration relative to their respective MPCs, including unidentified, must be less than 100%. :
(c.) The total integrated dose for the year must be less than one curie per isotop (d.) Each isotope should be equal to or greater than its individual -
MPC, with the exception of unidentified isotopes which are required to be at less than detectable quantitie (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
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I. -RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 6
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QUESTION I.05 (2.00).
Technical Specifications list three (3) criteria for determining whether or not experiments should be doubly encapsulated. STATE two (2) of these three (3) criteri (2.0)
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QUESTION I.06 (3.00)
WHAT 'should be done for the following effluent monitor alarms?
Consider each alarm separately, primary water .5 building air or building particulate .5 QUESTION I.07 (3.00)
WHAT should be done for the following area monitor high alarms?
Consider each alarm separately, N-deck 1,2,3 or hot cell . bridge . bridge, simultaneous, with building air .
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QUESTION I.08 (.50)
ANSWER TRUE or FALS Manual operation is the preferable mode of operation of the Truck Doo (0.5)
-QUESTION I.09 (2.40)
WHAT is the flow path for containment ventilation under emergency conditions that have resulted in isolation of the four (4) hydraulic -
dampers? (2.4)
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- RADIOACTIVE HATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 7
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QUESTION I.10 (1.00)
WHY are beam tubes " stepped"? (1.0)-
QUESTION I.11 (1.00)
WHAT two (2) gases are permissible for use in voiding the voidable tank?
(1.0)
- QUESTION I.12 (2.00)
- WHICH fume hoods should be used when opening an IF can? (1.0) An activated IF can should be kept under HOW MANY-' feet of water for 30 minutes prior to recovery? (1.0) ,
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' SPECIFIC OPERATING CHARACTERISTICS PAGE 8
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QUESTION J.01 (2.00)
Technical Specifications state several safety limits for the forced convection mode (e.g., maximum power, minimum pool level, minimum flow rate and maximum pool tem been arrived at using two (2) criteria perature). These safety for defining compromise limits have of fuel or cladding integrity. STATE these two (2) criteri (2.0)
QUESTION J.02 (4.00) LIST five (5) of the six (6) automatic scrams and STATE their setpoint (3.0) WHICH three (3) cf these scram functions are only required for the forced convection mode? (1.0)
QUESTION J.03 (2.00)
Residual xenon and samarium r..ust be accounted for during startup by-properly positioning the neutron detectors. With regard to this, WHAT is the difference between a hot startup and a cold startup? (2.0)
QUESTION J.04 (1.00)
WHAT is the purpose of the " suction valve closed" interlock? (1.0)
QUESTION J.05 (1.00)
HOW is true reactor power measured? (Note: A single phrase answer issufficient.) ,
(1.0)
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QUESTION J.06 (2.00)
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WHY should the purification system be placed in the desired operational condition prior to adjusting valve P-27 (2.0)
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" SPECIFIC OPERATING CHARACTERISTICS 3 e PAGE 9
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QUESTION J.07 (2.00)
DESCRIBE the basic process for ensuring that a negative worth IF sample is suspended in the area of peak flux. INCLUDE in your discussion the importance of dopple (2.0)
QUESTION J.08 (1.00)
'When filling the voidable tank, H04 far will pool level drop? (1.0)
QUESTION J.09 (1.00)
WHAT effect will loading an empty IF can into the core have on reactivity?
(1.0)
QUESTION J.10 (2.00)
WHAT is the purpose of making compensation voltage adjustments to the log and linear nuclear instrument channels?
(2.0)
QUESTION J.11 (1.00)
WHAT must be done if a reverse signal persists after acknowledgment? (1.0)
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QUESTION J.12 (1.00) g/ 47gp of f e n /c Should'a severe LOCA occur th results in an uncovering of the core, WHICH of the followin most closely represents the potential resultant radiation field (SELECTone) (1.0) R/hr **2 R/hr ' **3 R/hr **4 R/hr (*****ENDOFCATEGORYJ *****)
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- FUEL HANDLING AND CORE PARAMETERS
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QUESTION K.01 (.50)
ANSWER TRUE or FALS A fission plate containing a limited amount of highly enriched U-235 may be used at the outside face of the thermal column onl (0.5)
QUESTION K.02 (2.00)
STATE two (2) of the tf.ree (3) conditions given in Technical Specifications Deff pf tions that constitute " Reactor Operations." (2.0)
QUESTION K.03 (2.00)
The maximum allowable worth of individual experiments given in Technical Specifications is based in part upcn the type of experimen LIST the three (3) types of experiments IN ORDER from lowest to highest allowed maximum wort (2.0)
QUESTION K.04 (1.00)
If shutdown margin is maintained-in accordance with Technical Specifications and a reactor scram occurs with the most reactive
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safety control blade failing to insert its negative, the reactor will be shutdown by at least: (SELECTone) (1.0)
, % delta K/K .5% delta K/K .1% delta K/K .05% delta K/K QUESTION ~ K.05 (2.00) : In general, WHERE are the lowest burnup fuel elements and the highest burnup elements located in your core? (1.0) WHAT effect does maintaining this distribution have on K excess during fuel manipulations? (1.0)
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- FUEL HANDLING AND CORE PARAMETERS PAGE~ 11
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QUESTION K.06 (1.50)
When incorporating an experiment of large negative worth into the core, should adjustments in K excess be made with the experiment LOADED or UNLOADED? EXPLAI (1.5)
QUESTION K.07 (3.00)
Technical Specifications lists five (5) operations that must be supervised by a senior reactor operator. STATE these five (5)
operation (3.d)
QUESTION K.08 (1.50)
In WHAT two (2) ways are fuel assemblies marked for individual
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identification? (1.5)
l QUESTION K.09 (1.00)
WHAT is the purpose of the cd shield associated with the vertical stand pipe? (1.0)
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! QUESTION K.10 (3.00)
COMPLETE the attached table regarding the characteristics of these six (6) power channel (3.0)
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QUESTION K.11 (1.00)
WHAT are the four (4) chemical elements whose isotopes because of ,
their volatility, would comprise the majority of fission products to be potentially released from the fuel and the pool as a result of a fuel leak? (1.0)
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Dependent on Dependent on Power Long Term Control Rod Pool Thermal Response-Channel Measurement Stability Position Equilibrium Time (Absolute / Relative) (Good / Poor) (Yes/No) (Yes/No) (Slow / Fast)
Resistance delta T Thermocouple delta T N-16 Linear N Log N Safety 1 & 2
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QUESTION K.10 (contd) ,,
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QUESTION X.12 (1.50)
EXPLAIN the term " water logging" as it relates to the potential for loss of fuel integrit .(1.5)
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' ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS \.,PAGE 13
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QUESTION L.01- (2.00)
According to Technical Specifications, WHAT is the difference between a Fast Scram and Slow Scram? (2.0)
QUESTION L.02 (.50)
ANSWER TRUE or FALSE. A normal surveillance is classified by Technical Specifications as an experimen , (0.5)
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QUESTION L.03 (1.00) yl5g AT- RTQ AT- TQ W.H difuTM WHAT is the bases for having at le ni. ;..e (2) n;" -- '" d '--'---
during operation in the forced convection mode? (1.0)
QUESTION L.04 (1.00)
A licensed senior operator must be present in the facility when recovering from an unscheduled shutdcwn, unless the shutdown resulted from WHAT event? (1.0)
QUESTION L.05 (.70)
According to the Emergency Plan, dilution of the building air effluents is generally conservatively estimated at greater than
. (SELECTone.) (0.7)
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. fifty fold
. five hundred fold
. one thousan-1 fold :
. five thousand fold
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QUESTION L.06 (1.50)'
WHO is responsible for NSTF security during normal working hours? (0.75) during non-normal working hours? (0.75)
QUESTION L.07 (2.80)
GIVE four (4) examples of a reportable occurrence as set forth in the Technical Specification (2.8) .
QUESTION L.08 (1.00)
STATE two (2) of the four (4) functions served by the Operating Committe (1.0)
QUESTION L.09 (1.50)
WHO (by title) sits on the Operating Committee? (1.5)
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QUESTION L.10 (2.00)
OP #8, Reactor Data and Record Keeping, lists nine (9) logs that are routinely kept. STATE five (5) of thes (2.0)
QUESTION L.11 (3.50)
STATE five (5) of the six (6) responsibilities of the senior staff :
member present in the event of a severe fir (3.5)
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L. -ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PIGE 15
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QUESTION L.12 (1.50) .
WHAT is the difference between a Channel Calibration and a Channel check? (1.5)
QUESTION L.13 (1.00)
DEFINE Special Nuclear Materia (1.0)
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(***** END OF CATEGORY L *****)
(************* END OF EXAMINATION ***************)
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- REACTOR THEORY
. PAGE 16 ANSWERS -- STATE UNIV.-OF NEW YORK -86/08/21-HUENEFELD, .
ANSWER H.01 (2.00)
NO, it wont. Delayed neutrons behave as a source themselves. When a subcritical reactor has sufficient reactivity, the delayed neutrons are subcritically multiplied. The large number of generations associated with this multiplication effectively holds up the decay rate. The negative period becomes (-80 second [+2.0]
Proof: (notrequired)
rho = beta eff/1+1ambda tau (p. 11, equation, operator Training Manual)
beta tau = e-1/ lambda rho (( beta tau (( 1/ lambda (( -80 se REFERENCE SUNY: Operator Training Manual. Equations, p.1 .
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. PAGE 17 ANSWERS -- STATE UNIV. 0F NEW YORK :-86/08/21-HUENEFELD, ,
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ANSWER H.02 (2.00)
(2) [+1.0]
(1) [+0.5]
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For full credit the answer must show a prompt jump for Case 1 and the absence of a prompt jump in Case 2. [+2.0]
REFERENCE SUNY: Principles of Nuclear Reactor Engineering, Samuel Glasstone. See Duke Power Company, Fundamentals of Nuclear Reactor Engineering, p. 101.
- H.03 ANSWER (2.00)
The amount of reactivity by which the reactor is shutdown, or would be shutdown assuming all rods were inserted and the reactor is in -
the cold xenon free condition. [+2.0]
REFERENCE SUNY: Technical Specifications, p. ,
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ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
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ANSWER H.04 (2.00)
Not blocking the grid plate holes would allow flow to bypass the fuel elements. This ~would increase the relative bulk enthalpy and
.thus lower the critical heat flux (the heat flux at which DNB would occur). [+2.0]
REFERENCE 1. . SUNY: Technical Specifications, p.1 ANSWER H.05 (2.00) The reactor is supercritical. [+1.0] Reactivity addition rate is sufficient to maintain a constant ~
or increasing SU [+1.0]
. REFERENCE Basic Point Kinetic ANSWER H.06 (1.50)
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. PAGE 19 ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
' REFERENCE
. Basic Point Kinetic ANSWER H.07 (1.50)
The graphite of which it is constructed consists of a very large number of randomly oriented, small crystals that will diffract a wide spectrum of neutron [+1.5]
REFERENCE SUNY: OP 46, p. ANSWER H.08 (.50)
No [+0.5]
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REFERENCE Basic Point Kinetic ANSWER H.09 (1.50)
As near the fuel as possible, but on the opposite side of the core than the fission chamber. [+1.5]
REFERENCE SUNY: OP 74, p. ANSWER H.10 (1.00)
The 24-inch U-traps located in each drain lin :
REFERENCE SUNY: OP 31, p. , -
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' REACTOR THEORY PAGE 20
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ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
ANSWER H.11 (2.00)
Because of the pressure drop across the primary loop which is developed by flow friction. (Note: this only occurs during forced flow, i.e., the primary pump operating.) [+2.0]
REFERENCE
. SUNY: OP 24, p. ANSWER H.12 (2.00) = (K - K)/(K x K) = (1 - 0.96)/(1 x 0.96) = 0.04/0.96 = 0.041667
[+0.5]
= 0.041667 x ($1/0.0073) = $5.71 [+0.5] P = Po c t/ Tau 1000 = 1 C t/pi Ln 1000 = 6.9 x 30 = 207 sec [+1.0]
REFERENCE NE 390R Notes, p. .
-
__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ . ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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.' Is RADI0 ACTIVE MATERIALS HANDLING-DISPOSAL AND HAZARDS PAGE 21 ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD,' .
i ANSWER I.01 (.75)
(a.) - [+0.75]
REFERENCE- SUNY: Technical Specifications, p.12.
I ANSWER I.02 (1.50)
The' fixed filter [+0.75] must be evaluated daily [+0.75].
REFERENCE SUNY: Technical Specifications, p.1 ANSWER I.03 (2.10) The truck door shall be closed and sealed, one door in each of two airlocks shall be closed and sealed, and all other penetrations other than ventilation ducts shall be seale . The stack fan in the university steam plant shall be operating and the fan in the building air duct shall be operatin .- The pressure in the containment vessel shall be negative with respect to the outside atmospher . The dampers'in the containment ventilation ducts must be operable and be capable of closing in 5 sec or less. They must close automatically in response to-a manual signa . A charcoal filter shall be maintained in the emergency exhaust duct and the modulating damper in the exhaust duct and its controller shall be operabl . The leak rate of the containment vessel shall not' exceed ps (7 cfm) standard air at a negative differential of 1.27 cm of water (1/2 in, water).
Any three (3) [+0.7] each, +2.1 maximum -
REFERENCE SUNY: Technical Speciff. cations, p. 1 . . . . _ _ _ _ _ - .
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[ Ia RADI0 ACTIVE MATERIALS HANDLING DISPOSAL kND HAZARDS PAGE 22 ANSWERS - . STATE UNIV. OF NEW YORK 286/08/21-HUENEFELD, *
_
. ANSWER I.04 (.75)
(b.) [+0.75] ,_
~
REFERENCE ,
.
~ SUNY: Technical Specifications,'p.71 ANSWER I.05 (2.00) ' Excessive corrosive attack of'the reactor or experiment [1 facilit . Excessive contamination or production of' airborne radioactivity. _ Potential for a violent chemical reactio Any two (2) [+1.0] each, +2.0 max'imum .
REFERENCE SUNY: Technical Specifications, p.1 ANSWER I.06 (3.00) primary water (monitor 7). If monitor is off scale, shut down the reactor and secure.the primary and secondary cooling system Notify shift supervisor and health 3hysics. [+1.5] building air (monitor 10) or building particulate (moniter 11). Upon shift supervisor approval, increase the red alarm set point to an interim high alarm set point equal to twice the original red alarm set point. Notify health physics. If the interim alarm set point is reached, shut down the reactor and evacuate the building according to procedure. '[+1 5]
.-
REFERENCE SUNY: OP 268, p. 1.
, -
a L _ . _ _ _ _ _ _ _ _ _ _ _ _ . -
. _ _ . . .
.
.
." RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 23 ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
ANSWER . I.07 (3.00) l N-deck 1,2,3, hot cell (monitor 1,2,3,5). Announce condition
, over intercom to warn personnel in the area. Notify shift supervisor or health physics, if available, for investigatio [+1.0] bridge (monitor 6). Upon shift supervisor approval, increase the red alarm set point to an interim high alarm set point equal to twice the original red alarm set point. . Notify health physics. If the interim alarm set point is reached, shut down l
the reactor and evacuate the building according to procedur [+1.0]
i simultaneously bridge and building air (monitors 6 and 11). l If the cause cannot be immediately determined to be direct l
,
radiation, scram the reactor, actuate the evacuation alarm, evacuate the facility, and initiate emergency procedure Verify that the Pratt dampers are closed; back up manually if necessary. [+1.0]
REFERENCE SUNY: OP 26A, p. ANSWER I.08 (.50)
TRUE [+0.5]
REFERENCE l SUNY: OP 27, p. 1.
.
ANSWER I.09 (2.40)
.
A suction is drawn on the containment through the 6-inch stack bypass
[+0.8] line through a charcoal filter [+0.8] to the stack fan at the steam plant [+D.8].
,
REFERENCE - SUNY: OP.28, p. .
- , - - - . . . . - . . , . ~ - - . , - - - - - - -,...,n.n-a,,.. . . - . -e-----,.---.-, --m.,--,, - - - - - - - -
__ - - - .
/
' O RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HA'ZARDS PAGE 24 *
s ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
. .
,
k
. ANSWER I.10 (1.00) '
To prevent streamin [+1.0] -
, REFERENCE SUNY: OP 43, p. ANSWER I.11 (1.00) C0(2 ' N(2)) [+0.5][+0.5]
REFERENCE SUNY: OP 48, p. ,
,
,
ANSWER I.12 (2.00) Only those that exhaust to the power house stack. . [+1.0] Ten feet [+1.0]
REFERENCE SUNY: OP 49, p. .
.
.
. WECIFIC OPERATING CHARACTERISTICS PAGE 25 ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
ANSWER J.01 (2.00)
- Fuel centerline melting must not occur. [+1.0] Critical heat flux must not be exceeded. [+1.0]
REFERENCE SUNY: Technical Specifications, p. ANSWER J.02 (4.00) Automatic Scrams Setpoints power safety, channels A and B 120% dry chamber door open, scram door not closed flapper open >250 kW water level 6.13 m over fuel 82#[U' pool temperature 52 deg C W (R G" F flow 681ps n gyo pr%g
[+0.6] for each group (scram and setpoint), +3.0 maximum .- flow 2. - flapper open pool temperature
'
[+0.33] each REFERENCE SUNY: Technical Specifications, p. 1 ANSWER J.03 (2.00)
If a hot startup is being made, the chambers should' require no change in position. [+1.0] :
If a cold startup is being made, the chambers should be lowered to the previously established low residual xenon position as marked on each individual positioning screw. [+1.0]
-
REFERENCE SUNY: OP 5, p. .
- SPECIFIC OPERATING CHARACTERISTICS PAGE 26
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ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
ANSWER J.04 (1.00)
Prevents implosion of the N-16 delay tank by primary pump suctio [+1.0]
REFERENCE SUNY: Technical Specifications, p. 1 .
ANSWER J.05 (1.00)
By measuring the temperature across the core and the mass flowrat [+1.0]
REFERENCE SUNY: OP 6, p. ANSWER J.06 (2.00)
Because the purification system has the potential of robbing up to 20 gpm flow from the primary loop,' therefore interfering with proportionality between core delta T and true reactor powe REFERENCE SUNY: OP 24, p. . SUNY: OP 21, p. 1.
.
ANSWER J.07 (2.00)
The sample is slowly. lowered into the core. As the sample is lowered, reactor power will decrease. The power decrease will be opposed by doppler. As the sample goes through the peak flux power will begin:
to increase. The operator will coordinate with the sample loader a to position the sample at the position of minimum Rx power. [+2.0] !
REFERENCE
. SUNY: OP 49, p. . - _ - _ _ - . . .
.' J. ' SPECIFIC OPERATING CHARACTERISTICS PAGE 27
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ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, ANSWER J.08 (1.00)
thout two (2) inche [+1.0]
'
REFERENCE SUNY: OP 48, p. ,
. ANSWER J.09 (1.00)
It will increase reactivity because of a positive void coefficien [+1.0]
REFERENCE SUNY: OP 49, p. ANSWER J.10 (2.00)
To compensate for santa radiation which would tend 'to overpower the neutron countrate at very low power levels. [+2.0]
REFERENCE
- SUNY: OP 71, p. ANSWER J.11 (1.00)
scram the reactor [+1.0]
REFERENCE SUNY: OP 6, p. .
!
ANSWER J.12- (1.00)
(d.) [+1.0] '
REFERENCE I SUNY: EP 4, p. . . - . . . . -. - .- - - - - _ . _ . - _ . _ - . _ - - - . . ..
- FUEL HANDLING AND CORE PARAMETERS
. PAGE 28 l A!ct!ERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
ANSWER K.01 (.50)
True [+0.5]
REFERENCE SUNY: Technical Specifications, p. 1 )
!
ANSWER K.02 (2.00) . Control blades installed in the core are not fully inserte . The console key is in the keyswitc . Manipulations are being conducted in the pad that could affect core reactivit Any two (2), [+1.0] each, +2.0 maximu REFERENCE SUNY: Technical Specifications, p. ,
ANSWER K.03 (2.00)
Movable Unsecured Secured (lowest) (highest)
[+0.6] [+0.6] [+0.6] ([+0.2] for proper order)
REFERENCE SUNY: Technical Specifications, p. ANSWER K.04 (1.00)
(b.) [+1.0]
REFERENCE
- SUNY: Technical Specifications, p. _ . _ _
_ _ _ - . ___
.
~
~ FUEL HANDLING AND CORE PARAMETERS ~ PAGE 29
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ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
ANSWER K.05 (2.00) The lowest burnup fuel is generally located in the center of the core [+0.5] with the highest burnup fuel being peripheral areas [+0.5] . Fuel manipulations tend to cause significant changes in K exces [+1.0]
REFERENCE SUNY: OP 4, p. ANSWER K.06 (1.50)
The experiment should be unloaded [+0.5]. This is to. ensure that proper shutdown margin is achieved without the negative effect of the experiment [+1.0].
REFERENCE SUNY: OP 4, p. ANSWER K.07 (3.00) Fuel manipulations' in the core when there are >= 15 fuel assemblies on the grid plat . When experiments are being manipulated in the core that have an estimated reactivity worth > 0.6% delta k/ ;
3. . Removal of one or more control blades if there are >= 10 fuel assemblies on the grid plat . Removal of shielding plugs from a beam tub : Resumption of operation following an unscheduled shutdown, l unless _the shutdown was a result of an interruption of electrical !
power to the cente l
[+0.6] each -
REFERENCE SUNY: Technical Specifications, p. 31 and 3 l l
_ . _
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K .' FUEL HANDLING AND CORE PARAMETERS PAGE 30
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ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
.
~ ANSWER K.08 (1.50)
.
The assembly number is engraved in 2-inch high figures on the sides of the assembly box [+0.75] and coded notches are carved into the top ends of the assembly box ~ [+0.75].
REFERENCE SUNY: OP 9, p.~ ANSWER K.09 (1.00)
To select either thermal or full spectrum neutrons as the irradiating source. .[+1.0]
. REFERENCE
- SUNY: OP 50, p.. ANSWE .K.10 (3.00)
See attached tabl [+3.0]
REFERENCE
. SUNY: OP 78, Table- *
ANSWER ~ K.11- (1.00) krypton xenon bromine iodine
. -
^
[+0.25] each REFERENCE SUNY: EP 5, p. l
-. . - . . - , , , , _ - , - . - . . , _ . . . . - _ _ . - . . . . , , - , _ , _ . . - , . . - . , , . _ _ _ , _ _ , _ _ . - . ._.. ._ . --
.
.' a t
.-
E'
Dependent on Dependei.t on Power Long Term Control Rod Pool Thermal Response
,
Channel Measurement Stability Position Equilibrium Time
,
Resistance delta T Absolute Good No Yes Slow Thermocouple delta T Absolute Good No Yes Slow N-16 Relative Good No No appro secs Linear N Relative Poor Yes No Fast Log N Relative Poor Yes No Fast Safety 1 & 2 Relative Poor Yes No Fast
!
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$
E; w
ANSWER K.10 g
,
%
,
- FUEL HANDLING AND CORE PARAMETERS PAGE 31 ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
ANSWER K.12 (1.50)
Water logging-would result from the development of a small leak in a fuel pin. Should the water inside the fuel pin be heated, steam would form. The resultant pressure transient could potentially rupture the fuel pin.- [+1.5]
REFERENCE SUNY: EP 5, p. .
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- L; ADMINISTRATIVE PROCEDURES, CONDITIONS-AND LIMITATIONS PAGE 32
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' ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
.
ANSWER L.01' (2.00)
A Fast Scram is a rapid reductica of the magnet holding current of the control blades, and a Slow Scram is the shutoff ' electrical power to the units providing the magnet holding current with subsequent decay (slow) of the magnet holding current. [+2.0]
REFERENCE SUNY: Technical' Specifications, p. 2 and ANSWER L.02 (.50)
FALS [+0.5] (Evaluation or test of a surveillance would be considered an experiment.)
REFERENCE SUNY: Technical Specifications, .-
ANSWER L.03 (1.00)
To provide a measure of reactor power'that is not sensitive to neutron
.
flux distributio [+1.0]
REFERENCE 1.- SUNY: Technical Specifications, p. 1 ANSWER L.04 (1.00)
A loss of power to the facilit [+1.0]
- -
REFERENCE SUNY: OP 5, p. ym- r,- , - - , , . , - - , , - - - .-+-,-1m.y ---w , 4 - w
a
~ ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 31
' ANSWERS -- STATE UNIV. OF NEW YORK
.
-
86/08/21-HUENEFELD, .
ANSWER L.05 (.70)
(a.) ' [+0.7]
REFERENCE NSTF Emergency Plan, p.1 ANSWER L.06 (1.50) The reactor shift supervisor. [+0.75] The Department of Public Safety. [+0.75]
REFERENCE l'. SUNY:. Security Plan, Section 3.1 and 3.2.
l
- .
,
.
i
_ yw , , - - - y _
, .-,m-, -, , - . .-,
a s
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- ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 34 ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, J.
-.
ANSWER L.07 (2.80) operation in excess of a safety limit as set forth in Section . discovery of. a safety system setting less conservative than the limiting setting established in the Technical Specifications operation in violation of any _ condition for operation established in the Technical Specifications a safety system component malfunction or other component or system malfunction that could, or threatens to, render the safety system incapable lof performing its intended safety functions release of fission products from a leaking fuel element an uncontrolled or unplanned release of radioactive material from the restricted area of the facility in excess of applicable limits an uncontrolled or unplanned release of radioactive material that results in concentrations of radioactive materials within the restricted area in excess of the limits specified in Section 3.6 of these Technical Specifications conditions arising.from natural or man-made events that affect
-
or threaten to affect the safe operation of the facility an observed inadequacy in the-implementation of administrative or procedural controls that causes or threatens to cause the existence or development of an unsafe condition with the operation of the facilit Any four (4) [+0.7] each, +2.8 maximu REFERENCE SUNY: Technical Specifications, p. 3 ~ :
~
,
- -. .-_...-__y . - . - - - _ . -
,c' .
%
- ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 35
[
ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
ANSWER L.08 (1.00) review experiments which present no new significant safety problems approve additions to or revisions of any Operating Procedures review abnormal occurrences perform facility inspections Any two (2) [+0.5] each, +1.0 maximu REFERENCE SUNY: Technical Specifications, p. 3 ANSWER L.09 (1.50)
R atio r ection Service Manager - 'l50 8*dMN */ #" ? #U"" '
Operations Department Manager REFERENCE
, SUNY: Technical Specifications, p. 3 ANSWER L.10 (2.00) reactor log MWH log maintenance log fuel pin log primary coolant log radiation monitor log security log
. : waste water log i reactivity log i
Any five (5) [+0.4] each, +2. 0 maximu i
,
REFERENCE SUNY: OP 8, p. 1- _ _ .
__ t-L. ' ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 36 ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
ANSWER L.11 (3.50)
i Issue dosimeters, and record the firefighters' names, if possibl ~ Use Public Safety to keep the public from the area as much as possibl . After the situation is secured, do not release the firefighters or any of their equipment until checked and approved by Radiation Protection or Health Physic . Make sure that all the people that were in the building are accounted for. Do not release excess (non-essential) staff until they are cleared by Radiation Protection or Health Physic . Alert senior staff not on site when time permit . Arrange for escort of firemen into controlled areas when -
they arrive. -NSTF _ staff responsibility is to provide health ~
physics coverag REFERENCE SUNY: EP 6, pp. 2 and .
L ANSWER L.12 (1.50)
A Channel Calibration is an adjustment of a channel so that its output corresponds to known values of the parameter being measured
[+0.75]. A Channel Check is a qualitative verification of acceptable operation by observation of behavior [+0.75].
! REFERENCE l SUNY: Technical Specifications, p. _.
t ANSWER- L.13 (1.00)
Plutonium [+0.25], uranium-233 [+0.25] uranium containing more -
than the natural abundance of uranium-235 [+0.25] or any material artificially enriched by any of these substances [+0.25].
a - e-
- ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 37 ANSWERS -- STATE UNIV. OF NEW YORK -86/08/21-HUENEFELD, .
REFERENCE . SUNY: Operator Training Manual Definition .
S
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I
_ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . . _ _ _ . _ _ . . _ _ _ _ _ _ , _ _ . . _ _ _ . _ _ _ _ . - _ - - _ . . _ _ _ _ , - , , . . . _ _ _ . _ _ _ _ , _
A
'
- (. ,
o a
.
____________________________________________________________________________
EQUATION SHEET
____________________________________________________________________________
. .
'
Where mi = m2 (density)1(velocity)i(area)1 = (density)2(velocity)2(area)2
____________________________________________________________________________
KE = mv PE = mgh 1 1 = PE 2+KE2+P Y22 where V = specific 2 PEl + KE +P V l
volume P = Pressure
________________________________.___________________________________________
Q = mcp(Tout -T in ) Q = UA (Tay,-Tstm) Q = m(hl-h2)
____________________________________________________________________________
P = Po10(SUR)(t) P = Po et /T SUR = 26.06 T = (B-p)t T p
____________________________________________________________________________
delta K = (K,ff-1) CR1 (1-Keff1) = CR 2 (I-Keff2) CR=S/(1-Keff)
(1-K,f f 3) (1-K,ff) x 100%
SDM =
M = (1-Keff2) K,ff
____________________________________________________________________________
-
decay constant = in (2) = 0.693 A1 = A0 e-(decay constant)x(t)
t t 1/2 1/2
____________________________________________________________________________
Water Parameters Miscellaneous Conversions 1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 10 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 1 ft 3= 7.48 gallons 1 hp = 2.54 x 103 Btu /hr 3 6 Density = 62.4 lbg/ft 1 MW = 3.41 x 10 Btu /hr , -
Density = 1 gm/cm 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft-lbm/lbf-sec 2
_______________________________________________________________________-__--
- - - , . - - - - , . - . - - . .
,, ., , ,_. - _ - - , , , ,