ML20127P117

Exam Rept 50-228/OL-92-01 on 921102-04.Exam Results:All Seven SRO Passed Written & Operating Portion of Exam.Several Operators Demonstrated Weaknesses,Per Standards Set by Facility Requalification Program

ML20127P117
Person / Time
Site:	Aerotest
Issue date:	11/23/1992
From:	Caldwell J, Isaac P Office of Nuclear Reactor Regulation
To:
Shared Package
ML20127P102	List: ML20127P117
References
50-228-OL-92-01, 50-228-OL-92-1, NUDOCS 9212020072
Download: ML20127P117 (40)

Text

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ENCLOSURE 1 V. S. NUJLEAR REGULATORY COMMISSION OPERATOR LICENSING RE0VALIFICATION EXAMINATION REPORT REPORT NO.: 50-228/0L-92-01 FACILITY DOCKET N0.: 50-228 FACILITY LICENSE N0.: R-98 FACILITY: Aerotest Triga Reactor EXAMINATION DATES: November 2 - 4, 1992 EXAMINER: Patri Isaac (Chief Examiner)

SUBMITTED BY: o- // 7!fA a r ck Is g / h f Examiner / Date APPROVED BY: dtYde/.

hines L. CaldwelT, Chief

/ Mdb

' Date Mn-PowerReactorSection Operator Licensing Branch Division of Reactor Controls '

and Human Factors, NRR

SUMMARY

NRC administered written and operating requalification examinations to seven Senior Reactor Operators (SRO). All seven SR0s passed the written examination. Several operators demonstrated weaknesses, per the standards set by the facility's requalification program, in at least one section of the written examination. NRC expects the facility to implement the_ requirements __of their requalification program for the-weaknesses identified during the written examination. All seven SR0s passed the operating portion of the examination.

9212O20072 921123 8 DR ADOCK 0500

1 e

BIPORT DETAUS

1. Examiners:

Patrick Isaac, Chief Examiner

i. Results:

R0 SRO Total (Pass / Fail) (Pass / Fail (Pass / Fail)

NRC Grading: N/A 7/0 7/0 Facility Grading: N/A ~l0 7/0 -

3. Written Examination:

The written examination was administered on November 2,1992 to st:ven Senior Reactor Operators. All the operators passed the written examination.

Three SR0s received grades below the threshold set by the facility's '

requalification program, in at least one section of the written examination. In accordance with their requalification program, the facility is expected to provide remedial training with a follow up retesting of the operators who demonstrated weaknesses.

As a result of the discussion during the oxit meeting, one written examination question (C.08) was deleted. .

No official comments were submitted by the facility.

4. Operating Tests:

The operating examinations were administered on November 3 - 4, 1992.

All seven SR0s passed the operating examinhtion.

5. Exit Meeting:

-An exit meeting was_ held between Mr. Hugo G. Simens (Aerotest) and Patrick Isaac (NRC) following the completion of the examination. There were no generic concerns raised by the NRC and Mr. Isaac expressed his gratitude to Mr. Simens for his help in the preparation and administration of the examination, i

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ENCLOSURE 2 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Aerotest REACTOR TYPE: AGNIR DATE ADMINISTERED: 92/11/02 REGION: 5 CANDIDATE:

LICENSE APPLIED FOR:-

JNSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach all answer sheets to the examination. Each question is worth one (1.00) point. A 70% overall score is required to pass the examination.

Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALU1_ TOTAL SCORE VALUE CATEGORY

_20.00 33.33 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 23.00 33.33 __ B. NORMAL AND EMERGENCY O'~ RATING PROCEDURES AND RAD 10LCL4 CAL CONTROLS

_20.00 33.33 C. PLANT AND RADIATION MONITORING SYSTEMS 63.00  % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's signature

Page -3 A. RX THEORY, THERM 0 & FAC OP CHARS ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

MULTIPLE CH0 ICE 001 a b c d 002 a b c d 003 a b c d 004 a b c d 005 a b c d 006 a b c d 007 a b c d 008 a b c d 009 a b c d 010 , ,

011 a b c d 012 a b c d 013 a b c d 014 a b c d 015 a b c d 016 a b c d 017 a b c d 018 a b c d 019 a b c d 020 a b c d

(***** END OF CATEGORY A *****)

i

Page' 4 t

B. NORMAL /EMERG PROCEDURES & RAD CON.

ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your answer, write your selection 'in the blank.

001 a b c d 002 a b c d 003 004 a b c d

.. 005 a b c d 006 a -b ,

e d 007 a b c d 1

008 a b c d 009 , , ,

010 a- b c d 011 * , ,

012 a b c d 013 a b c d 014 a b c d _

015 a b c d 016 a b c d 017 a b- c- d 018 a- b c d 019 a b c d

-020 a b c d 021 a b c-.d 022 a b c d 023 a b c d '

7****ENDOFCATEGORY B *****)

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Page 5 C. PLANT Af4D RAD M0filTORING SYSTEMS ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

001 , ,

002 , ,

003 , ,

004 a b c d _

005 a b c d i

006 a b c d __

007 , , ,

008 a b c d DELETED 1 009 a b c d _

010 a b c d 011 a b c d 012 a b c d _

013 a b c d _

014 , ,

015 a b c d __

016 a b c d _

017 a b c d 018 a 1 2 3 4 b 1 2 3 4 c 1 2 3 4 d 1 2 3 4 e 1 2 3 4 019 a b c d 020 a b c d 021 a b c b

Page -6 NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination. This must be done after you complete the examination.

3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating. _

4. Use black ink or dark pencil only to facilitate legible reproductions.

5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.

6. Fill in the date on the cover sheet of the examination (if necessary).

7. Each question .; worth one (1.00) point. Partial credit may be given only to matching and completion questions. .

8. Print your name in the upper right-hand corner of the first page of each section of your answer sheets.

. 4

9. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper. -

~

10. If the intent of a question is unclear, ask questions of the examiner only.

11. The passing grade requires a final grade of at least 70%.

12. There is a time limit of (3) hours for completion of the examination.

13. When you are done and have turned in your examination, leave the examin-ation area as defined by the examiner. If you are found in this area while the examination is still in progress, your license may be denied or revoked.

4 Page 7 CATEGORY A Reactor Theory, Thermodynamics, and facility Operating Characteristics ,

1. Ir. the ARRR, Beta Effective is larger than Beta because:

a. The average energy of tl.e delayed neutrons is lower than fission <

neutrons,

b. The average energy of the delayed neutrons is higher than fission neutrons,

c. The ARRR approximates an infinite array.

d. There is little neutron leakage from the ARRR core.

2. The source of delayed neutrons in a nuclear reactor is:

a. Slow neutron fissions.

b. Beta decay of certain fission products.

c. Doppler broadening,

d. Moderator effects.

3. The prompt temperature coefficient in the ARRR is . The size of this coefficient, as compared to the bath coefficient is .

(Pick the right combination that will fill in the blanks.)

a. positive-/ small

b. negative / large

c. positive / large

.d. negative / small s

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

i

Page 9

4. With all rods in, cold, Xe free, in, ount rate-is 1000 cpm and the reactivity is -$5.36. -What final count rate vould you expect to see if the safety rod was completely withdrawn? (Assume 8 0.0079 and Safety Rod worth of $3.85)

a. 5360 cpm

b. 3662 cpm

c. 1510 cpm

d. 344 cpm

5. With the reactor on a constant period, wLich transient requires the LONGEST time to occur?-

A reactor power change of;

a. 5% of rated power - going from 1% to 6% power of rated power

b. 10% of rated power - going from 10% to 20% power of rated power

c. 15% of rated power - going from 20% to 35% power of rated power

d. 20% of rated power - going from 40% to 60% power of rated power

6. A customer has requested an irradiation of a spec 1 men which has a negative reactivity worth of $1.00. He requires that the sample be irradiated for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Can this service be_provided an the ARRR and why?

a. No. The value of the experiment exceeds the max. allowed per T.S.

for a single experiment,

b. No. The maximum excess reactivity of $3 is not sufficient.

c. Yes. As long as the experiment has a reactivity insertion rate of less than 10 cents /sec.

d. Yes. The worth of the experiment does not exceed any T.S. values.

Page 9

. 7. If the secondary coolant flow through the reactar heat exchanger is stopped when the-pool water is 80'F, the reactre may be operated at 250-Kwatts for an additional time of:

a. 3 minutes

b. 3.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />

c. 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />

d. 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />

8. The minimum pool water temperature below which reactor start-up is not allowed is:

a. 70'F b, 60'F

c. 40*F

d. 32'F

9. The control rods are interlocked so that only one may be raised at a time. This is because:

a. Dual movement is confusing,

b. Reactivity would be added too fast.

c. The reactor operator could not manage it,

d. A circuit overload from the rod motors would occur.

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

Page 10

10. The ARRR is permitted to contain no more than fueled elements in the reactor core. Also, the core may contain iio more than grams of U-235. Finally, Aerotest may have no more than grams oT U-235 in its possession on t.he premises.

11. Assuming that tne demineralizers should become plugged with foreign material, which ONE of the following statements describes the operating state of the reactor?

a. Tne reactor can be operated providing that primary coolant conductivity is less than 5 micrombos/cm and flow continues around the units that are plugged.

b. The reactor can be operated providing that primary coolant conductivity is less than 7.5 micrombos/cm and pH is greater than 5.

c. In accordance with Tech. Specs, the reactor cannot be operated.

d. The reactor can be operated providing that the coolant temperature

- remains less that 140 'F.

12. At the beginning of a reactor startup, Keff is 0.90 with a count rate of 30 CPS. Power is increased to a new, steady value of 60 CPS. The new Keff is:

a. 0.91

b. 0.925

c. 0.95

d. 0.975

(***** CATEGORY A C0tlTltlUED ON NEXT PAGE *****)

Page 11

13. A reactor has been operating at full power for one week $. hen a scram occurs. Twelve hours later, the reactor is brought critical and quickly raised to full power. Considering xenon effects only, to maintain a constant power level for the next fae 6.:urs. control rods must be:

a. inserted

b. maintained at the present position

c. withdrawn

d. withdrawn, then inserted to the original position

14. The time required to increase power from 100 watts to 250 Kwatts on a 5 second period is about:

a. 40 seconds

b. 93 seconds

c. 200 seconds

d. 360 seconds

15. ' Which ONE of the following statements is a characteristic of subcritical multiplication?

a. The number of neutrons gained per generation doubles for each suceeding generation.

b. A constant neutron population is achieved when the total number of neutrons produced in one generation is equal to the number of source neutrons in the next generation.

c. For equal reactivity additions, it takes less time for the equilibrium subtritical neutron population level to be reached as Keff approaches one.

d. Doubling the indicated count rate will reduce the margin to criticality by approximately one half.

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

gi ?$h

o .

Page 12

. 16. Which ONE of the following statements concerning the moderating properties of Zirconium Hydride is correct?

a. The probability that a neutron will return to the fuel element before being captured elsewhere is a function of the temperature of the hydride,

b. The ratio of hydrogen atoms to zirconium atoms affect the moderating properties for slow neutrons.

c. The hydride mixture is quite effective in slowing down neutrons with energies below 0.025 eV.

d. The elevation of the hydride temperature increases the probability that a thermal neutron will escape the fuel-moderator element t before being captured.

Which ONE of the following is the reason for the -80 second period 17.

following a reactor scram?

.a. The negative reactivity added during a scram is greater than 8-effective

b. The half-life of the longest-lived group of delayed neutron precursors is approximately 55 seconds

c. The fuel temperature coefficient adds positive reactivity as the

, fuel cools down, thus retarding the rate at which power drops -

d. The amount of negative reactivity added is greater than the Shutdown Margin

18. The term " Prompt Critical" refers to:

a. the instantaneous jump in power due to a rod withdrawal

b. a reactivity insertion which is less than beta-effective

'c. a reactor which is critical using both prompt and delayed neutrons

d. a reactor which is supercritical using only prompt neutrons

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

Page 13

19. Which ONE of the following correctly completes the sentence?

The thermal flux is depressed in the center of the core, when a fuel element is installed in the A-ring, because the installation of a fuel element causes the center of the core:

a. to be highly undermoderated, b, to be highly overmoderated,

c. to act as a reflector.

L

d. to increase in critical mass.

20. Which of the following effects contribute, the_most to the large prompt temperature coefficient of TRIGA fueled reactors?

a. Cell and inhomogeneities,

b. Doppler coefficient,

c. Core leakage,

d. Bath coefficient. ,

4

(***** END OF CATEGORY A *****)

l 1

Page 14 CATEGORY B Normal and Emergency Operating Procedures and Radiological Controls .

1. If the Glory Hole were to suddenly fill with water while the. reactor is in operation, the reactor operator would see:-

a. No char.ve in the consolo instruments,

b. A decrease in indica <'d power.

c. An increase in indicated power.

d. A shift in instrument readings up and down.

2. If the irradiation tube which extends into the Thermal Column were to suddenly fill with water while the reactor is in operation, the reactor operator would see:

a. No change in the console instruments,

b. A decrease in indicated power,

c. An increase in indicated power.

~

d. A shift in instrument. readings up and down.

3. The control room area radiation monitor, the-pool water radiation monitor and the reactor real-time air monitor have their alarm points

, set at a level which is no more than  % of-the established emergency levels.

= ,

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

4 Page 15

. 4. An ARRR reactor operator would become aware of a serious downward drift in high voltage to the channel 2 3 & 4 ion chambers because:

a. Indicated power would decrease.

b. Channel #2 period meter would go negative,

c. The 90% H.V. scram would occur.

d. Major rod withdrawal would be required to maintain power.  :

5. Which ONE of the following would NOT be the result of a serious fuel cladding rupture while operating at 250 Kwatts would bring about

a. Pool water radioactivity high.

b. Reactor Room air monitor radioactivity high

c. High conductivity in pool water

d. Control Room radiation high.

6. Which ONE of the following statements is FALSE 7

a. Pool water high radiation monitors shall annunciate an audible alarm on the reactor consolc.

~

b. If the pool water conductivity meter is reading less than 5 micro-mho, the demineralizer pump may be shut down during operation?

c. The reactor room shall be maintained at a negative pressure with -

respect to the control room,

d. If the reactor is operating, the Building Gas Effluent shall be monitored and have an alarm setpoint of 5 2 mr/hr.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

Page 16

7. Following reassembly of the ARRR core aftar ea:S biennial inspection, which ONE of the following activities must be performed?

a. Excess reactivity measurement,

b. Flux mapping of the core.

c. Thermal mapping of the core.

d. Demineralizer Loop full flow test

8. A Quarterly reactor inspection, is deemed late if the time since the last inspection exceeds three months by:

a. I day

b. I week

c. I month

d. 3 months

9. The Demineralizer system (does or does not) operate continuously. A major leak in the flow meter occurring on Sunday (would or would not) release pool water in a quantity (greater than or less than) 100 gallons. This system Tiilure (is or is not) self limiting.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

Page -PF 17

10. With the reacr pool outlet initially at 80 'F and the reactor at 250 kW, a reductic, in primary flow rate from normal to 100 gpm will:

f

a. Eventually result in a reactor scram if no operator action is taken.

b. Result in an immediate scram, e s

c. Cause the cooling tower fan to operate more frequently.

d. Result in a higher steady state pool outlet temperature.

E

11. In order for a reactor operator to remain on active status on the ARRR, there must be a record of operating hours during any calendar "

period of . Also, a follow-up physical examination must be taken at least every .

12. Effective 1 January 1994 the permitted occupational exposure to whole body radiation will be:

a. 5 (N - 18) Rem /yr not to exceed 3 Rem /qtr.

• b. 5 Rem /yr.

c. 2 Rem /yr.

d. I Rem /yr.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****) d

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4 Page 18

13. The sign " cavil 0N - RADIATION AREA" denotes an area in which a person may be exposed to whole body radiation at a MAXIMUM rate of:

r 2 tRem/hr

b. 5 Mrem /hr

c. 100 Mres/hr

d. 3000 Mrem /hr 5

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2

14. A small sized source of cobalt-60 roads' 500 Mr/hr at 4 feet. At 6 feet this source will read:

a. 1286 mrjar _

b. 333 mr/hr 4

c. 320 mr/hr

d. 222 mr/hr .

15. How long would it take the pool water to rise from 70 to 100 "F if the reactor was operating at 250 Kw? Assume a normal pool level. *

~

a. 135 mis

b. 221 min

c. 240 min

d. 300 min

(***** CATEGORY B CONTINVED ON NEXT PAGE *****)

Page 19

16. During performance of corrective maintenance to replace the Control Rod Drive Mechanism rod down limit switch, it was discovered that the magnet wire conduit had been damaged and needed to be replated. A temporary change to the limit switch replacement ORF (Operations Request form) was prepared by the SRO. The replacement of the switch and the conduit was then completed. ,

Which ONE of the following statements applies to the above scenario?

a. The temporary change was adequate and shall be subsequently reviewed by the Reactor Safeguards Committee.  ;

1

b. In accordance with the Administrative Pro:edures, only the Reactor  :

Supervisor may issue temporary changes to a procedure. '

c. The change to the ORf changed the intent of the procedure and therefore a temporary change was not allowed.

d. The temporary change was adequate and the Reactor Safeguard Committee approval is not required.

17. If the reactor was at 250 KW and one central fuel element failed, what ,

would be the approximate dose received in the first hour by an ,

individual standing in the middle of the reactor room 7 Assume that the individual did not evacuate as he should have,

a. 0 - 15 mr

b. 50 - 75 mr

c. 250 - 300 mr

d. 1 - 2 Rem e

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

- _ - . _ _ _ _ . - - - _ _ ~ . , , , _ _ _ - . . _ _ . _ . .-._ _ __

3 Page 20

18. The procedure for control rod calibration by the rod drop methed states '

that power should be maintained between 100 and 1000 watts just before dropping the rod. Which ONE of the following statements describes why these limits are imposed?

a. Testing outside these limits may cause the minimum Shutdown Margin (SDM) to be exceeded.

b. Exceeding the upper limit would cause significant reactivity contributions due to the fuel temperature,

c. Exceeding the lower limit would cause significant reactivity contributions due to the Bath coefficient,

d. To minimize the temperature rise of the coolant due to the primary -

pump being 0FF.

19. Which ONE of the following statements is NOT a procedural control that help to prevent the accidental swapping of fuel elements during surveillance checks?

a. Only one fuel element may be out of core or stora,e at a single time.

b. All fuel is required to be returned to its original position prior to startup.

c. A data sheet is prepared in advance which delineates fuel moves to

• be per formed. - - -

d. Deviation from the fuel movement planned moves are not allowed.

(***** CATEGORY B CONTINVED ON NEXT PAGE *****)

9 Page 21

, 70. Upon receipt of a water radioactivity alarm, the operator immediately tep ao :i monitor the water and air radiation levels. The reactor was opt n $mc at 250 Kw when the alarm was received.

Whitu ONE of the following best describes the actions to be taken immediately by the operator if both the monitors are slowly increasing?

a. Scram the reactor

b. Scram the reactor and evacuate the high bay area.

c. Scram the reactor and evacuate the high bay area.

Hit the two emergency buttons (near the control room door).

.d. Scram the reactor and evarcate the high bay area.

Hit the two emersency buttons (near the control room door). -

Sound the rauiation siren and shutdown the air handling equipment 1

21. Which ONE of the following statements concerning instrumentation requirements for refueling operations is correct?

a. The daily reactor checks are NOT required to be completed,

b. Either the air OR water radiation monitors and the associated chart recorder must be operational,

c. ALL instrumentation required for reactor er 'ation must be operable and operating,

d. Only Channel 4 must be operational-since-it is the channel -that is normally used.

+

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

Page 22

22. Which ONE of the following actions is required by ARRR Operating procedures, if after the Safety rod is withdrawn to its full out position there is NOT a significant increase in countrate, during a reactor startup'l  ;

a. Insert the Safety rod and initiate corrective action.

b. Adjust the Shim and Reg rods to obtain the desired power level.

c. Adjust the output of the L>g Count Rate Meter and continue the startup.

d. Obtain permission from the Reactor Supervisor to continue the startup and make a log entry to that effect.

23. Which ONE of the following listed personnel is required by the General Emergency Procedures to inform the San Ramon Fire Department in the event of a fire that cannot be controlled by the fire fighting equipment within the facility?

a. The SR0 in charge.

b. The Reactor Supervisor,

c. The Radiological Safety Officer. ,

d. The person discovering the fire.

J

(***** END OF CATEGORY B *****)

. . . -1 . - , . _ _ , _ ,___,m. -,,-~v_.,

t Page 23 CATEGORY C -

Plant and Radiation i Monitoring Systems

1. The pool water radiation monitor is located in the building.  !

Circulation through this monitor is provided by the pump, which is located (upstream or downstream) of the monitor.

2. The reactor room / pool area air monitor is located in .

Circulation through this monitor is provided by a pump, located in the building.  ;

3. Air particulates are collected on a filter paper located in .

This system operates  % of the time. The air sampled by this system comes from .

4. In a declared radiological emergency which ONE of the following air handling systems must be shutdown?

a. Control Room AC.

b. Lavatory fans.

c. Tagging room AC.

d. QC/ Dark room AC - ~ . _ . _

5. Which ONE of the following materials may NQI be used in contact with reactor pool water?

a. Aluminum,

b. Copper,

c. Stainless Steel.

d. PVC.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

. Page f424

6. According to the ARRR Radiological Safety manual the permitted emergency exposure which may be sustained to protect property is:

a. 1.25 Rem  ;

b. 5 Rem

c. 25 Rem

d. 50 Rem

7. Our procedures renuire that we check for radioactive contamination on surfaces by taking swipe samples no less frequently than .

The " release" limit for removeble surface contamination is dpm alpha and dpm beta / gamma ;,er 100 square centimeters.

8.

Which ONE of the following [isREC)

) ELE' NOT a f unction of the Demineralizer loop?

a. Provides an out of direct radiation field radioactivity monitor for the pool water.

b. Provides temperature contro; for the coolirig system.

c. Removes float;ng material from the rater surface of the pool,

o. Provides temperature control to turn off the primary pump when pool water cools to 80 'f.

9. Reactor pool water leakage collected in the hold-up tanks:

a. Must be disposed of at a nuclear waste collection facility.

b. May be treated and released if it meets NRC limits,

c. Must remain on site until-1994 in accordance with the Nuclear Waste Policy Act of 1982,

d. Is released after being held 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

Page 25

10. The Automatic Alarm System:

a. Has separate lines to several emergency agencies,

b. Only alerts certain plant personnel.

c. Goes to DENALECT, which, in turn, alerts other entities,

d. Simultaneously alerts DENALECT as well as others. -

11. During unattended hours at the plant, the Automatic Alarm System does not detect:

a. Unauthorized entry

b. Reactor pool water leak

c. Fire

d. High radiation

12. The ARRR control rods contain a neutron absorber of: .

.a. Cadmium

b. Boron Carbide

c. Gadolinium 0xide

d. Indium

13. Temporary fuel sterage racks may be placed in the reactor pool provided that, when fully loaded with fuel and fully moderated, the K effective will not exceed:

a. 0.90

b. 0.80

c. 0.50 ,

d. 0.08

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

a i niner. i i .. .m i i i mme

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Page 26

14. The two large red emergency buttons inside the front door of the facility have separate functions.

One button .

The other button .

Activation of these two buttons (does or does not) send an alarm to DENALECT.

15. With the following initial conditions:

1. Safety rod fully withdrawn

2. Regulating rod fully inserted

3. Shim rod half way out of core and moving in the outward direction (operator is depressing up switch) the wire in the safety rod drive motor breaks between the coil and the 300 ohm bias resistor. Assuming that the operator continues to Fress the UP switch for the shim rod but takes no other action and assuming that all automatic features operate correctly, what will be the position of each of the above rods two minutes after the wire f ails?

a. Safety rod - Fully withdrawn Regulating rod - Fully inserted Shim rod - Slightly over half way out of core

b. Safety rod - Fully withdrawn Regulating rod - Fully inserted Shim rod - Fully inserted

c. Safety rod - Fully inserted Regulating rod - Fully inserted Shim rod - Slightly over half way out of core o

d. Safety rod - Fully inserted Regulating rod - Fully inserted Shim rod - Fully inserted

'16. Wnich ONE of the following correctly describes the response to the safety rod "0N" light bulb burning out during reactor power operation?

a. The safety rod cannot be moved any further in the outward direction from its original position,

b. The safety rod cannot be driven in either direction from its original position.

c. The safety rod will scram due to an interruption of power to the magnet coil.

d. There is no affect of the bulb being burned out other than a loss of indication.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

Page 27

. 17. The reactor primary pump is inadvertently turned "off" during normal l reactor operation. Which ONE of the following correctly describes the l effect on cooling tower fan operation? The cooling tower fan: <

a. is also deenergized,

b. will operate if the water temperature in the sump is above setpoint.  !

I c, will only run in the manual "on" position. '

l

d. is prevented from operating without primary pump flow. j

18. Match the events in Column A to the correct response of the Denalect automatic alarm system in Column B. (Example f. 6, Note: the responses in Colrmn B may be used once, more than once or not at all)

Column A Column B

a. Unauthorized entry. 1. Automatic alarm - notification of A0 personnel and Sheriff.

b. Earthquake.

2. Automatic alarm - notification of

c. Fire. A0 personnel, Sheriff and Fire Dept.

d. Evacuation. 3. Automatic alarm - notification of

, A0 personnel and Fire Dept.

e. Radiation.

4. No automatic alarm or notification.

4

19. Which ONE of the following is the method used to differentiate between a graphite element and a fuel element?

a. By weight differential.

b. By the blue color of the fuel elements.

c. By the difference in shape.

d. By the size difference.

(***** -

CATEGORY C CONTINUED ON NEXT PAGE *****)

. _ . _ , - . . . . - . . , , ~ . . , . . . . _ . - , . , ~ . . . . - . - _

~

\

l Page 28 ,

20. Which ONE of the following correctly describes the minimum requirement that must be met in order to perform maintenance on more than one control rod guide sleeve?

a. All fuel must be removed from the reactor core.

b. No more than 28 fuel elements may remain in the reactor core.

c. Removal of 28 or more fuel elements from the reactor core.

d. Only one control rod guide sleeve can be removed at a time.

21. Which ONE of the following statements correctly describes the methoo used to ensure the operability of the Denalect Alarm System?

a. The system is tested weekly,

b. The system self-check monitors operability.

c. The system status lights are energized,

d. The system failure status lights are not energized.

(***** END OF CATEGORY C *****)

(********** END OF EXAMINATION **********)

.y.. .

Page 29

. Reactor Theory Thermodynamics, and facility Operating Characteristics

• ANEWER A-1 a .

• REFERENCE ARRR Training Manual Vol. 4 Sect.1.2.2 & Tab.1.1

• ANSWER A-2 b

• REFERENCE ARRR Tr aining Manual Vol. 4 $ect.1.2.2 _

• ANSWER A-3 b

• REFERENCE ARRR Training Manual Vol. 4 Sect.1.3.3 and 1.3.4 ,

• ANSWER A-4 b

• REFERENCE As 4tated on the rod worth curves, the Safety rod is worth $3.85.

Therefore the reactor is shutdown by $5.36 - $3.85 - $1.51 after safety rod withdrawal.

CR (i - keff) t (1CR CR 3 - keff)3 3 (1 - keff)3CR,/ (1 - keff$2 KeTfa 1/1-p where p$xB ~

Keff 1/1-(5.36 x 0.0079) 3 Keff 1/1-(1.51 x 0.0079)

CR 2 - CR,, 11/1-(5.36 x 0.0079)]

1 - [l/1-(1.51 x 0.0079))

- 3662 cpm ARRR rod worth curves.

ARRR Reactor Operator Training Manual, Vol. 4, Sec 1.2.1 & l.2.7.

• ANSWER A-5 a

• REFERENCE Equation sheet 4

I h'nt "

.- . . - . - . _ _ - . . - - . . . . - - . - - . . - . - - . . . _ . . - ~ _

t

.Page 30 l

• ANSWER A-6 b ,

• REFERENCE Tech. Specs. 5.1.2 & 5.1.3 / ARRR TH Vol. 4 Tig. 1.6 Solution: $3 max, allowed reactivity minus 50.80 min, reactivity decrement, minus 41.40 Xenon effect at equilibrium, minus $1.00 for the experiment leaves a reactivity of -50.20.

• ANSWER A-7 C

• REFERENCE ARRR 1H Vol. 2 Sect. V2 i

• ANSWER A-8  ;

b r

• REFERENCE Tech. Spec. 4.1

• ANSWER A-9 ,

b

• REFERENCE Tech. Spec. 5.3.2 ,

• ANSWER A-10

, 90 fuel Elements =

3300 grams 5000 grams

• REFERENCE Tech. Spec 5.1.1 / License Condition 2B(2) 1

• ANSWER A-ll l a

• REFERENCE Tech. Spec 4.2 & 7.3 *

• ANSWER A-12 C

• REFERENCE Equation Sheet (CR2 /CR ) = (1-Keff )/(1-Keffr )

(60/30)3 = (0.90)(13Keff,)

Kef f, = 0.95 l

Page 31

.

• ANSWER A-13 a

• REFERENCE 1M Vol. 4 Sect. 1.2.5

• ANSWER A-14 a

• REFERENCE ARRR TM Vg'l 4 Sect. 1.2.5 P, - P, e' " / t 7 (in P,/P ) / t 5 sec (in 250000 w/100 w) - 39.12

• ANSWER A-15 d

• REFERENCE ARRR TM Vol. 4 SECT. 1.2.4

• ANSWER A-16 ,

d.

• REFERENCE ARRR OTM, Vol 4, Sec 1.3.2. ,

• ANSWER A-17 b

• REFERENCE ARRR TH Vol. 4

• ANSWER A-18 d

• ANSWER ARRR TM Vol. 4

• ANSWER A-19 a.

• REFERENCE AGNIR Reactor Physics Tests, See VI.C.

• ANSWER A-20 a-

• REFERENCE ARRR TM VOL 4 Sect.1.3.3 and Table -1.3

-.. - . ~ . . . . - - - . . . . . . - . . - . . - . . . _ - . . - . . . . . - - , . . - . . . . . . . - . - . , . - . , ,

Page 32

- Normal and Emergency Operating Procedurts and Radi., logical Controls

• ANSWER B-1 c

• REFERENCE ARRR TH Vol . 4 Sect 1.3.5

• AfiSWER B-2 4

• REFERENCE ARRR TH Vol. 2 Sect !!! 4.6.B ,_

• ANSWER B-3 c 10%

• REFERENCE Tech. Spec. Table 2

• ANSWER B-4 C

• REFERENCE ARRR IM Vol. 1 Sect. 11 F y. 1

• ANSWER B-5 C ~

' REFERENCE Emergency Plan App. C

• ANSWER B-6 b

• REFERENCE Tech Spec. 7.3 ,

• ANSWER B-7 a

• REFERENCE ARRR Til Vol. 1 Sect. IV B.3 / ARRR TM Vol. 1 Sect. IV C

• ANSWER B-8 b

• REFERENCE ARRR 1H Vol. 1 Sect. Vll! 8.2

• ANSWER B-9 DOES, WOULD, GREATER THAN, 15

• REFERENCE ARRR TM Vol. 2 Sect. V 3.3

• ANSWER B-10 d,a -

• REFEDENCE ARRR Reactor Operator Training Manual, Vol.1. Sec. IV.C.3.b.

ARRR Reactor Operator 1 raining Manual, Vol. 2, Sec. V.

• ANSWER B-ll 4 Hrs, 13 Wks, 2 Yrs

• REFERENCE 10CFR55.53(e), 10CFR 55.21

• ANSWER B-12 b

• REFERENCE 10CFR20.1201

• ANSWER B-13 C

• REFE DCE 10CFRD'.202(b)(2)

• ANSWER B-14 d

• REFERENCE 2 2 D 8 - DR2b > DR b 2 /Da = DR 2 > DR2 = 500 mr/hr x 4 ft / 6 ft DR, =3 222mrfhr

• ANSWER B-15 b-

• REFERENCE ARRR Reactor Operator Training Manual, Vol.1, Sec. IV.C.2.a. pg. 7 (100'F - 70'F1.x 60 min - 221 min 8.14*/hr hr

• ANSWER B-16 d

• REFERENCE ARRR Technical Specifications, Sec. 12.1.3.2 & 12.2.2.

• ANSWER B-17 b.

• REFERENCE ARRR Emergency Plan, App. B, pg.17 of 29.

• ANSWER B-18 b

• REFERENCE ARRR Reactor Operator Trait.ing Manual, Vol.1, Sec. IV.C.2.

Control Rod Calibrating Procedure Pg 4 of 26

• ANSWER B-19 d

• REFERENCE ARRR Reactor Operator Training Manual, Volume 1, Sec. IV.D.

ARRR Critical Assembly & Power Calibration Procedures pg.11 of 26.

4

• ANSWER B-20 b

• REFERENCE ARRR Reactor Annunciator Responses, p. 4.

• ANSWER B-21 C.

• REFERENCE ARRR.0TM, Vol ol, _Sec IV, p 1.

.i

t Page 38

.

• ANSWER C-15

• C

• REFERENCE ARRR Reactor Operator Training Manual, Vol. 2. Sec IX.  ;

• ANSWER C-16  !

c.  !

• REFERENCE ARRR OTM, Vol 2, fig IX-4 -5.

• ANSWER C-17 b.

• REFERENCE ARRR OTM, Vol 2, p V-5.

• ANSWER C-18

a. 1

! b. 4 C. 3

d. 4

e. 2

• REFERENCE ARRR*0TH, Vol 1, Emergency Plan , p 7; Test bank.

• ANSWER C-19 a.

• REFEREilCE ARRR OTM, Vol 2, p 111-13.

• ANSWER C-20 c.

• REFERENCE ARRR OTH, Vol 1, Sec IV, p 11.

• ANSWER C-21 b.

• REFERENCE ARRR Test No 3, Ques Vill-1.

• • • • • • • • • • END OF EXAMINATION **********

vu - -- w ,

., . ~ .. -... ._ - . - .. - - _ _ - - - . _ - -. . - - - - .

. Page 35

• ANSWER B-22 ,

, a.

• REFERENCE ARRR, Operating Procedures, p 3.

• ANSWER B-23 a.

• REFERENCE ARRR, General Emergenc/ procedures, p 4.

E e

O r

4 p e - , , , -er- = O- M4 . es,wn d es ewy u e,-s****>4 , , , . . . . _ , , , . . ,e as e # .

y g ..p m , , _

~-, -r -

Page 36 Plant and Radiation Monitoring Systems

• ANSWER C-1 Heat Exchanger Demineralizer Downstream

• REFERENCE ARRR 1H Vol. 2 Fig. V.4

• ANSWER C-2 Storage Pit in Rad. Waste Room Vacuum Demineralizer *

• REFERENCE Plant Familiarity

• ANSWER C-3 Control Room

.100 Reactor Room

• REFERENCE ARRR TH Vol. I Sect. II Fig,1 & Sect. VI D.3 .

• ANSWER C-4 b =

• REFERENCE ARRR TH Vol. 2 Sect.11 2.1, 2.3, 2.6, 2.9, 2.10

• ANSWER C-5

.y

• REFERENCE .

Tech. Spec. 8.4.2

• ANSWER C-6 c

• REFERENCE ARRR TM Vol. 5 Sect. 6 l

l l

gr e .- w - .-,. --- ,v ,- . , , - . - , . . . . . , _ .....7..y.s,, . _ , . _ . .

,.s-i..,--

• ANSWER C-7 -

Quarterly '

30 1

. 200

• REFERENCE ARRR TM Vol.1 Sect. VI D. 5 E.lc

• ANSWER C-B t)EtJE11E[)

d

• REFERENCE ARRR 1!! Vol. V pg. V-5

• ANSWER C-9 b _ _ _

• REFERENCE 10CFR20.303

• ANSWER t-10 c

• REFERENCE ARRR TM Vol.1 Sect. Vil C.5

• ANSWER C-Il b

• REFERENCE ARRR GM Vol. 1 Sect. Vil C.5

• ANSWER C-12 b *

• REFERENCE ARRR IM Vol. 2 Sect. 111 4.12

• ANSWER C-13 b

• REFERENCE ARRR TM Voi.1 Sect. IV A.6

• ANSWER C-14 Sounds the Building Rad. Alarm Shuts down HVAC Systems Does Not-

• REFERENCE ARRR TM Vol. 2 Sect. Il 1/ Also Indoctrination

. .. - . - .- . - - -. .-