Text

Exam Rept 50-228/OL-88-01 on 880413.Exam Results:Of Two Candidates Administered Test,One Passed & Given Senior Reactor Operator License & One Failed Written Exam & Not Granted License.Master Copy of Test Encl
	ML20197F502
Person / Time
Site:	Aerotest
Issue date:	05/23/1988
From:	Coe D, Elin J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	;
Shared Package
ML20197F498	List: ML20197F493; ML20197F502;
References
	50-228-OL-88-01, 50-228-OL-88-1, NUDOCS 8806130339
	Download: ML20197F502 (156)
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Examination Report No. 50-228/0L-88-01 Facility: Aerotest Radiography and Research Reactor Docket No. 50-228 Examinations administered at Aerotest Operations, Inc. San Ramon, California.

NRC Chief Examiner:

M _m I/ 7 5'

Douglas H. Coe Date Operat r icen ng Examiner

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6/L)/6 Approved:

John lin, Chief Odte/

Ope ions Section Summary:

Examination on April 13, 1988 (Report No. 50-228/0L-88-01)

Two candidates were administered written and operating examinations.

One candidate for an SR0 license passed both sections of the examination and was given a license.

One candidate for an R0 license passed the operating examination but failed one section of the written examination and was not granteo' a license.

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6 REPORT DETAILS TYPE OF EXAMINATION:

Replacement EXAMINATION RESULTS:

R0 SRO Pass / Fail Pass / Fail Operating Exam 1/0 1/0 Written Exam 0/1 1/0 Overall 0/1 1/0 1.

CHIEF EXAMINER AT SITE:

W. S. Roesener (EG&G) 2.

PERSONNEL PRESENT AT EXIT INTERVIEW:

Contractor Personnel W. S. Roesener (EG&G), Chief Examiner Facility Personnel R. L. Newacheck, President I. Lamb, Reactor Supervisor 3.

SUMMARY

OF NRC COMMENTS MADE AT EXIT INTERVIEW:

A.

Future reference packages to the NRC for test preparations should include the following in addition to what was sent for this exam:

i.

Experimental procedures ii.

Core loading (1/m) procedures iii.

Surveillance procedures iv.

Hazards Report v.

FSAR vi.

Technical Specification bases if not part of iv I

or v above.

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B.

References are made to instrumented fuel elements in the written reference material provided.

Present status of these elements should be included in reference materials.

C.

The Radiological Safety Of ficer did not initial the Operations Request Form for approval of the Ion Exchanger resin change-out.

The facility reviewed the appropriate forms and made the necessary corrections.

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A drip was noted off the inlet piping to the Ion Exchanger.

The facility investigated the leak and determine that no significant problem existed.

The leak was cleaned up.

E.

It was recommended that production schedule conflicts be clearly explained to the NRC in advance of the exam, and that requests for early morning ar.'d/or evening exams be made in advance of examiners arrival on site.

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NRC Official Use Only i%

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Nuclear Regulatory Commission Operator Licensing Examination a

e This document is removed from Official Use Only category on date of examination.

NRC Official Use Only MAS"RCOPY

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NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY:

ARRR l

REACTOR TYPE:

TRIGA DATE ADMINSTERED:

88/04/13 EXAMINER:

ROESENER, S.

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CANDIDATE INSTRUCTIONS TO CANDIDATE:

Use separate paper for the answers.

Write answers on one side onl y.

Staple question sheet on top of the answer sheets.

Points /or each question are indicatet in parentheses after the question.

The passing grade requires at least 70% in each category.

Examination papers will be picked up six (6) hours after the examination starts.

% OF CATEGORY

% OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 14.00 14.00 A.

PRINCIPLES OF REACTOR OPERATION 14.00 14.00 B.

FEATURES OF FACILITY DESIGN 13.50 13.50 C.

GENERAL OPERATING CHARACTERISTICS 15.00 15.00 D.

INSTRUMENTS AND CONTROLS 13.50 13.50 E.

SAFETY AND EMERGENCY SYSTEMS 15.00 15.00 F.

STANDARD AND EMERGENCY OPERATING PROCEDURES 15.00 15.00 G.

RADIATION CONTROL AND SAFETY 100.0 Totals pg - ni Final Grade All work done on thi s examination is my own.

I have neither given nor received aid.

i Candidate's Signature

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

of your application the examination means an automatic denial 1.

Cheating on severe penalties.

and could result in more a time may limited and only one candidate at 2.

Restroom trips are to be leave.

You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

3.

Use black ink or dark pencil only to f acilitate legible reproductions.

4.

Print your name in the blank provided on the cover sheet of the examination.

5.

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

for answers.

Use only the paper provided 6.

in the upper right-hand corner of the first page of each 7.

Print your name section of the answer sheet.

B.

Consecutively number each answer sheet, write "End of Category __" as write only on one side appropriate, start each category on a new page, of the paper, and write "Last Page" on the last answer sheet.

for example, 1.4, 6.3.

answer as to category and number, 9.

Number each

10. Skip at least three lines between each answer.

answer sheets face sheets from pad and place finished

31. Separate answer down on your desk or table.

12. Use abbreviations only if they are commonly used in facility literature.

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

14 Show all calculations, methods, or assumptions used to obtain an answer to mathematical prob. ems whether indicated in the question or not.

Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE 15.

QUESTION AND DO NOT LE, AVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the examiner only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in This must be done after the examination has completing the examination.

been completed.

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examination, you shall

18. When you complete your Assemble your examination as follows:

a.

(1)

Exam questions on top.

(2)

Exam aids - figures, tables, etc.

(3)

Answer pages including figures which are part of the answer, b.

Turn in your copy of the examination and all pages used to answer the examination questions.

Turn in all scrap paper and the balance of the paper that you did c.

not use for answering the questions.

as defined by the examiner.

If after d.

Leave the examination area, while the examination is still are f ound in thi s area l eavi ng, you license may be denied or revoked.

in progress, your i

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PRINCIPLES OF REACTOR OPERATION f

A.

QUESTION A.01 (2.00) a.

Define Bath Temperature Coefficient.

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Define Prompt lemperature Coefficient.

QUESTION A.02 (2.00) a.

How does a fuel temperature increase result in the hardening of the neutron spectrum?

b.

How does hardening of the neutron spectrum result in a decrease in reacti vi ty?

QUESTION A.03 (2.00)

Define BETA EFFECTIVE.

a.

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QUESTION A.04 (1.00)

Why has the strength of the installed neutron source increased since i t i

i was originally installed?

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QUESTION A.05 (1.00) a.

How long does it take Xenon to buildup to equilibrium from a Xenon free condition?

b.

How long does it take for Xenon to peak after shutdown from equilibrium Xenon conditions?

QUESTION A.06 (1.00)

What is the increases from 40 to 60 watts in 20 seconds.

Reactor power reactor period associated with this power i ncrease?

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(*****

CATEGORY A CONTINUED ON NEXT PAGE

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A.

PRINCIPLES OF REACTOR OPERATION Pego 5

DUESTION A.07 (1.00)

/- $.01, associated with a What is the approximate core reactivity,

+

period of 10 seconds?

QUESTION A.08 (1.00)

Why is graphite a better reflector than water?

QUESTION A.09 (3.00)

If the reactor was operating at 250 kW when the safety rod was dropped the power woul d immedi atel y drop to about 50 kW and then decay slowly to a final steady state value of a few thc;usand counts per second.

(Note:

in answering the questions below, calculations are neither required nor desired.)

a.

The loss of what component of the neutron flux causes the sharp drop in power?

b.

What determines the rate of power decrease at about five minutes after the rod i s dropped?

Why does the power stabilize after approximately one hour when keff c.

is less than 1.O?

(*****

END OF CATEGORY A

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B.

FEATURES OF FACILITY DESIGN QUESTION B.01 (2.00)

What are the TWO purposes for maintaining high pool water purity?

QUESTION B.02 (1.00)

What are the Technical Specification pH AND conductivity l i mi ts?

QUESTION B.03 (1.00)

What design feature of the pool makeup system prevents overflow of the pool?

QUESTION B.04 (1.00)

What is the purpose of the foot valve in the suction line to the primary pump?

QUESTION B.05 (2.00) a.

Is it possible to siphon the pool below the Technical Specification level limit via the suction line if a break occurs in the primary coolant loop?

Explain specifically how it would occur or what would prevent it.

b.

Is it possible to siphon the pool below the Technical Specification level limit via the discharge line if a break occurs in the primary coolant loop?

Explain specifically how it would occur or what would prevent it.

QUESTION B.06 (1.50)

How is the control rod piston prevented from slamming into the bottom of the barrel?

(*****

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

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D2__EE9IUBEg_gE_E891bily_QgQN t \\ QUESTION B.07 (1.00) What is the approximate vertical travel of a control rod during normal operations? An accuracy of +/- 1 0*/. is required. 1 QUE ON B.08 (3.00) Using e top view of the core provided in Attachment 0-1, i ndicate the following or the present core configuration: a. location o e regulating rod. } b. location of the s ty rod. c. location of the source. d. location of the Glory Hole, e. outline of ONE of the two TRIANGULAR radiation f acilities. f. name of the component located at G10. i QUESTION B.09 (1.50) a. From what mater i al (s) is the shield portion of the beam catcher shield made? (0.50) b. What is the height of the shielding material (s)? (1.00) i i (***** END OF CATEGORY B

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2 1 C. GENERAL OPERATING CHARACTERISTICS Pago 8 l QUESTION C.01 (1.00) Why is the primary pump switched on at startup rather than waiting for the temperature switch to activate? QUESTION C.02 (1.00) What is the name of the heat transfer process that cools the CORE? QUESTION C.03 (1.00) Cal cul ate the time (in minutes) it wtuld take the pool water to rise f rom 70 to 100 F if the reactor was operating at 250 kW. A copy of the calorimetric procedure is included as Attachment Q-2. Assume a normal pool level. An accuracy of +/- 5 minutes is required. QUESTION C.04 (1.00) Multiple Choice With the reactor pool outlet initially at 80 F and the reactor at 250 kW, a reduction in primary flow rate f rom normal to 100 gpm wills a. Eventually result in a reactor scram if no operator action is taken. b. Result in an immediate scram, c. Cause the cooling tower fan to operate more frequently. d. Result in a higher steady state pool outlet temperature. I l QUESTION C.05 (1.00) Considering that the Safety rod and Shim rod are both located in the same ring, why is the safety rod worth more than the shim rod f or the present core loading scheme? (***** CATEGORY C CONTINUED ON NEXT PAGE

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C. GENERAL OPERATING CHARACTERISTICS Page 9 QUESTION C.06 (2.00) Assuming that the rod worths are not affected significantly, what would be the affect, if any, of moving the Glory Hole closer to.the center of the core on: a. the critical rod position at 1000 watts? b. the change in rod position from 1000 watts to 250 kW? QUESTION C.07 (2.00) List FOUR ways in which ARRR personnel may adjust excess reactivity such that the limit of Technical Specification section 5.1.2 is approached. Technical Specification 5.1.2 states that: The maximum excess reactivity above cold clean critical, with or without experiments in place, shall be 3 dollars. QUESTION C.OB (1.50) Given that the reactor is critical at.01 watt, what behavior / trend would you expect to observe on the f ollowing 17struments? a. Rod position indications. b. Period meter. c. Channel #1 count rate. QUESTION C.09 (3.00) With all rods in, c ol d, Xe free, the count rate is 1000 com and the reacti vi ty i s -$5. 36. What final count rate would you expect to see if the safety rod was completely wi thdrawn ? Show all work. i (***** END OF CATEGORY C

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D. INSTRUMENTS AND CONTROLS Pcga 10 t QUESTION D.01 (2.50) a. With the Regulating rod in the full down posi tion the UP pushbutton is depressed. The foot microswitch fails such that it will not change position from the normal control rod down posi t i on. Describe the sequence of rod motion AND rod indicator lamp changes for this situation. Attachment G-3 showing the rod drive, motor control and indicator lamp circuit is included for your use. b. With the Safety rod in the full up position, the DN pushbutton is depressed. The foot microswitch fails such that it will not change position from the normal control rod up position. Describe the sequence of rod motion AND rod indicator lamp changes for this situation. Attachment Q-3 showing the rod drive, motor control and indicator lamp circuit is included for your use. QUESTION D.02 (3.00) With the following initial conditions: 1. Safety rod fully withdrawn 2. Regul ati ng rod fully inserted 3. Shim rod half way out of core and moving in the outward direction (operator is depressing up switch) l the wire in the safety rod drive motor breaks between the coil and the 300 ohm bias resistor. Assuming that the operator continues to press i 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 cwo minutes after the wire fails? QUESTION D.03 (1.50) Refer to Attachment Q-4 and name the components identified as A through F. (***** CATEGORY D CONTINUED ON NEXT PAGE

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I I D. INSTRUMENTS AND CONTROLS Page 11 QUESTION D.04 (2.00) a. State the major reaction that produces ionizing particles f rom neutrons in the Channel 1 neutron detector, b. In what form is the material which reacts with neutrons in the channel 1 neutron detector? QUESTION D.05 (1.00) What is the function of the discriminator in the Channel 1 neutron detector? QUESTION D.06 (2.00) a. WHY is the LCRM (Log Count Rate Meter) turned off during a normal startup to f ull power operation? (1.00) b. At what power level is the LCRM (Log Count Rate Meter) turned off during a normal startup to full power operation. (0.50) c. Which detector channel supplies the signal which secures pcWer to the LCRM? (0.50) QUESTION D.07 (1.00) What would be the indication during a normal shutdown following eight hours of full power operation of a compensated ion chamber that was overcompensated? l (***** CATEGORY D CONTINUED ON NEXT PAGE

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t Page 12 D. INSTRUMENTS AND CONTROLS QUESTION D.08 (2.00) e Match the appropriate regi on (s) of gas amplification curve operation as listed in column B to the detectors listed in column A. Each detector listed in c ol umn A has only one correct response in column B. Column B responses may be used more than once. Column B Column A a. Channel #1 1. Region I (Recombination) b. Channel #2 2. Region II (lon Chamber) c. Pocket Dosimeter 3. Region III (Proportional) d. Waste water tank radiation 4. Region V (Geiger) monitor 5. Region I and 11 6. Region II and III (***** END OF CATEGORY D

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h' b E. SAFETY AND EMERGENCY SYSTEMS Page 13 e QUESTION E.01 (3.00) List SIX of the seven scrams and the specific Technical Specification setpoints associated with the Channele #1, 2 and 3 of neutron detectors. Jeleted QUESTION E.02 (1.00) The Magnet Relay Interlock elay, K69A, prevents re-energizing of the scram relay, K3808, 11owing a scram as long as power remains above disconnect. Wh is the reason for this interlock? QUESTION E.03 (1.00) What two components of the earthquake detector change positions to cause a loss of power to the rod magnet and scram power circuit? QUESTION E.04 (1.50) a. What kind of detector is used to initiate a pool water high temperature scram? (1.00) l b. What is the Technical Specification set poi nt for the high temperature scram? (0.50) QUESTION E.05 (3.00) Interlocks prevent safety rod withdrawel unless FOUR conditions are met. One of these conditions is that the startup channel count rate must be greater than its setpoint. State the other THREE conditions. QUESTION E.06 (1.00) The reactor safety systems are required by Technical Specificaitons to be FAIL-SAFE. Define FAIL-SAFE when used in this context. (***** CATEGORY E CONTINUED ON NEXT PAGE

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l Pago 14 E. SAFETY AND EMERGENCY SYSTEMS l r Y QUESTION E.07 (3.00) a. State the location of the emergency button which is pressed to lock (0.50) out power to the Air Handling Relay. b. List the FIVE ventilation components that Hill automatically be(2.50) secured by pressing the Air Handling Relay Lockout. l (***** END OF CATEGORY E

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F. STANDARD AND EMERGENCY OPERATING PROCEDURES Pcge 15 QUESTION F.01 (1.50) a. According to Technical Specifications what is the minimum number of personnel that must be present for reactor op er at i ons: to be (0.50) permitted. b. In accordance with Technical Specifications what is the license level, if any, required of each person on the minimum reactor (1.00) operating crew. DUESTION F.02 (2.00) According to ARRR Operating Procedures, what are the f our specific times when the presence at the facility of an SRO would be required? GUESTION F.03 (1.00) Under what conditions is an unlicensed person allowed to operate the reactor controls? QUESTION F.04 (1.00) According to the Technical Specification definitions, what are the TWO , methods of securing the console key? QUESTION F.05 (2.50) a. What action must the operator take when reducing power across disconnect to prevent the reactor from scramming? (1.00) b. How long does the operator have to take the above actions af ter going below the disconnect power? (0.50) c. In addition to the indicated nuclear instrument power level, how is the operator alerted to the f act tiie he is below disconnect? (1.00) Ther rke fown:r (t**** CATEGORY F CONTINUED ON NEXT PAGE

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F. STANDARD AND EMERGENCY OPERATING PROCEDURES Pags 16 QUESTION F.06 (2.00) State the TWO actions which should be taken immediately by the reactor oper ator if the reactor automatically scrams during normal operation at 250 kW. QUESTION F.07 (1.00) During a reactor startup, with the safety rod fully withdrawn and the regulating rod being withdrawn, the building begins to shake. The shaking continues for a few seconds and appears to be increasing in magnitude. An automatic scram has not and should not have occurred (the setpoint of the earthquake monitor has not been reacned). What action should be immediately taken by the operator? QUESTION F.OB (3.00) Upen receipt of a water radioactivity alarm; the operator immediately begins to monitor the water and air radiation levels. The reactor was operating at 250 kW when the alarm was received. a. What TWO actions should the operator take immediately if both the monitors are increasing? b. If the rate of increase is fairly rapid what TWO additional actions should be taken? QUESTION F.09 (1.00) In accordance with the Reactor Annunciator Responses guide, why does the failure of the demineralizer pump force a shutdown of the reactor? (***** END OF CATEGORY F

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e G. RADIATION CONTROL AND SAFETY Page 17 4 QUESTION G.01 (1.00) If two centimeters of lead placed at a certain location in a beam of gamma rays would reduce the gamma radiation level from 100 mR/ hour to 50 mR/ hour, what thickness of lead placed in this beam would reduce the gamma radiation level from 400 mR/ hour to 50 mR/ hour? QUESTION G.02 (1.00) What is the purpose of a Quality Factor as used in a calculation to convert rad to REM? QUESTION G.03 (1.50) With regards to the ARRR ALARA programs a. What is the weekly cumulative whole body exposure limit? b. Who may approve exceeding the ARRR weekly whole body limit? c. What is the quarterly whole body exposure level above which an investigation of the type and circumstances of the exposure must be performed? QUESTION G.04 (2.50) Define the f ollowing in accordanta with 10CFR20s (1.50) a. Radiation area b. Restricted area (1.00) QUESTION G.05 (1.00) Why is the Glory Hole purged with carbon dioxide? (***** CATEGORY G CONTINUED ON NEXT PAGE

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I G. RADIATION CONTROL AND SAFETY Pcge 18 t QUESTION G.06 (1.00) Multiple Choice t If the reactor was at 250 KW and one central fuel element failed, what would be the dose received in the f.rst hour by an i ndi vi dual standing in the middle of the reactor room. Assume that the i nd i vi dual did not evacuate as he should have, a. O - 25 mr b. 50 - 75 mr c. 250 - 300 mr d. 475 - 525 mr QUESTION G.07 (1.00) State TWO of the THREE radioactive gases of major concern during a fuel element failure. QUESTION G.OB (2.50) a. State the type and meter range of the TWO portable radiation detectors required by Technical Specifications. (2.00) b. What type of radiation is the "pancake counter" used at ARRR designed to detect? (0.50) QUESTION G.09 (1.50) The following questions apply to the fixed gamma monitor required by Technical Specifications. a. What is the setpoint as stated in the Technical Specifications? (0.50) b. Upon reaching setpoint, in what TWO locations must alarms be sounded in accordance with Technical Specifications? (1.00) l i (***** CATEGORY G CONTINUED ON NEXT PAGE ses**) j l

G. RADIATION CONTROL AND SAFETY Pege'19 QUESTION G.10 (2.00) i The f oll owing questions apply to the fixed detector required by Technical Specifications for monitoring of radi oac ti ve gasses. a. State the two sample points, either of which must be monitored in order to be in compli ance with Technical Specifications. (1.00) -ej b. In what location is there required to be a continuous detector readout? (0.50) c. What is the Technical Specification setpoint of the annunciator associated with the fixed detector? O J0. l l l l i i 1 (***** END OF CATEGORY G

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(********** END OF EXAMINATION **********) 4

A. PRINCIPLES OF REACTOR OPERATION Pcg2 20 ANSWER A.01 (2.00) a. The change in reactivity associated with a change in the bath (pool) (1.00) temper ature. b. Tne change in reactivity associated with a change in the fuel (1.00) l temperature. REFERENCE ARRR Training Test #7. ARRR Reactor Operator Training Manual, Vol. 4, Secs. 1.3.3 L 1.3.4 ANSWER A.02 (2.00) a. Temperature increase causes increased thermal vibration of the Hydrogen atoms in the Zirc-Hydride matrix CO.503 which then results in increased neutron energies (harder spectrum) following scattering by the Zirc-Hydride CO.503. b. As the neutron spectrum hardens, more neutrons escape f rom the f uel CO.503 and are absorbed in the non-fuel (moderator, reflector, core structure) portions of the core CO.503. f REFERENCE r ARRR Reactor Operator Training Manual, Vol. 4, Sec. 1.3.2 L 1.3.3. l l l 1 ANSWER A.03 (2.00) a. The #raction of the thermal neutron population that was born delayed. (1.00) b. Since delayed neutrons are born at lower energies than prompt neutrons (0.503 they are more likely to reach thermal energies CO.503. (Therefore, the fraction of delayed neutrons at thermal energies (beta effective) is greater than the fraction of delayed neutrons at birth (beta).) C C 2-w+ L. (***** CATEGORY A CONTINUED ON NEXT PAGE

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h e A. PRINCIPLES OF REACTOR OPERATION Paga 21 REFERENCE ARRR Reactor Operator Training Manual, Vol 4, Sec 1.2.2. Other standard texts for example Lamarsh's," Nuclear Reactor Theory", Sec. 12-5. ANSWER A.04 (1.00) Neutron transmutation in the source CO.503 has created a more active alpha emitter CO.503. OR Americium 241 has been converted to Curium 242 by neutron capture CO.503 and curium 242 is a more active alpha emitter [O.503. REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. 111.4.8. ANSWER A.05 (1.00) a. 60 hours +/- 15 hours. (0.50) b. 3-7 hours. (0.50) REFERENCE ARRR Reactor Operator Training Manual, Vol. 4, Sec. 1.3.7. ANSWER A.06 (1.00) 1 4 4?. 3 t)r Ln(n /n ) = 20 sec k un(60/40) =_S.i / .5 seconds. T = 1 O [0.75 for correct equation. O.25 for correct result.3 (***** CATEGORY A CONTINUED ON NEXT PAGE

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I ? A. PRINCIPLES OF REACTOR OPERATION Pega 22 REFERENCE ARRR Reactor Operator Training Manual, Vol. 4, sec. 1.2.5. ANSWER A.07 (1.00) Using the Inhour graph S.35 +/-5.01. REFERENCE ARRR Reactor Operator Training Manual, Vol. 4, sec. 1.2.5. ARRR Reactor Operator Training Manual, Vol. 1, sec. IV, Figs. II & III. ANSWER A.OB (1.00) Because graphite has a significantly lower neutron absorption cross section. REFERENCE ARRR Reactor Operator Training Manual, Vol. 3, Sec. RT-5.II.C. ANSWER A.09 (3.00) (1.00) a. The prompt component. b. After five minutes the power decrease is controlled by the decay of (1.00) longest lived delayed neutron precursor. c. Subtritical multiplication (of core source neutrons) causes the power to stabilize. (1.00) REFERENCE ARRR Reactor Operator Training Manual, Vol. 4, Secs. 1.2.5 & 1.2.7. (***** END OF CATEGORY A

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~r 1 b D. FEATURES OF FACILITY DESIGN Pega 23 ANSWER B.01 (2.00) 1. Minimizes corrosion [1.003. , 3, ptas clew asuI <>spub% oF r < W "T "O O1 ('g47 wnr) / 2. Mi ni mi z es induced radioactivity [1.00]. u REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. V.2. ~ ANSWER B.02 (1.00) (corrective action shal* be taken to avoid exceeding) 1. 7.5 pH [0.503 2. 5 micromho/cm conductivity [0.503. REFERENCE ARRR Technical Specifications, Sec. 4.2. 4 ANSWER B.03 (1.00) The two pool level controlled float valves in series in the makeup supply line. REFEHENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. V.2. i ANSWER B.04 (1.00) Prevents loss of prime when the pump is not operating. (***** CATEGORY B CONTINUED ON NEXT PAGE

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l ( B. FEATURES OF FACILITY DESIGN Paga 24 ) 1 REFERENCE ARRR Eeactor Operator Training Manual, Vol. 2, Sec. V.3.1. s l ANSWER B.OS (2.00) a. No. The suction line extends only one foot below the normal water (1.00) level. b. No. inc ditch li-e 'Chec' et f :il.ty t

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r4= ei r ' s aim, c= I thr=. sr.ancara cesign i r. L u. but w;; r. c, t aie. ii vi -w ir the t ex t 3 j's e-l is A ~ e ** (1.001 f.ic po o' n' in T h c. cli s chey e /,ne e x re w < / To Yhe Thsn o n e-Sv* r below rke rtoresl water freel. REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. V.3.1. ARRR 1 raining Guides and Tests, Study Handout No. 2, Guestion 2. CAF ANSWER B.06 (1.50) The graded vents in the bottom of the barrel CO.503 combine with the control rod piston CO.503 to create a dashpot action CO.SO3. ) REF EilEf.CE ARRR Reactor Operator Training Manual, Vol. 2, Sec. 111.4.12. ARRR Training Guides and Tests, Examination 6, Question 23. ANSWER B.07 (1.00) 2.0 15 in. ( + / Vri n. ) (***** CATEGORY B CONTINUED ON NEXT PAGE

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f 8:__EE9295ES_9E_E991hlII_9E919td Pcgo 25 REFERENCE ARRR Reactor Operator Training Manual, Vol. 2. S e c. il I 1. (*. I1. 'NSWER B.08 (3.00) sed on January 1988 core loadsng. en e r e,' a /o r. n'e A r-4), ll e e ef r 50 J /4. (Each 0.50) ne4 rs ;, p.,r> a k, c, a a <l cl. See etch below +or a to e. co j end a dlre ss is hery irr, sr be cor'eer r. 'O'50' +. Fue1. ement. ce c ce di r t.,lIl be h r. ~ ~ - - see x / O O \\ \\ l t. GL I2 OI h 3o l'O' C6 o El Ft I, a st j \\ O GLORY Notg / 8 ma REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. 111.4.3, Fig. I!!-4 ANSWER B.09 (1.50) A' W A X', Lesd,a'd bero n.

Chach at i a r-4 1 ' t ; :

b. 12 o' A e L e s 2 .2 o'n c l. e s (***** CATEGORY B CONTINUED ON NEXT PAGE

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b 1 Pcgo 26 B. FEATURES OF FACILITY DESIGN REFERENCE Check at facility. (***** END OF CATEGORY D

4***)

v r C. GENERAL OPERA 11NG CHARACTERISTICS Pego 27 ANSWER C.01 (1.00) To reduce the level of Nitrogen-16 radiation at the surface of the pool. REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. V.2. ARRR Training Guides and Tests, Test No. 1, Question 4. ANSWER C.02 (1.00) Natural convection. REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. V.3. ANSWER C.03 (1.00) 225 min +/- 5 min. (30 F/ (B F/hr) ) x 60 min /hr = REFERENCE ARRR Reactor Operator Training Manual, Vol. 1, Sec. IV.C.3.a. ANSWER C.04 (1.00) i d REFERENCE ARRR Reactor Operatt.- Training Manual, Vol. 1 Sec. IV.C.".b. ARRR Reactor Operator Training Manual, Vol. 2, Sec. V. l (***** CATEGORY C CONTINUED ON NEXT PAGE *****) _l

+ C. GENERAL OPERATING CHARACTERISTICS Pcgo 28 i ANSWER C.OS (1.00) i (The core loading is skewed and as a result) the Safety rod is located in a region of higher flux. REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, III-4, Core Loading (January 1989) ANSWER C.C6 (2.00) a. The cri tical rod position would be higher. b. The change in rod position would not be af f ected. REFERENCE AGN1R Reactor Physics Tests, Fig. 9, Core component reactivity worth as a function of core position. ARRR Reactivity Loss to Power Procedure. ANSWER C.07 (2.00) Any four of the following at 0.50 eacht 1. Adding fuel. 2. Shuffling fuel. 3. Changing fuel (ref ueling). i 4. Adding experiments of positive worth. 5. Adding graphite. 6. Shuffling graphite. 1 (***** CATEGORY C CONTINUED ON NEXT PAGE

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r k C. GENERAL OPERATING CHARACTER 1STICS Page 29 REFERENCE ARRR Technical Specifications, 5.1.2. ARRR Reactor Operator Training Manual, Vol. 1, Sec. IV.B.2. ANSWER C.08 (1.50) - ( 0. 50) a. No motion. b. 2ECO 'er SLIE"TLY p :itic ?. To Wa,'ry. (0.50) c. Stable (or SLOWLY increasing). (0.50) REFERENCE ARRR Reactor Operator Training Manual, Vol. 4, Sec. 1.2.7. l ~ (***** CATEGORY C CONTINUED ON NEXT PAGE

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1 L

C. GENERAL OPERATING CHARACTERISTICS Pega 30 t s ANSWER C.09 (3.00) As stated on the rod worth curves attached to the test, the Safety rod is worth s3.85. Theref ore the reactor is shutdown by $5.36 - s3.85 = $1.51 after safety rod withdrawal. From the equation sheet the proper equations to use are k ) C (1 C (1 -k ) = 1 1 2 2 AND 1/p> 1/(1 = (k - 1)/k which means 1 -k = p where p = rho. Alternatively k can be calculated as shown below ar.d directly substituted into the first equation above. Of course the final answer will still be the same. k = 1/(1 - p) Additionally, it is necessary to convert dollars to p using p=$ x Beta Combining the above gives: 1/p ) 1/p ) / (1 Final count rate = Initial count rate (1 final initial 3446 cpm. 1/(5.36 x.0079)) = 1/(1.51 x.0079)) / (1 1000 (1 = Grade as follows: 2.00 f or proper use of equations. 0.50 f or calcul ation of reactivity with rod withdrawn. 0.50 for use of proper value of beta,.0079. REFERENCE ARRR rod worth curves. ARRR Technical Specifications, 5.1.2. ARRR Reactor Operator Training Manual, Vol. 4, Sec 1.2.1 & 1.2.7. (***** END OF CATEGORY C

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}

D. INSTRUMENTS AND CONTROLS Pago 31 ANSWER D.01 (2.50) Sequence of motor and lamp events. CPoints for each individual event as shown, 0.25 points per question a and b for completely correct sequence, loss of 0.25 points for each incorrect event.] a. 1. Rod starts to drive out CO.253. 2. DN and CONT lamps extinguish [0.25 each3 (1.25) and rod motion stops CO.253. b. 1. Rod starts to drive in t' O. 2 5 3. 2. UP lamp i s extinguished [0.253. 3. DN lamp is lit CO.253 and rod motion ceases CO.253. (1.25) REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec IX. ANSWER D.02 (3.00) 1. Safety rod - Fully inserted [1.003. 2. Regulating rod - Fully inserted C1.OO3. 3. Shim rod - Half way out of core OR just slightly over half way out of core (due to small amount of time to actuate the safety rod MAG UP switch) [1.003. REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec IX. ANSWER D.03 (1.50) A - Magnet wire conduit B - Motor (motor cover) C - Potentiometer (potentiometer cover) i D - Magnet E - Armature (0.25 each) F - Connecting rod REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec III, Fig. III-10. (***** CATEGORY D CONTINUED ON NEXT PAGE

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I Pago 32 D. INSTRUMENTS AND CONTROLS s ANSWER D.04 (2.00) a. 10 1 7 4 B+ n --> Li + HE (Alpha) 5 O 3 2 OR B(n, alpha)Li DR Boron-10 combines with a neutron to produce Lithium and an alpha (1.00) particle. (1.00) b. As B C. 4 REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec VIII. ANSWER D.05 (1.00) It discards the pulses caused by gamma interaction in the detector. l REFERENCE ARRR Reactor Operator Traioing Manual, Vol. 2, Sec VIII. ANSWER D.06 (2.00) a. The LCRM is turned off to protect the Channel #1 neutron detector from damage (that would occur if it remained energized in a high (1.00) radiation field) (0.50) 6. 10 E -10 amps. (0.50) c. Channel #2. (***** CATEGORY D CONTINUED ON NEXT PAGE *****)

D. INSTRUMENTS AND CONTROLS Paga 33 REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec IX, Figs. IX-4 & 5. ANSWER D.07 (1.00) The indication will read low off-scale (and then slowly return to an on-scale reading). C) R re a d. j REFERENCE Lover sh<n ir aanJ0 norm s 07 ARRR Training Guides and Tests, Test No. 3, Question III.4. \\ 1 l ANSWER D.OB (2.00) ) a. 3 b. 5 f c. 2 (2.00) d. 4 REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec VII. ARRR Reactor Operator Training Manual, Vol. 2, Sec VIII. Glasstone and Sesonske, Nuc!?ar Reactor Engineering, Sec. 5.240 to 5.255 and 9.152. l i (***** END OF CATEGORY D *****)

r Page 34 E. SAFETY AND EMERGENCY SYSTEMS ANSWER E.01 (3.00) Any six of the following at 0.25 for each scram and 0.25 for each setpoint: Channel #1 Low Source Level - Greater thar, or equal to 2 cps. Short Period - Greater than or equal to 3 sec. Channel #2 Greater than or equal to 3 sec. Short Period Low Voltage - Greater than or equal to 500 volts. Channel #3 High Flux Level - Less than or equal to 98'/. of full scale not to exceed 120% full e ower. Low Flux Level - Greater than or equal to 5% of full scale. Greater than or equal to 500 volts. Low Voltage REFERENCE ARRR Technical Specifications, Table 2. a, lerej ANSWER E.02 ( 00), Prevents star up witP channel #1 scrams bypassed. j i REFERENCE ARRR Re, tor Operator Training Manual, Vol. 2, Sec. IX. l ANSWER E.03 (1.00) 1. The balanced ball C O. 50 3. 2. The switch beneath the ball CO.503. l = (***** CATEGORY E col 4TINUED ON NEXT PAGE

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E. SAFETY AND EMERGENCY GYSTEMS Pcgo 35 REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. IX, Fig. IX-5. ARRR Technical Spec i f i cati ons, Table 2. ANSWER E.04 (1.50) (1.00) a. A bimetallic switch. 6. Less than or equal to 130 F. (0.50) REFERENCE c ARRR Reactor Operator Training Manual, Vol. 2, Sec. IX, Fig. IX-5. ARRR Reactor Operator Training Manual, Vol. 2, Sec. V.2. ANSWER E.05 (3.00) 1. The master switch must be in the on position C1.003. 2. The saf ety system must be reset C1.003. 3. All four nuclear instruments must be in the operate mode C1.003. REFERENCE ARRR Technical Specfications, Sec. 6.5. ANSWER E.06 (1.00) De-energizing of the reactor safety systems shall cause a scram. j REFERENCE ARRR Technical Spccifications, Sec. 6.1. (*ss** CATEGORY E CONTINUED ON NEXT PAGE ***ss)

i I [ E. SAFETY AND EMEFGENCY SYSTEMS Pcgo 36 i e ANSWER E.07 (3.00) (0.50) a. Near the control room outside door. l' b. Rest room vent fans. High bay air conditioner. Chemical laboratory hood exhaust fan. High bay heaters (Unit heater fans). (2.50) N-Ray Set-Up room furnace. REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. 11.2. s I o 5 L l l l l (***** END OF CATEGORY E *sses) j

Fo STANDARD AND EMERGENCY OPERATING PROCEDURES Page 37 ANSWER F.01 (1.50) (0.50) a. TWO (1.00) b. One must be a licensed Operator. REFERENCE ARRR Technical Specifications, Sec. 10.1. Training Guides and Tests, Test #1, Question 1. I ANSWER F.02 (2.00) 1. During initial startup and approach to power. 2. During refueling. 3. During recovery from an unplanned shutdown. 4. During significant power reductions. i REFERENCE ARRR Operating Procedures, Sec. C.2. ANSWER F.03 (1.00) When the unlicensed i ndi vi dual is under the direction and in the presence of a licensed operator (RO or SRO) LO.503 and the operation is part of the individuals training (to qualify for a license) CO.503. REFERENCE 10CFR55.13. Training Guides and Tests, Study Handout #4. (esses CATEGORY F CONTINUED ON NEXT PAGE sesse)

[ F. STANDARD AND EMERGENCY OPERATING PROCEDUKE3 Page 3B ANSWER F.04 (1.00) The key is secured by having it 1. under the control of a licensed operator CO.503 2. in a locked storage area C0.503. REFERENCE ARRR Technical Specifications, Sec. 1.1. ARRR Operating Procedures, Sec. C.6. ANSWER F.05 (2.50) a. The operator must reset both the channel #1 annunciators. (1.00) (0.50) b. 40 seconds. c. By the operation of a control console annunciator ("Channel 1 (1.00) disconnect"). REFERENCE ARRR Reactor Annunciator Responses, p. 2. ANSWER F.06 (2.00) 1. Determine the cause of the scram (1.003. 2. Insure control rods have dropped C1.OO3. REFERENCE ARRR Reactor Annunciator Responses, p. 2. (***** CATEGORY F CONTINUED ON hw. par 5 **sst) <M A n W,,

F. STANDARD AND EMERGENCY OPERATING PROCEDURES Page 39 ANSWER F.07 (1.00) Scram the reactor. REFERENCE ARRR Reactor Annunciator Responses, p. 2. ANSWER F.08 (3.00) Scramthereactor40.75h[/b-[0e7h 1 1. 2. Evacuate the hi gh bay area -CO. '5 2. - 41.501-06( 'b,%I$= Hit the two emergency buttons (near the control roomdoor).[0,7f) e-U-. dietir-ri--" rd shutdown the air, handling '[; Cu .J equi pmen t ) Lesespr.f;, eh [o,7,r] 3 Ensure all the external building doors are closea CO.753. ' !. 50 '- REFERENCE ARRR Reactor Annunciator Responses, p. 4., ANSWER F.09 (1.00) Because it renders the water radiation monitor inoperable. (1.00) REFERENCE ARRR Reactor Annunciator Responses, p. 5. ARRR Technical Specifications, Sec. 7.3. Training Guides and Tests, Test #5, question 8. (***** END OF CATEGORY F stats)

s 4 I G. RADIATION CONTROL AND SAFETY Pcg2 40 + ANSWER G.01 (1.00) 6 cm REFERENCE ARRR Reactor Operator Training Manual, Vol. 5, Sec. 10.4. ANSWER G.02 (1.00) The quality f acter accounts f or the biological damaged caused (by the absorbed radiation). REFERENCE ARRR Reactor Operator Training Manual, Vol. 5, Sec. 3.5. ANSWER G.03 (1.50) (0.50) a. 100 mrem. b. Radiological Safety Officer. ' (0.50) (0.50) c. 1.0 rem. j REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. VI.E.1.a. l + (****a CATEGORY G CONTINUED ON NEXT PAGE **ess)

I i ~ G. RADIATION CONTROL AND SAFETY Page 41 s ANSWER G.04 (2.50) a. Any area, (accessible to personnel), in which there exists radiation, (originating in whole or in part within licensed material), at such levels that a major portion of the body could receive to.503 in excess of 5 millirems in any one hour to.50], or in excess of 100 millirems in any S consecutive days LO.503. (1.50) b. Any area to which access is controlled by Aerotest Operations (the licensee) for the purposes of protecting individuals (employees and visitors) f rom exposure to radiation and radioactive materials. (1.00) REFERENCE 10CFR2O ARRR Reactor Operator Training Manual, Vol. 2, Sees. VI.C.1 & VI.F.1. l ANSWER G.05 (1.00) To prevent the formation of excessive amounts of Ar_41. REFERENCE ARRR Technical Specifications, Sec. 8.3.2. ANSWER G.06 (1.00) (1.00) b. REFERENCE ARRR Emergency Plan, p. C-8. I (***** CATEGORY G CONTINUED ON NEXT PAGE

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6 ) i i Pago 42 G. RADIATION CONTROL AND SAFETY ANSWER G.07 (1.00) Any two of th'e, f ol l owi ng at 0.50 point each: 1. Xenon 2. Krypton 3. lodine REFERENCE ARRR Emergency Plan, p. C-1. ANSWER G.OB (2.50) ,of m e/*, t o S C ' a. Beta-Gamma [0.503, _01 t: 50 --/hr [0.503. Neutron (f ast and thermal) CO.SO3, .1 to 1000 mrem /hr CO.503. (2.00) (0.50) b. Alpha. REFERENCE ARRR Technical Specifications, Secs. 7.4 L 7.5. ARRR Reactor Operator Training Manual, Vol. 5, Secs. 7.1 & 7.2. ARRR Reactor Operator Training Manual, Vol. 2, Sec. VIII.6. ANSWER G.09 (1.50) a. Less than or equal to 10 mr/hr. (0.50) b. Within the reactor building. j ) At the San Ramon Fire Department. (1.00) (***** CATEGORY G CONTINUED ON NEXT PAGE

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kn G. RADIATION CONTROL AND SAFETY Pcgo 43 REFERENCE I ARRR Techni cal Specificatiens, Sec. 7.1. ANSWER G.10 (2.00) a. 1. Roof vent (0.253 above the reactor core CO.253. 2. In the vicinity of the reactor core (0.503. (1.00) (0.50) b. 'In the control room. A c. Less than of equal to 2 mr/hr. (0.50) REFERENCE ARRR Technical Sp er. i f i c a t i on s, Sec. 7.2. ] d H k l (***** END OF CATEGORY G

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(********** END OF EXAMINATION **********) 'l

Al t1 CHM ENT Q-F I <a on sn - \\ Al % to 0, tu n st \\OOO .O / O G

Q ATTfCHM ENT Q-a l 3.Reastgt egygt gatigtetigg The three techniques that have been used to calibrate the j absolute power level of the ARRR are 1) calorimetric, 2) { temperature differential across heat exchanger times coolant flow rate and 3) reactivity loss vs. reactor power level, a. Calorimetric The volume of water in the ARRR pool with the thermal column, neutron radiography facility and dual detector beam tube in place is 1675 cu. ft. or { 1.047 x 105 lbs. of water. Since 250 kw is equal l to 8.535 x 105 Btu /hr, for a totally insulated system the temperature in the reactor pool water would increase at the rate of 8.20F per hour. However, conduction and evaporative losses both calculated and measured have shown to increase with temperature. This results in the measured temperature vs. time data as follows at 250 kw: Iteetta19tt 12El Iteetta19tt 10 strait 12Elbt! 70 8.09 80 8.00 90 7.90 j 100 7.86 Since the range of temperature used in the calorimetric measurements ranges from 700 to 1000F, an average of 7.970F/hr or 80F is used for these measurements. The following procedure is used: With the reactor pool temperature at 750F or less, turn off secondary coolant pump which circulates coolant water between primary heat exchanger and cooling tower. This disconnect is located on the east wall of high bay area. Record the temperature indicated by the intet to the heat exchanger and the thermocouple located in the water at the top of the reactor pool. The thermocouple readout is located in the instrument rack behind the reactor console. Measurements on each indicator should be taken every 15 minutes. Continue to take measurem?nts until a pool temperature of approximately 1000F is reached. At this time turn on secondary coolant pump switch in high bay area. System is now in normal operation, i

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2 1 + (B2 Lth ) 2 2 Lf) ) Pr = e-(B p = e-( N ] [Ierr] 5E s C1 (1-Kerri) = C2 (1 - Keff2) m= 1 = _C (final) 1-K C (initial) 82 ( Ef2 + E m2) aT = 1 Af + 1 Ap f At p At At At i

~ -- Page 2 of 5 DATA SHEET e1 o THERM 3 DYNAMICS AND FLUIDEOMNICS FORMULAS: k I k=AAh Q = 2 w LAT + In R /R2 l in R2/R1 3 1 + $=UA(AT) K3 K X2 J 6 = AC ( AT)- p 6==6A*R4 n=61n-6out_ 61n l n = (h n - hout) REAL i (hin - hout) IDEAL np = W ACTUAL W SUPPLIED PV11 = P V2 2 T1 T2 AV AV P1 1 1 = p2 2 2 m = pAV 5 = KA / A Px 0 duc = @3 / g = KA AT / AT = KA Ap / AP ATm = AT (IN) - AT (OUT) In ( AT (IN) ) AT (OUT) G= I ith f 8.8 x 109 TCL - Tes = M a 6=M Ax 6=AATtotal AXA + AXB +'AXN KN KA KB ~-~ - ~ ~

r 9 ORTA SE ET 7 ~ CENTRIFUGAL PLM' LAWS (Speed )3 Powerl Speed 1 Flowl (Speed )2 Headi i i = = = ISpeed )3 Power 2 Speed 2 fl082 (Speed )2 Head 2 2 2 RADIATION AND DEMISTRY FORWLAS_: R/hr = 6CE_ Ix = Io e-mx d2 t /2 = 0.693 1 A C = Q e4t G = Dilution Rate A = AN Volume A = Ao -At e 1 = Io(iln 10 CONVERSIONS: 3 Density of water (20 C) = 62.4 lbm/ft3 = Ig/cm3 1 gq/cm3 = 62.4 lbm/ft 1 gal = 8.345 lbm 23 1 ft3 = 7.48 gal Avogrado's Number = 6.023 x 10 1 gal = 3.78 liters Heat of Vapor (H2 ))= 970 Btu /lbm 0 Heat of Fusion (ICE = 144 Btu /lbm 1 lbm = 454 grams 1 AHJ = 1.66 x 10-24 grams e = 2.72 1 = 3.1415 Mass of Neutron - 1.008665 AMJ 1 KW = 738 ft-lbf/sec Mass of Proton = 1.007277 AMJ 1 KW = 3413 Btu /hr Mass of Electron =.003549 AMJ 1 HP = 550 ft-lbf/sec One atmosphere = 14.~7 psia = 29.92 in. Hg. abs. 1 HP =.746 KW

F = 9/5'C + 32 1 HP = 2545 Btu /hr
R = *F + 460 1 BTU = 778 ft-lbf

'C = 5/9 ( *F -32) 1 EV = 1.54 x 10-16 BTU h = 4.13 x 10-21 M-sec 'K = *C + 273 IW = 3.12 x 1010 fissions /sec go = 32.2 lbm - ft Ibf - sec2 1 CAL / TRAM = 1.8 Btu /lbm C2 = 931 EV/AMJ 1 in. = 2.54 CM C = 3 x 108 m/sec o = 0.1714 x 10-8 Btu hr ftZ

R4 r

i 4

Page 4 of 5 DATA SHEET _ AVERAT TERMAL CONDUCTIVITY (K) BTU /hr-ft 'F Material [ O.025 Cork 0.028 Fiber Insulating Board 0.096 Maple or Oak Wood O.4 Building Brick h 0.45 Window Glass 0.79 ) Concrete 25.00 0 1 Percent rarbon Steel 1 Percent Chrome Steel 35.00 } 118.00 Aluminum 223.00 Copper 235.00 Silver 0.39 2 Water (20 psia, 200*F) Steam (1000 psia, 550'F) 0.046 1.15 Uranium Dioxide 0.135 Helium 10.0 Zircaloy MISCELLAEOUS IWORMATION: E = mc2 KE = 1/2 mv2 PE = mgb Vf = Vo + at AE = 931 Am AREA VOLUE GE0ETRIC OBICT A = 1/2 bh ////////////////// TRIANGLE A~= 32 ////////////////// SQUAPE A=LxW ////////////////// RECTANGLE A = wr2 /////////////////j CIRCLE A = 2(LxW + LxH + WxH) V=Lxwxh RECTANGULAR SOLID RIQiT CIRCULAR CYLINDER A = (2 wr2)h + 2(wr2) V = wr2h A = 4 wr2 V = 4/3 wr3 SPHERE ///////////////////////) V=S3 CUBE e

( O. Page 5 of 5 j

l DATA SEET_

d !l [ MISCELLAEOUS IEOR)% TION CONTINLED: 1 \\ 10 CFR 20 Appendix B i Gamma Table I Table II Energy Col I Col II Col I Col II EV per Air Water Air Water Materi:n Half-Life 01sintegratior uc/ml uc/ml uc/ml uc/ml Ar-41 1.83 h 1.3 Sub 2x10-6 4x10-8 Co-60 5.27 y 2.5 S 3x10-7 1x10-3 1x10-8 5x10-5 1-131 8.04 d 0.36 S 9x10-9 6x10-5 1x10-10 3x10-7 Kr-85 10.72 y 0.0L Sub 1x10-5 3x10-7 N1-65 2.52 h 0.59 S 9x10-7 4x10-3 3x10-8 1x10-4 y D.003 S 2x10-12 1x10-4 6x10-14 5x10-6 Pu-239 2.41x104 Sr-90 29 y = S 1x10-9 1x10-5 3x10-ll 3x10-7 .l Xe-135 9.05 h 0.25 Sub 4x10-6 1x10-7 Any single radionuclide with T /2> 2 hr 1 which does not decay by a or spcntaneous 3x10-9 9x10-5 1x10-10 3x10-6 fission Neutron Energy (EV) te.utrons per cm2 Average flux to deliver r ilvalent to 1 rem 100 mrem in 40 hours Thermal 970 x 106 670 0.02 400 x 106 280 (EUTRONS) 0.5 43 x 106 30 m2 sec 10 24 x 106 17 LIEAR ABcMPTION COEFFICIENTS y (m-1) Energy (E V) Plater Corcrete Iron Lead 0.5 0.090 0.21 0.63 1.7 1.0 0.067 0.15 0.44 0.77 1.5 0.057 0.13 0.40 0.57 2.0 0.048 0.11 0.33 0.51 2.5 0.042 0.097 0.31 0.49 3.0 0.038 0.088 0.30

0. 47__

NRC Official Use Only ) 1 MASI!R :0)Y I l Nuclear Regulatory Commission Operator Licensing j Examination l l This document is removed from Official Use Only category on date of examination. NRC Official Use Only -MASPiCOPY

i f U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION i FACILITY: ARRR ] REACTOR TYPE: TRIGA DATE ADhINSTERED: 88/04/13 EXAMINER: ROESENER, S. MASIBPC2Y O CANDIDATE INSTRUCTIONS TO CANDIDATE: Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category. Examination papers will I be picked up six (6) hours after the examination starts. % OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 19.00 19.00 H. REACTOR THEORY 20.00 20.00 I. RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS 20.50 20.50 J. SPECIFIC OPERATING CHARACTERISTICS 20.00 20.00 K. FUEL HANDLING AND CORE PARAMETERS 20.50 20.50 L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS 100.0 Totals i Final Grade l All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: l 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties. 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating. 3. Use black ink or dark pencil only to facilitate legible reproductions, j 4. Print your name in the blank provided on the cover sheet of the examination. 5. Fill in the date on the cover sheet of the examination (if necessary). 6. Use only the paper provided for answers. 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet. 8. Consecutively number each answer sheet, write-"End of Category ___" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet. 9. Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

12. Use abbreviations only if they are commonly used in facility literature.

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the examiner only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.

This must be done after the examination has been completed.

18. When you complete your examination, you shall:

a. Assemble your examination as follows: (1) Exam questions on top. (2) Exam aids - figures, tables, etc. (3) Answer rusos including figures which are part of the answer. b. Turn in your copy of the examination and all pages used to answer the examination questions. c. Turn in all scrap paper and the balance of the paper that you did not use for answering tise questions, d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked. l ] O

H. REACTOR THEORY Paga 4 QUESTION H 01 (2.00) a. Define Bath Temperature Coefficient. b. Define Prompt Temperature Coefficient. QUESTION H.02 (2.00) a. How does a fuel temperature increase result in the hardening of the neutron spectrum? b. How does hardening of the neutron spectrum result in a decrease in reactivity? QUESTION H.03 (2.00) a. Define BETA EFFECTIVE. b-Uky is DETA EFFECTI"E greater ther. BETA? QUESTION H.04 (1.00) Why is the thermal flux depressed in the center of the core when a fuel element is installed in the A-ring? QUESTION H.05 (2.00) a. State the TWO reactions which produced neutrons in the neutron source when it was new (unirradiated source). Either a word explanation or an equation is acceptable. b. Why has the strength of the installed neutron source increased since it was originally installed? (***** CATEGORY H CONTINUED ON NEXT PAGE *****)

H. REACTOR THEORY Pago 5 l QUESTION H.06 (3.00) Using the attached graph paper (Attachment Q-1), sketch the buildup and decay of xenon poisoning reactivity as a function of time from Monday morning at 8:00 to Thursday morning at 8:00 for the following power history. INCLUDE scale indications for the vertical axis of the graph. HISTORY: Monday 0800 - Startup from cold, Xenon free 1 conditions Monday 0800 to 1600 - Constant operation at 250 kW Monday 1600 - Shutdown Tuesday 0800 to 1600 - Constant operation at 250 kW Tuesday 1600 to Thursday 0800 - Shutdown j QUESTION H.07 (1.00) Reactor power increases from 40 to 60 watts in 20 seconds. What is the reactor period associated with this power increase? QUESTION H.08 (1.00) What is the approximate core reactivity, +/- 3.01, associated with a period of 10 seconds? QUESTION H.09 (1.00) Why is graphite a better reflector than water? (***** CATEGORY H CONTINUED ON NEXT PAGE *****)

e H. REACTOR THEORY Pago 6 QUESTION H.10 (3.00) If the reactor was operating at 250 kW when the safety rod was dropped the power would immediately drop to about 50 kW and then decay slowly to a final steady state value of a few thousand counts per second. (Note: in answering the questions below, calculations are neither required nor desired.) The loss of what component of the neutron flux causes the sharp drop a. in power? b. What determines the rate of power decrease at about five minutes after the rod is dropped? Why does the power stabilize after approximately one hour when keff c. is less than 1.07 QUESTION H.11 (1.00) Multiple Choice Which ONE of the following factors plays the most important role in determining the worth of a control rod? 1 a. The rod speed. b. The flux shape, c. The reactor power. d. The delayed neutron fraction. (***** END OF CATEGORY H *****)

I. RADIOACTIVE MATERIALS HANDLING DISPOSAL Paga 7 AND HAZARDS QUESTION I.01 (1.00) If two centimeters of lead placed at a certain location in a beam of gamma rays would reduce the gamma radiation level from 100 mR/ hour to 50 mR/ hour, what thickness of lead placed in this beam would reduce the gamma radiation level from 400 mR/ hour to 50 mR/ hour? QUESTION I.02 (2.00) How long would a person have to spend in each of the following fields to receive a whole body dose equivalent to the ARRR weekly guideline? Show all work and state all assumptions, a. 40 mr/hr gamma b. 10 mr/hr thermal neutrons c. 30 MREM /hr fast neutrons d. A field containing all of the above QUESTION I.03 (2.00) A mixed beam of neutrons emerges from a reactor port. The intensities 2 are 10,000 thermal and 360 fast neutrons /cm sec. t a. How long can a worker stay in this neutron field before he exceeds the ARRR quarterly limit of 1.0 rem? Attachment Q-2 taken from 10CFR20 will be useful in your calculation. Show all work. b. What action must be taken if the worker exceeds the ARRR quarterly limit by 150 mrem? QUESTION I.04 (2.00) An individual in a restricted area may be allowed to receive a whole body dose in excess of the federal quarterly limit of 1.25 rem under certain conditions. State TWO of the three conditions. (***** CATEGORY I CONTINUED ON NEXT PAGE *****)

i I. RADIOACTIVE MATERIALS HANDLING DISPOSAL Pago 8 AND HAZARDS QUESTION I.05 (2.00) In accordance with 10CFR20, state TWO of the THREE alternative ways of controlling access to a high radiation area. QUESTION I.06 (2.00) List the FOUR major drains which feed potentially contaminated liquids to the low level sump tank. QUESTION I.07 (1.50) The following questions apply to the fixed gamma monitor required by Technical Specifications. a. What is the setpoint as stated in the Technical Specifications? (0.50) b. Upon reaching setpoint, in what TWO locations must alarms be sounded in accordance with Technical Specifications? (1.00) QUESTION I.08 (2.00) The following questions apply to the fixed detector required by Technical Specifications for monitoring of radioactive gasses, a. State the two sample points, either of which must be monitored in order to be in compliance with Technical Specifications. (1.00) 1 b, In what location is there required to be a continuous detector readout? (0.50) l c. What is the Technical Specification setpoint of the associated annunciator? (0.50) QUESTION I.09 (3.00) State THREE of the FOUR EAL (Emergency Action Levels). Include setpoints in your answer. (***** CATEGORY I CONTINUED ON NEXT PAGE *****) \\

I. RADIOACTIVE MATERIALS HANDLING DISPOSAL Pago 9 AND HAZARDS QUESTION I.10 (1.00) Multiple Choice If the reactor was at 250 KW and one central fuel element failed, what would be the dose received in the first hour by an individual standing in the middle of the reactor room. Assume that the individual did not evacuate as he should have, a. 0 - 25 mr b. 50 - 75 mr c. 250 - 300 mr d. 475 - 525 mr QUESTION I.11 (1.50) State the THREE radioactive gases of major concern during a fuel element failure. (***** END OF CATEGORY I *****)

l J. SPECIFIC OPERATING CHARACTERISTICS Pego 10 l l QUESTION J.01 (2.00) The procedure for control rod calibration by the rod drop method states that power should be maintained between 100 and 1000 watts just before dropping the rod. Testing outside these limits may cause the measured rod worth to be lower than the actual rod worth. Why will exceeding the upper limit cause the measured rod worth to be less than the actual rod worth? In your answer to the question give both the physical effect of operating outside the limit and explain how i the stated ph;sical effect will lead to the errer in rod worth. QUESTION J.02 (3.00) With all rods in, cold, Xe free, the count rate is 1000 cpm and the reactivity is -$5.36. What final count rate would you expect to see if the safety rod was completely withdrawn 7 Show all work. QUESTION J.03 (1.00) Multiple Choice With the reactor pool outlet initially at 80 F and the reactor at 250 kW, a reduction in primary flow rate from normal to 100 gpm will: a. Eventually result in a reactor scram if no operator action is taken. b. Result in an immediate scram. c. Cause the cooling tower fan to operate more frequently. d. Result in a higher steady state pool outlet temperature. QUESTION J.04 (1.00) What design feature of the pool makeup system prevents overflow of the pool? (***** CATEGORY J CONTINUED ON NEXT PAGE *****) l l

J. SPECIFIC OPERATING CHARACTERISTICS Pago 11 QUESTION J.05 (2.00) a. Is it possible to siphon the pool below the Technical Specification level limit via the suction line if a break occurs in the primary coolant loop? Explain specifically how it would occur or what would prevent it. b. Is it possible to siphon the pool below the Technical Specification level limit via the discharge line if a break occurs in the primary coolant loop? Explain specifically how it would occur or what would prevent it. QUESTION J.06 (1.En} Given that the reacto: is critical at.01 watt, what behavior / trend would you expect to observe on the following instruments? a. Rod position indications. b. Period meter. c. Channel #1 count rate. QUESTION J 07 (2.50) a. With the Regulating rod in the full down position the UP pushbutton is depressed. The foot microswitch fails such that it will not change positior; from the normal control rod down position. Describe the sequence of rod motion AND rod indicator lamp changes for this situation. Attachment Q-3 showing the rod drive, motor control and indicator lamp circuit is included for your use. b. With the Safety rod in the full up position, the DN pushbutton is depressed. The foot microswitch fails such that it will not change position from the normal control rod up position. Describe the sequence of rod motion AND rod indicator lamp changes for this situation. Attachment Q-3 showing the rod drive, motor control and indicator lamp circuit is included for your use. (***** CATEGORY J CONTINUED ON NEXT PAGE *****)

J. SPECIFIC OPERATING CHARACTERISTICS Page 12 QUESTION J.08 (3.00) 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 press 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 fails? QUESTION J.09 (1.00) What would be the indication during a normal shutdown following i eight hours of full power operation of a compensated ion chamber that was overcompensated? QUESTION J.10 (1.00) bre The Magnet Relay Inter 1 ok relay, K69A, prevents re-energizing of the scram -alay, K380 following a scram as long as power remains above disconnect. at is the reason for this interlock? QUESTION J.11 (1.50) a. What kind of detector is used to initiate a pool water high temperature scram? (1.00) b. What is the Technical Specification setpoint for the high temperature scram? (0.50) QUESTION J.12 (1.00) The reactor safety systems are required by Technical Specifications to be FAIL-SAFE. Define FAIL-SAFE when used in this context. (***** END OF CATEGORY J *****)

l K. FUEL HANDLING AND CORE PARAMETERS Pcgo 13 l I QUESTION K.01 (1.50) What is the physical sequence of events that occur when the emergency release pins on the pneumatic fuel-handling tool are removed in order to release a fuel element. Include in your answer a discussion of the effects on or of the following components: Steel balls Fuelelementengagementsleeve(insidecylinderoflockingmechanism') Locking sleeve (outside cylinder of locking mechanism) Spring Fuel element end fixture groove QUESTION K.02 (3.00) State THREE procedural controls that help to prevent the accidental swapping of fuel elements during surveillance checks. l QUESTION K.03 (3.00) a. Following the removal of all the fuel elements from the core for maintenance on a non-fueled core structure the excess reactivity must be measured after the reloading of a maximum of 70 fuel elements. How is this excess reactivity measurement performed? (2.00) l b. How often is this procedure repeated as reloading is continued? (1.00) QUESTION K.04 (2.50) a. What is the maximum number of fuel elements than can be stored in the the storage rack in the reactor tank? (0.50) b. If it is necessary to unload the entire core, where would the fuel and reflector elements in excess of the storage rack capacity be stored? (1.00) c. What is the Technical Specification limit related to the design of in pool storage racks? (1.00) 1 (***** CATEGORY K CONTINUED ON NEXT PAGE *****)

h i K. FUEL HANDLING AND CORE PARAMETERS l' ego 14 QUESTION K.05 (2.50) a. What surveillances must be performed on fuel elenont s? (1.00) b. How often are these surveillances performed? (0.50) j c. State two inspection observations that could result. ln an element being withdrawn from service? (1.00) STION K.06 (3.00) Usin e top view of the core provided in Attachment Q-4, indicate the followin r the present core configuration: a. location of t egulating rod. b. location of the safety c. location of the source. d. location of the Glory Hole. e. outline of ONE of the two TRIANGULAR irradiation lities. f. name of the component located at G10. he t QUESTION K.07 (2.00) Assuming that the rod worths are not affected significantly, what would be the affect, if any, of moving the Glory Hole closer to the center of the core on: a. the critical rod position at 1000 watts? b. the change in rod position from 1000 watts to 250 kW7 i (***** CATEGORY K CONTINUED ON NEXT PAGE *****) j j

K. FUEL HANDLING AND CORE PARAMETERS Pags 15 QUESTION K.08 (2.50) Referring to the data below and the Attachment Q-5 subcritical multiplication plot of that data: a. predict fuel loading for criticality. (0.50) b. state why the data indicates a procedural violation AND specifically state which steps and which detectors show this violation. (2.00) TOTAL NUMBER STEP OF ELEMENTS DETECTOR A DETECTOR B DETECTOR C 0 0 100 75 50 1 30 417 97 90 2 40 645 115 122 3 50 1,667 150 192 4 60 6,667 246 435 5 65 20,000 441 1,111 6 66 25,000 600 2,000 P (***** END OF CATEGORY K *****)

L. ADMINISTRATIVE PROCEDURES, CONDITIONS Pega 16 / AND LIMITATIONS QUESTION L.01 (3.00) The attached REFERENCES package will be useful in an.,wering this questior During performance of corrective maintenance to replace the Control Rod Drive Mechanism rod down limit switch, it was discovered that the magnet wire c>nduit had been damaged and needed to be replaced. A temporary change to the limit switch replacement ORF (Operations Request Form) was prepared. After reviewing Technical Specification 12.2.2 the SRO and another qualified staff member approved the change. The replacement of the switch and the conduit was then completed, a. Wh. wc1 it incorrect to apply Technical Specification 12.2.2 in the above scenario? b. What Technical Specif.ication was violated by the incorrect application cf Technical Specification 12.2.27 c. It. accordance with the Administrative Procedures, who must the SRO notify when the error is discovered? QUESTION L.02 (3.00) , ;7 g7g4 The attached REFERENCES package will be useful in answering this questior At 1000 on Monday, the reactor automatically scrams from 250 kW when the channel #4 nuclear inst dment fails low. At 1100 it is determined that the detector is broken nd must be replaced. During the investigation of the channel #4 pro em the area radiation monitor fails low (the detector has failed) a. What Technical Specification has been violated? (Either exact section or a ummary statement is acceptable). b. What actio would be necessary to get within compliance? c. According/to the facility license, to whom AND within what time period should a report be made? / l (***** CATEGORY L CONTINUED ON NEXT PAGE *****)

e L. ADMINISTRATIVE PROCEDURES, CONDITIONS Pcgo 17 AND LIMITATIONS QUESTION L.03 (2.00) The attached REFERENCES package will be useful in answering this questioi If a licensed operator has not actively performed his function as SRO for the minimum of four hours in a quarter, what actions must be taken before he resumes the function authorized by his license? QUESTION L.04 (1.00) In accordance with the Reactor Annunciator Responses guide, why does the failure of the demineralizer pump force a shutdown of the reactor? QUESTION L.05 (1.50) a. According to Technical Specifications what is the minimum number af personnel that must be present for reactor operations to be permitted. (0.50) b. In accordance with Technical Specifications what is the license level, if any, required of each person on the minimum reactor operating crew. (1.00) QUESTION L.06 (2.00) State FOUR specific times when the presence at the facility of an SRO would be required. 3 QUESTION L.07 (1.00) According to the Technical Specification definitions, what are the TWO methods of securing the console key? (***** CATEGORY L CONTINUED ON NEXT PAGE *****) i

-. ~ -.

L. ADMINISTRATIVE PROCEDURES, CONDITIONS Pago 18 AND LIMITATIONS QUESTION L.08 (2.00) The attached REFERENCES package will be useful in answering this questior How long should the following records be maintained? Answer each part separately, a. Records of emergency reactor scrams including reasons for emergency shutdowns. b. Requalification program records. QUESTION L.09 (2.00) State the TWO reasons for gathering in the control room in the event of a fission product release from the core. QUESTION L.10 (1.00) According to the Emergency Plan, who has primary authority for authorizing exposures in excess of 100FR20 requirements? QUESTION L.11 (1.00) 1 State the criterion used by the SRO for determining whether or not he should immediately call the San Ramon Fire Department. QUESTION L.12 (1.00) In the absence of the President, Aerotest Operations, with no designated l alternate, state who is the Emergency Coordinator for a: a. radiological emergency, b. facility emergency. (***** END OF CATEGORY L *****) (********** END OF EXAMINATION **********)

H. REACTOR THEORY Paga 19 ANSWER H 01 (2.00) a. The change in reactivity associated with a change in the bath (pool) temperature. (1.00) b. The change in reactivity associated with a change in the fuel temperature. (1.00) REFERENCE ARRR Training Test #7. ARRR Reactor Operator Training Manual, Vol. 4, Sees. 1.3.3 & 1.3.4. ANSWER H.02 (2.00) a. Temperature increase causes increased thermal vibration of the Hydrogen atoms in the Zirc-Hydride matrix [0.50] which then results in increased neutron energies (harder spectrum) following scattering by the Zirc-Hydride [0.50]. (1.00) b. As the neutron spectrum hardens, more neutrons escape from the fuel [0.50] and are absorbed in the non-fuel (moderator, reflector, core structure) portions of the core [0.50]. (1.00) REFERENCE ARRR Reactor Operator Training Manual, Vol. 4, Sec. 1.3.2 & 1.3.3. ANSWER H.03 (2.00) a. The fraction of the thermal neutron population that was born delayed. (1.00) b. ed neutrons are born at lower energies than prompt neutrons [0. ore likely to reach thermal energies [0,50]. (Therefore, the frac Qe t eutrons at thermal energies (beta effective) is greater than th raet4

delayed neutrons at birth (beta).)

,,(l (***** CATEGORY H CONTINUED ON NEXT PAGE *****)

e r H. REACTOR THEORY Pcco 20 REFERENCE, ARRR Reactor Operator Training Manual, Vol 4, Sec i.2.2. Other standard texts for example Lamarsh's," Nuclear Reactor Theory", Sec. 12-5. ANSWER H.04 (1.00) Because the installation of a fuel element causes the center of the core to be highly undermoderated. 1

s REFERENCE AGNIR Reactor Physics Tests, Sec VI.C.

ANSWER H.05 (2.00) a. Americium 241 decays by alpha emission [0.50]. Beryllium 9 absorbs the alpha and decays immedistely with the emission of a neutron [0.50). OR 241 237 Am ---> Np + Alpha [0.50). 9 12 Be + Alpha - -- > C + neutron [0.50). (1.00) b. Neutron transmutation in the source [0.50] has created a more active alpha emitter [0.50]. OR Americium 241 has been converted to Curium 242 by neutron capture (0.50] and curium 242 is a more active alpha emitter [0.50). (1.00) (***** CATEGORY H CONTINUED ON NEXT PAGE *****)

H. REACTOR THEORY Pcgo 21 REFERENCE ARRR Reactor Operator Training Manual, Vol. 3, Sec RT-5.D. ARRR Reactor Operator Training Manual, Vol. 2 Sec. III.4.8. ANSWER H.06 (3.00) See graph included as Attachment A-1. Assumed a xenon equilibrium value of $1.40. Will accept answers that reflect and equilibrium of $1.30 to $1.50. Grading - Rise to $.35 (+/- $.10) at 1600 Monday [0.50). - Peak at $.04 (+/- 3.02) higher [0.25] in 2 to 4 hours [0.25]. - Drop to $.20 (+/- $.10) by 0800 Tuesday [0.25] - Small dip of less than $.02 [0.25] with minimum occurring in one hour or less [0.25]. Rise to 3.04 (+/- $.10 BUT higher than 1600 Monday) at 1600 Tuesday [0.50]. - Peak at 3.05 (+/- $.02 but as large or larger than peak on Monday) higher [0.25] in 2 to 5 hours (but as long or longer than peak on Monday) [0.25]. - Decay to 3.10 (+/- $.075) by 0800 Thursday [0.25]. REFERENCE ARRR Reactor Operator Training Manual, Vol. 4, sec. 1.3.7. ARRR Reactor Operator Training Manual, Vol. 4, sec. 1.3.7, Fig. 1.7, assuming a flux of 4 x 10 E 12 for 250 kW in the ARRR. AGNIR Reactor Physics Tests, Fig. 14, "Xenon vs time". ANSWER H.07 (1.00) 9 Y1.3 T = t r Ln(n /n ) = 20 sec,r Ln(60/40) = ert +/.5 seconds. 1 0 i [0.75 for correct equation. 0.25 for correct result.] l (***** CATEGORY H CONTINUED ON NEXT PAGE *****)

H. REACTOR THEORY Pago 22 REFERENCE ARRR Reactor Operator Training Manual, Vol. 4, sec. 1.2.5. ANSWER H.08 (1.00) Using the Inhour graph S.35 +/-$.01. REFERENCE ARRR Reactor Operator Training Manual, Vol. 4, sec. 1.2.5. ARRR Reactor Operator Training Manual, Vol. 1, sec. IV, Figs. II & III. ANSWER H.09 (1.00) Because graphite has a significantly lower neutron absorption cross section. REFERENCE ARRR Reactor Operator Training Manual, Vol. 3, Sec. RT-5.II.C. ANSWER H.10 (3.00) a. The prompt component. (1.00) b. After five minutes the power decrease is controlled by the decay of longest lived delayed neutron precursor. (1.00) c. Suberitical multiplication (of core source neutrons) causes the power to stabilize. (1.00) REFERENCE ARRR Reactor Operator Training Manual, Vol. 4, Secs. 1.2.5 & 1~.2.7. (***** CATEGORY H CONTINUED ON NEXT PAGE *****) 1

H. REACTOR THEORY Pego 23 ANSWER H.11 (1.00) b. REFERENCE ARRR Reactor Operator Training Manual, Vol. 4, Sec. 1.1.13. J l 4 (***** END OF CATEGORY H *****) I I. -

I. RADIOACTIVE MATERIALS HANDLING DISPOSAL Paga 24 AND HAZARDS ANSWER I.01 (1.00) 6 cm REFERENCE ARRR Reactor Operator Training Manual, Vol. 5, Sec. 10.4. ANSWER I.02 (2.00) a. 100 mREH/(40 mr/hr x QF of 1) = 2.5 hr (0.50) b. 100 MREM /(10 MRAD /hr x QF of 3) = 3.33 hr (0.50) c. 100 MREM /(30 MREM /hr) = 3.33 hr (0.50) d. 100 MREM /(40 MREM /hr + 30 MREM /hr + 30 MREM /hr) = 1 hr (0.50) REFERENCE ARRR Reactor Operator Training Manual, Vol. 1, Sec. VI.E.1.a. ARRR Reactor Operator Training Manual, Vol. 5, Sec. 3.5. ANSWER I.03 (2.00) 2 2 a. (1 rem /970 E 6 n/cm ) x 10,000 n/cm sec x 3600 sec/hr =.037 rem /hr. 2 2 (1 rem /14 E 6 n/cm ) x 360 n/cm sec x 3600 sec/hr =.093 rem /hr 1 rem /(.037 rem /hr +.093 rem /hr) = 7.7 hrs (+/-.1 hr) (1.00) b. An investigation must be completed and the type and circumstances of exposure must be recorded. (1.00) (***** CATEGORY I CONTINUED ON NEXT PAGE *****)

I. RADIOACTIVE MATERIALS HANDLING DISPOSAL Pago 25 AND HAZARDS REFERENCE ARRR Reactor Operator Training Manual, Vol. 1, Sec. VI.E.1.a. 10CFR20.4.(a).(4). ANSWER I.04 (2.00) Any two of the following at 1.00 point each: 1. He does not exceed 3 rem per quarter, j 2. His radiation history is known and properly recorded (NRC Form 4). j i 3. The dose received when added to his radiation history does not exceed 5(N-18) rems where N = the person's age at his last birthday. REFERENCE 10CFR20.101.(b). ANSWER I.05 (2.00) Any two of the following at 1.00 point each: Access to the high radiation area may be controlled by: 1. A device lowering radiation upon entry [0.50] such that it is less than the high radiation limit (0.50). 2. A warning device that upon entry audibly [0.25] or visibly [0.25] alerts the person entoring [0.25] and alerts the licensee or a ) supervisor [0.25]. )

1. s e.

1 3. A locking device {0.50] er rnaitiva nnntral ever-each-individual __ l entry-eor 503-J N. in ect.Sur ve 1 lis.,ce p e vent u n a r Gr; e ed en rey. ro (***** CATEGORY I CONTINUED ON NEXT PAGE *****)

I. RADIOACTIVE MATERIALS HANDLING DISPOSAL Pega 26 AND HAZARDS REFERENCE 10CFR20.203.(c) ANSWER I.06 (2.00) 1. Reactor trench. 2. Heat exchanger building trench. 3. Demineralizer building trench. 4. Chemical laboratory sink. REFERENCE ARRR Reactor Operator Training Manual, Vol. 2 Sec VI.4. ANSWER I.07 (1.50) a. Less than or equal to 10 mr/hr. (0.50) b. Within the reactor building. At the San Ramon Fire Department. (1.00) REFERENCE ARRR Technical Specifications, Sec. 7.1. ANSWER I.08 (2.00) a. Roof vent (0.25] above the reactor core [0.25]. In the vicinity of the reactor core [0.50). (1.00) b. In the control room. (0.50) l c. Less than or equal to 2 mr/hr. (0.50) (***** CATEGORY I CONTINUED ON NEXT PAGE *****)

I. RADIOACTIVE MATERIALS HANDLING DISPOSAL Pega 27 AND HAZARDS REFERENCE ARRR Technical Specifications, Sec. 7.2. ANSWER I.09 (3.00) Any three of the following at 0.50 point each for the parameter and 0.50 point cach for the setpoint: 1. High radiation level in the control room, > 100 mR/hr. 2. High water radioactivity as seen on the control room monitor > 200 mR/hr. 3. High air radioactivity as seen on the control room monitor > 20 mR/hr. 2 4. Smearable surface contamination > 10 mr/hr per 100 cm. REFERENCE ARRR Emergency Plan, Sec. V. ANSWER I.10 (1.00) b. REFERENCE ARRR Emergency Plan,

p. C-8.

ANSWER I.11 (1.50) 1. Xenon 2. Krypton 3. Iodine (***** CATEGORY I CONTINUED ON NEXT PAGE *****) l -e ,.n. -,.m..,, ,,-r

RADIOACTIVE MATERIALS HANDLING DISPOSAL Pega 28 I. AND HAZARDS l i REFERENCE ARRR Emergency Plan,

p. C-1.

i P i i I t l l s a J (***** END OF CATEGORY I *****) m

J. SPECIFIC OPERATING CHARACTERISTICS Paca 29 ANSWER J.01 (2.00) Exceeding the upper limit would cause significant generation of heat in the fuel [0.50) which would add negative reactivity to the core (0.50). When the rod is dropped the fuel will cool [0,50] and.the negative reactivity added by the fuel will decrease [0.50] such that the measured overall reactivity change due to the dropped rod (as inferred from the resultant negative period) will be less than the actual rod worth. REFERENCE ARRR Reactor 0;t4Fator Training Manual, Vol. 1, Sec. IV.C.2. l l (***** CATEGORY J CONTINUED ON NEXT PAGE *****) )

J. SPECIFIC OPERATING CHARACTERISTICS Pega 30 ANSWER J.02 (3.00) As stated on the rod worth curves attached to the test, the Safety rod is worth $3.85. Therefore the reactor is shutdown by $5.36 - $3.85 = $1.51 after safety rod withdrawal. From the equation sheet the proper equations to use are: C (1 - k ) = C (1 - k ) 1 1 2 2 AND p= (k - 1)/k which means 1 - k = 1/(1 - 1/p) where p = rho. Alternatively k can be calculated as shown below and directly substituted into the first equation above. Of course the final answer will still be the same. k - 1/(1 p) Additionally, it is necessary to convert dollars to p using: p = $ x Beta Combining the above gives: Final count rate = Initial count rate (1 - 1/p ) / (1 - 1/p ) final initial = 1000 (1 - 1/(1.51 x.0079)) / (1 - 1/(5.36 x.0079)) = 3446 cpn. Grade as follows: 2.00 for proper use of equations. 0.50 for calculation of reactivity with rod withdrawn. l 0.50 for use of proper value of beta,.0079. REFERENCE i ARRR rod worth curves. ARRR Technical Specifications, 5.1.2. ARRR Reactor Operator Training Manual, Vol. 4, Sec 1.2.1 & 1.2.7. (***** CATEGORY J CONTINUED ON NEXT PAGE *****)

J. SPECIFIC OPERATING CHARACTERISTICS Paga 31 ANSWER J.03 (1.00) d REFERENCE ARRR Reactor Operator Training Manual, Vol. 1, Sec. IV.C.3.b. ARRR Reactor Operator Training Manual, Vol. 2 Sec. V. ANSWER J.04 (1.00) The two pool level controlled float valves in series in the makeup supply line. REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. V.2. ANSWER J.05 (2.00) a. No. The suction line extends only one foot below the normal water level. (1.00) b. No. The-diocharge line (Chech-at f-aci-lity-to-see-if-there-is-any design-features-such,s a Ele drltled-in-the--discharge _line-piping, this-a standard-design-feature-but-was-not-mentioned-in-the-text. ) No ps; - r in r G-d: se he, e Noe exterm / ro T h e );u e l is /ccue r (1 00) TH8, one L r-h# lo t h e-w,< / i w re, te n f. w ARRR Reactor Operator Training Manual, Vol. 2, Sec. V.3.1. ARRR Training Guides and Tests, Study Handout No. 2, Question 2. CAF (***** CATEGORY J CONTINUED ON NEXT PAGE *****)

J. SPECIFIC OPERATING CHARACTERISTICS Pega 32 ANSWER J.06 (1.50) a. No motion. (0. 50 )- b. 2E"S @r SLIGHTL 4 siLivc); T n Sn /r7, (0.50) c. Stable (or SLOWLY increasing). (0.50) REFERENCE ARRR Reactor Operator Training Manual, Vol. 4, Sec. 1.2.7. ANSWER J.07 (2.50) Sequence of motor and lamp events. [ Points for each individual event as shown, 0.25 points per question a and b for completely correct sequence, loss of 0.25 points for each incorrect event.] a. 1. Rod starts to drive out [0.25]. 2. DN and CONT lamps extinguish [0.25 each] and rod motion stops (0.25]. (1.25) b. 1. Rod starts to drive in [0.25]. 2. UP lamp is extinguished [0.25]. 3. DN lamp is lit (0.25] and rod motion ceases [0.25]. (1.25) REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec IX. ANSWER J.08 (3.00) 1. Safety rod - Fully inserted [1.00]. 2. Regulating rod - Fully inserted [1.00]. 3. Shim rod - Half way out of core OR just slightly over half way out of core (due to small amount of time to actuate the safety rod MAG UP switch) [1.00]. (***** CATEGORY J CONTINUED ON NEXT PAGE *****)

J. SPECIFIC OPERATING CHARACTERISTICS Pcgo 33 REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec'IX. ANSWER J.09 (1.00) The indication will read low off-scale (and then slowly return to an on-scale reading). c) R REFERENCE Lo,ec r t,,,, J r n o vicl n a r k e lh n'a c}. ARRR Training Guides and Tests, Test No. 3, Question III.4. /' f ANSWER J.10 (.00)LCej'TO' Prevents sta up with channel #1 scrams bypassed. REFERENCE ARRR Repctor Operator Training Manual, Vol. 2, Sec. IX. ANSWER J.11 (1.50) a. A bimetallic switch. (1.00) b. Less than or equal to 130 F. (0.50) REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. IX, Fig. IX-5. ARRR Reactor Operator Training Manual, Vol. 2, Sec. V.2. ANSWER J.12 (1.00) De-energizing of the reactor safety systems shall cause a scram. (***** CATEGORY J CONTINUED ON NEXT PAGE *****)

l J. SPECIFIC OPERATING CHARACTERISTICS Pcss 34 REFERENCE ARRR Technical Specifications, Sec. 6.1. l 1 e i 1 i l l I i 1 l (***** END OF CATEGORY J *****) .n----- ,,-.m, -w. -, -, egg,.,n g ,,v. .,y...,,-, g,,,-,-- ,,n,,- ,e_.m.,.,-w... p., -.,,,n-,,,,, w..y.,

K. FUEL HANDLING AND CORE PARAMETERS Pega 35 ANSWER K.01 (1.50) When the pins are removed the fuel element engagement sineve is forced downward by spring pressure [0.50]. When the steel balls in the fuel element engagement sleeve clear the lower lip of the locking sleeve the balls are free to move to their outermost position [0.50]. When the balls are in their outermost position they no longer engage the grove in the fuel element end fixture [0.50] and the fuel element is released. REFERENCE ARRR Reactor Operator Training Manual, Volume 2, Fig. IV-1. ANSWER K.02 (3.00) Any three of the following at 1.00 points each: 1. Only one fuel element may be out of core or storage at a single time. 2. All fuel is required to be returned to its original position prior to startup. 3. Records of all fuel movements are maintained. 4. A data sheet is prepared in advance which delineates fuel moves to be performed. 5. Any deviation from the fuel movement schedule requires the approval of two operators, and at least one of these must be an SRO. 6. Adequate supervision is ensured by requiring an SRO to be present. REFERENCE ARRR Reactor Operator Training Manual, Volume 1, Sec. IV.D. (***** CATEGORY K CONTINUED ON NEXT PAGE *****)

K. FUEL HANDLING AND CORE PARAMETERS Paga 36 ANSWER K.03 (3.00) a. 1. The reactor is brought to critical at 100 W [1.00]. 2. The rod worth curves are used to determine how much reactivity would be inserted if the rods were fully withdrawn [1.00].(2.00) b. The excess reactivity is measured after the ir. rtion of each i-ndividual uol olower.t. each 5 h s e g ' - ' r (m e / 4 oq/, r A-2. (1.00) ^ REFERENCE ARRR Reactor Operator Training Manual, Volume 1, Sec. IV.E.8. ANSWER K.04 (2.50) a. 21 (0.50) b. The fuel is stored in temporary ir. pool storage racks (0.50]. The reflector elements are stored in the graphite column [0.50]. (1.00) ' c. Keff will not exceed 0.8 (for all conditions of moderation. (1.00) i REFERENCE ARRR Technical Specifications, Sec. 11.2. ARRR Study Guides and Tests. Test #6, Question 3. ARRR Reactor Operator Training Manual, Volume 1, Sec. IV.D. (***** CATEGORY K CONTINUED ON NEXT PAGE *****)

h K. FUEL HANDLING AND CORE PARAMETERS Paco 37 ANSWER K.05 (2.50) a. Fuel elements must be visually inspected for defects. (1.00) b. Inspections are done every two years. (0.50) c. Any two of the following at 0.50 points each: 1. Significant bowing. 2. Significant swelling. 3. Excessive corrosion. 4. Cladding failure. (1.00) REFERENCE ARRR Training Guides and Tests, Test #6, Question 24. (***** CATEGORY K CONTINUED ON NEXT PAGE *****)

IC. FUEL HANDLING AND CORE PARAMETERS Pcg3 3E l 0 ANSWER K.06 (3.00) Based on nuary 1988 core loading. (y ( f/ c,ed;r 9e ev " < r r,4) 4,); II a e e q*T See sketch be ow for a to e. f,e.go,, (g fo,,,g.,e4,3 ;, p,<n $ j c,V(Each 0.50) / 'I#4 "' 6 " '

/" " J "'i T (O.50)

A I ^ * * ' f. Fuel element. be conec r ce e red;r w ; // ke La r. f- ~ 50vRcE, Q7 N

e O@'X y

66 1 h x \\ Es 1 0 ' C,I D cl FI I d Ts \\OOO O 8@ au REFERENCE ARRR Reactor Operator Training Manual, Vol. 2, Sec. III.4.3, Fig. III-4. ANSWER K.07 (2.00) .s. The critical rod position would be higher. b. The change in rod position would not be affected. (***** CATEGORY K CONTINUED ON NEXT PAGE *****)

K. FUEL HANDLING AND CORE PARAMETERS Pega 39 REFERENCE AGNIR Reactor Physics Tests, Fig. 9, Core component reactivity worth as a function of core position. ARRR Reactivity Loss to Power Procedure. ANSWER K.08 (2.50) a. 68 (0.50) b. More than half the number of fuel elements projected to be required to reach criticality were added in many steps [1.00]. Steps 2,3,4, & 5 for Detector A [0.50] Steps 4 & 5 for Detector C [0.50). REFERENCE ARRR Training Guides and Tests, Test #5, Questions 20 and 21. (***** END OF CATEGORY K *****) l

L. ADMINISTRATIVE PROCEDURES, CONDITIONS Pega 40 AND LIMITATIONS ANSWER L.01 (3.00) a. The change to the ORF changed the intent of the procedure and therefore a temporary change was not allowed. (1.00) b. Technical Specification 12.1.3.2. (1.00) c. The Reactor Supervisor. (1.00) REFERENCE ARRR Technical Specifications, Sec. 12.1.3.2 & 12.2.2. ARRR Administrative Procedures, Sec. B.6.d. / ANSWER L.02 (3.00) 2 eT8 a. Sec. 6.4. t OR Reactor sequence, interlocks and safety circuits shall remain operable while fuel is in the core except that one channel may be removed for main 'enance purposes when the reactor is shutdown. (1.00), b. Immediately re air or replace one of the two failed detectors. OR Unload th core. (1.00) c. Should port to the NRC [0.50) within 10 days [0.50]. (1.00) REFERENCE ARRR Te9 nical Specifications 6.4 and 1.3. h ARRR License, Sec. D. 7 (***** CATEGORY L CONTINUED ON NEXT PAGE *****)

e L. ADMINISTRATIVE PROCEDURES, CONDITIONS Paga 41 AND LIMITATIONS ANSWER L.03 (2.00) An authorized representative of the facility licensee shall certify that (0.66): 1. the qualifications and status of the licensee are current and valid [0.67) 2. the licensee has completed a minimum of six hours of shift function under the direction of and SRO (including a complete tour of the plant and all shift "turnover" procedures) [0.67). REFERENCE 10CFR55.53(f) ANSWER L 04 (1.00) Because it renders the water radiation monitor inoperable. REFERENCE ARRR Reactor Annunciator Responses, p. 5. ARRR Technical Specifications, Sec. 7.3. ARRR Training Guides a'nd Tests, Test #5, question 8. ANSWER L 05 (1.50) a. TWO (0.50) b. One must be a licensed Operator. (1.00) l 1 l l (***** CATEGORY L CONTINUED ON NEXT PAGE *****)

L. ADMINISTRATIVE PROCEDURES, CONDITIONS Pcco 42 j AND LIMITATIONS REFEREliCE 1 ARRR Technical Specifications, Sec. 10.1. Training Guides and Tests, Test #1, Question 1. ANSWER L.06 (2.00) 1. During initial startup and approach to power. l 2. During refueling. 3. During recovery from an unplanned shutdown. 4. During significant power reductions. REFERENCE ARRR Operating Procedures, Sec C.2. ANSWER L.07 (1.00) Tha key is secured by having it: 1. under the control of a licensed operator (0.50] 2. in a locked storage area (0.50]. REFERENCE ARRR Technical Specifications, Sec. 1.1. ARRR Operating Procedures, Sec. C.6. ANSWER L.08 (2.00) 4 a. Until the NRC authorizes disposition. (1.00) b. Until the operator's license is renewed. (1.00) (***** CATEGORY L CONTINUED ON NEXT FAGE *****)

i L. ADMINISTRATIVE PROCEDURES, CONDITIONS Pcga 43 AND LIMITATIONS REFERENCE 10CFR50.71(c) 10CFR55.59(c)(5)(1) ARRR License, Sec. E(4). ANSWER L 09 (2.00) 1. To far litate a head count (personnel accountability) [1.00]. 2. Because the control room is pressurized with clean air from outside (1.00]. REFERENCE ARRR Training Guides and Tests, Test #4, Question 29. ARRR Emergency Plan, Sec. E. ARRR Reactor Operator Training Manual, Vol. 2, Sec II.1. ANSWER L.10 (1.00) Radiological Safety Officer. REFERENCE ARRR Emergency Plan, Sec. C.2. ANSWER L.11 (1.00) If it is obvious that the fire cannot be controlled by portable fire fighting equipment within the facility then the fire department should be called. J (***** CATEGORY L CONTINUED ON NEXT PAGE *****) J

- L. ADMINISTRATIVE PROCEDURES, CONDITIONS Page 44,1 AND LIMITATIONS I' f F l REFERENCE ~ ARRR General Emergency Procedure, Sec. C 6. i ANSWER L.12 (1.00) s a. Radiation Safety Officer. (0.50) b. Reactor Supervisor. (0.50) REFERENCE ARRR Emergency Plan, Sec. C.1. y / it t (***** END OF CATEGORY L *****) (**t++***** END OF EXAMINATION **********) Io 1 / l l s

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P;ge 1 of 5 OATA SHEET l REftC10R THEORY FORRLAS: e /T t P = Po 5UR(t) P = Po10 f{th V i P= I 3.12 x 1010 fissions /sec leff p = f + 1 + AT T T : _!.* p T = leff - p_ Ap op = In K (final) K (initial) p = K-1_ K SLR = 26.06 7 Kerr = c Pr p Pth f T1 2 2 -(B Lth ) 3 p 2 1 + (B2 Lth ) 2 2 Lt) Pr = e-(8 p = e-( N 3 [.Ierr) it s C1 (1-Kerri) = C2 (1 - Keff2) m= 1_ = C (final) 1-K C (initial) B2(Rf2 + Eg2) a7 = 1 Af + 1 Ap f At p at At 'At

h Page 2 of 5 DATA SHEET I l THERM 3 DYNAMICS AND F1UIDECHANICS FORMAAS_: 6=AAh Q = 2 : LAT + in R /R2 1 + in R /R1 3 2 Q = UA(AT) i K3 6=AC(AT) K K2 p 6==6A'R4 4=61n-6out din n = (h n - hout) REAL i (hin - hout) IDEAL np = W ACTUAL 1 W SUPPLIED PV11 =PV22 l 1 T1 T2 AV AV P2 2 2 P111: l m = pAV in = KA / A Px p 1 KA Ap / AP KA AT / AT 3/ $ inNC=KAQ = = ATm = AT (IN) - AT (OUT)_ In ( AT (IN) ) AT (OUT) l G= rf(th 8.8 x 109 T L - Tps = Gr2 C a 6=kAAT Ax \\ i=AATtotal AXA + AXg... + AXN N' KA ks N n- - - e m. -,e- -m e --,,,------+-.---,-,..---g n- - - - ,---n--- ,-e + - -, w,

1 V Page 3 of 5 04TA SE ET ENTRIFUGAL PUW LAWS (Speed )3 Powerl Speed 1 Flowl (Speed )2 Headi i 1 = = = ISpeed )3 Power 2 Speed 2 Flow 2 . (Speed )2 Head 2 2 2 RADIATION ANO DEM1STRY FORKJLAS_: RAir = 6CE Ix = Io e* d2 CVI1=CV22 t /2 = 0.693 C = Q e4t 1 A G = 011ution Rate A = AN Volume A = Ao -At e I = Io(iln 10 CONVERSIONS: Density of water (20*C) = 62.4 Itra/ft3 = Ig/cm3 3 1 gm/cm3 = 62.4 1,.2/ft 1 gal = 8.345 lbm Avogrado's Number = 6.023 x 1023 1 ft3 = 7.48 gal Heat of Vapor (H O) = 970 Btu /lbm 2 1 gal = 3.78 liters Heat of Fusion (ICE) = 144 Btu /lbm 1 lbm = 454 grams 1 AMJ = 1.66 x 10-24 grams e = 2.72 Mass of Neutron - 1.008665 AHJ = 3.1415 1 KW = 738 ft-lbf/sec Mass of Proton = 1.007277 ARJ Mass of Electron =.000549 AMJ 1 KW = 3413 BtuAtr One atmosphere = 14.7 psia = 29.92 in. Hg. abs. 1 HP = 550 ft-lbf/sec 'F = 9/5 C + 32 1 HP =.746 13t 1 HP = 2545 BtuAir 'R = *F + 460 'C = 5/7 ('F-32) 1 BTU = 778 ft-lbf 1 EV = 1.54 x 10-16 BTU

K = *C + 273 h = 4.13 x 10-21 M-sec IW = 3.12 x 1010 fissions /sec go = 32.2 lttn - ft IBf - sec2 1 CAL / TRAM = 1.8 Btu /lbm C2 = 931 EV/AMJ C = 3 x 108m/sec 1 in. = 2.54 CM o = 0.1714 x 10-8 Btu hr ftZ

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l Page 4 of 5 1 DATA SEET I~ AVERAT TEIUML CDOUCTIVITY (K)_ BTU /hr-ft 'F Material O.025 Cork Fiber Insulating Board _ 0.028 0.096 Maple or Oak Wood 0.4 Building Brick 0.45 Window Glt.cs 0.79 Concrete 1 Percent Carbon Steel 25.00 1 Percent Chrome Steel 35.00 118.00 Aluminum 223.00 Copper 235.00 Silver 0.392 Water (20 psia, 200'F) Steam (1000 psia, 550*F) 0.046 1.15 Uranium Dioxide 0.135 Helium 10.0 Zircaloy MISCELLAEOUS IWDFUMTION: E = mc2 f E = 1/2 mv2 PE = mgh Vf = Vo + at AE = 931 &n AREA VOLUE E0ETRIC OtLECT A = 1/2 bh ////////////////h TRIANr3 E n' = s2 ////////////////// Souane ////////////////// A=LxW RECTANr3E A = vr2 ////////////////// CIRCLE A = 2(LxW + LxH + WxH) V=Lxwxh RECTANGUl)R SOLID RIGiT CIRrU__AR CYLINDER A = (2 vr2)h + 2(vr2) V = vr2h A = 4 vr2 V = 4/3 Tr3 SRtRE 3 //////////////////////h V = S CUBE

s Page 5 of 5 \\ ORTA SE ET MISCELLATOUS IWORH4 TION CDNTINlED: 10 CFR 20 Appendix B Gamma Table I Table II Energy Col I Col 11 Col I _ Col II EV per Air Water Air Water Material Half-1.ife Disintegratior uc/ml uc/ml uc/ml oc/ml Ar-41 1.83 h 1.3 Sub 2xiO-6 4x10-8 Co-60 5.27 y 2.5 S 3x10-7 1x10-3 1x10-8 5x10-5 1-131 8.04 d 0.36 S 9x10-9 6x10-5 1x10-10 3x10-7 Kr-85 10.72 y 0.0L Sub 1x10-5 3x10-7 N1-65 2.52 h 0.59 S 9x10-7 4x10-3 3x10-8 1x104 y 0.003 S 2x10-12 1x10-4 6x10-14 5x10-6 Pu-239 2.41x104 S 1x10-9 1x10-5 3x10-11 3x10-7 Sr-90 29 y Xe-135 9.09 h 0.25 Sub 4x10-6 1x10-7 Any single radionuclide with T /2> 2 hr 1 which does not decay by a or s;xr.taneous 3x10-9 9x10-5 1x10-10 3x10-6 fission Neutron Energy (EV) NeJtrons per cm2 Average flux to deliver eculvalent to 1 rem 100 mren in 40 hours Thermal 970 x 106 60 0.02 400 x 106 280 (EUTRONS) g g sec lb' N06 LIEAR ABSORPTION CDEFFICIENTS y (m-1) Energy (EV) Water Corcrete Iron Lead 0.5 0.C90 0.21 0.63 1.7 1.0 0.067 0.15 0.44 0.77 1.5 0.057 0.13 0.40 0.57 2.0 0.048 0.11 0.33 0.51 2.5 0.042 0.097 0.31 0.49 3.0 0.038 0.088 0.30 0.47

l i l REFERENCES 1. Technical Specifications 2. License 3. Administrative Procedures 4. 10CFR50 5, 10CFR55 i I 1 i

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a e en e k l TECHNICAL SPECIFICATIONS l i l

e-APPENDIX A LICENSE NO. R-98 TECHNICAL SPECIFICATIONS FOR THE AER0 TEST RADIOGRAPHY AND RESEARCH REACTOR (ARRR) 1.0 Definitions 1.2 Reactor Operation Reactor operation shall mean any condition wherein the reactor is not shut down. 1.3 Operable A system or component shall be considered operable when it is capable of performing its required function in its normal manner. 1.4 operating A component or system is operating if it is performing its required function in its normal manner. 1.5 Experiment Experiment shall mean any apparatus, device, or material installed in the core or experimental facilities (except for underwater lights, fuel storage racks and the like) which is not a normal part of these facilities. 1.6 Experimental Facilities Experimental facilities shall mean Glory Hole, vertical tubes, pneumatic transfer systems, central thimble, beam tubes, thermal column, and in-pool irradiation facilities. 1.7 Reactor Safety Circuits Reactor safety circuits shall mean those circuts, including their associated

input circuits, which are designed to initiate a reactor scram. 2.0 Reactor Site 2.1 The reactor and associated equipment is located within an exclusion area. 2.2 A steel, locked perimeter fence shall surround the ARRR facility, forming an exclusion area. The minimum distance from the center of the reactor pool to the boundary of the exclusion area fencing shall be 50 feet. The restricted area, as defined in 10 CFR 20, shall consist of the entire exclusion area, i 2.3 The principal activites carried on s-ithin the exclusion area shall be those associated with the operation of the ARRR reactor and the use of a hot cell and chemistry laboratory. ) 3.0 Reactor Building 3.1 The reactor shall be housed in a steel building capable of meeting { the following functional requirements: i 3.1. all circulating fans and air conditioning systems except the system which supplies air to the control room shall have the capability to be shut off from a single control in the control room. 3.1.2 ventilation shall be achieved by gravity ventilators located on the roof of the building, and 3.1.3 a positive air pressure shall be maintained in the control room with respect to the reactor room. 3.2 An alarm system shall be installed to detect unauthorized entry into the reactor building. The alarm system shall be monitored constantly and its annunciation shall be tested monthly. 4.0 Reactor Pool (Primary System) 4.2 The pH and conductivity of the primary coolant shall be measured at least once each month. Corrective action shall be taken to avoid exceeding a pH of 7.5 or a conductivity of 5 umho/cm.

5.0 Reactor Core 5.1 Fuel Elements 5.1.1 The reactor shall contain no more than 90 TRIGA type fuel elements. The core shall be loaded with not more than 3.30 kg of U-235. 5.1.2 The maximum excess reactivity above cold, clean critical, with or without experiments in place, shall be 3 dollars. 5.1.3 The bath temperature coefficient and the prompt fuel temp-erature coefficient shall be negative at all operating temp-eratures and the minimum reactivity decrement at full power j shall be 80 cents when measured with respect to source power level. 5.1.4 The coolant void coefficient shall be negative across the active core. Maximum in-core operating void shall be 10% of the coolant core volume as defined by a cylinder bounded by the grid plates. 5.2 Reflector Elements l 5.2.1 The overall reflector elements' dimensions shall be the same as the fuel elements. 5.3 Control Elements l 5.3.1 The reactor shall be suberitical by a minimum margin of 0.50 dollar when the maximum worth rod is fully withdrawn from the core. 5.3.2 The maximum rate of reactivity addition for the control rods shall be 11 cents /second. There shall be a minimum of three operable control elements. 5.3.3 The total time for insertion of the control rods following receipt of a scram signal by the safety system shall be a maximum of 600 milliseconds. 6.0 Reactor Safety Systems 6.1 The reactor safety system shall include sensing devices and associated circuits which automatically actuate visual and audible alarms and, when certain pre set limits are exceeded, scram the reactor. --.-,-..-w%,,,,~.w=. y+, ,-,y.,c, ,mwee,we-,ee3+c w

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i 6.2 The nuclear, process and radiation monitoring instrumentation shall provide the functions and have the set point ranges and associated annunciations listed in Table 2 of these specifications. 6.3 The safety system shall be designed such that no single component failure or circuit fault shall simutaneously disable both the auto-matic and manual scram circuits. 6.4 Reactor sequence, interlocks and safety circuits shall remain operable while fuel is in the core except that one channel may be removed for maintenance purposes when the reactor is shut down. 6.5 Interlocks shall prevent safety rod withdrawal unless all of the following conditions exist: 6.5.1 The master switch is in the ON position; 6.5.2 The safety system has been reset; / 6.5.3 All four nuclear instruments channels are in the OPERATE mode; 6.5.4 The startup channel count rate is greater than 2 cps. It shall not be possible to withdraw more than the safety rod until it has reached the upper limit interlock, at which time either the shim or regulating rod may be moved, but only one at a time. 6.6 During a critical experiment a suberitical multiplication plots shall be obtained from at least three instrumentation channels. These channels may be used in addition to the normal operating instrumentation in Table 1. 6.7 Process instrumentation with readout in the control room shall be operating to permit continous indication of pool water temperature and conductivity. Alarms shall be operable to indicate low water flow, low pool water and improper location of the crane bridge. 700 Radiation Monitoring

q 7.4 Portable survey instruments for measuring beta-gamma dose rates in the range of 0.01 mr/hr to 50 r/hr shall be available to the facility. 7.5 Portable instruments for measuring fast and thermal neutron dose rates from 0.1 mrem /hr to 1.0 rem /hr shall be available at the facility. 7.6 Radiation detector packets containing a series of threshold detectors shall be placed at several locations within the reactor building for post-accident radiation analysis. 8.0 Experimental Facilities 8.1 Large-Component Irradiation Box 8.1.1 A large-component irradiation box shall have a maximum volume of 20 cu. feet. The box shall encompass not more than 120' arc of the core and shall be designed so that it can be placed no closer than 5 cm to the outer row of active fuel elements. 8.1.2 The platform shall be positioned remotely relative to the reactor core by a positive drive and shall be captive to the s'tand which ic bolted to the floor of the tank. Positive mechanical stops shall provent moving the experiment box into the active reactor core. CO2 shall be used for purging and to maintain a slight positive pressure in,the box relative to the pool water pressure. 8.1.3 To remove or install the experiment box, the platform shall be moved two or more feet away from the reactor core. The box shall then be lowered onto the platform and bolted in place with remote handling equipment. The voided box shall be purged of air prior to exposure to neutrons. 8.2 Pneumatic Transfer Facility 8.2.1 A pneumatic transfer f acility may be located in any reactor core position. The facility shall be operated with dry CO2 and ex-hausted through a filter ventilation system, which is monitored for radioactivity. 8.2.2 The in-core portion of the transfer facility shall have a max-imum void volume of 34 cu. in. in the active fuel region. A manual control shall be provided which is capable of overriding the automatic ttmer control. 8.3 Glory Hole Facility 8.3.1 A dry glory hole facility may be located in any reactor core position. The glory hole shall accept capsules to a maximum of 1.35 in. in diameter. 8.3.2 The glory hole shall be purged with C0 to prevent formation of ex. 7 cessive amoents of argon-41. Gas samples shall be taken near the pool when the glory hole facility is operated without a shield plug to insure c4 equate monitoring of radioactive gases. 8.4 Neutron Radiography Facility 8.4.1 The beam tube shall consist of c two-section tapered tube having a rectangular cross section. The upper and lower sections of the t2be shall be equipped with a fill and drain line. 1 8.4.2 All components contacting the pool water shall be fabricated j f rom aluminum or stainless steel. 8.4.3 The beam catcher shield shall consist of a movable radiation shield. 8.5 Thermal Column 8.5.1 The thermal column shall be positioned remotely on steel locating ) pins immediately adjacent to the reactor core. 8.5.2 The thermal column shall be composed of a three-foot cube of grap-hite encased in aluminum containg five rows of 1.5 in. diameter irradiation holes. The rows shall be placed 6 inches apart and contain seven holes per row. Slotted beams shall be provided to allow experiments to be attached directly to the thermal column. 8.6 Vertical Tube 8.6.1 Vertical irradiation tubes, having diameters up to 6 in, may be attached to the thermal column.

7-8.6.2 The vertical tube shall be purged with CO t prevent the formation 2 of excess amounts of argon-41. 8.7 Other Irradiation Facilities 8.7.1 The central 7 fuel elements of the reactor may be removed from the coreandacentralirradiationfacilityinstalledgrovidedthecross-section area of the facility does not exceed 16 in 8.7.2 Two triangular exposure facilities are available which shall allow the insertion of circular experiemnts to a maxin.um of 2.35 in dia-meter or triangular experiments to a maximum of 3.0 in. on a side. 8.7.3. Irradiation capsules in the shape of dummy fuel elements shall have a maximum inner void volume of 34 cu. in. in the active fuel region. 9.0 Experiment Limitations 9.1 Experiments shall be evaluated in the most reactive condition. 9.2 The documentation of experiments, which shall be reviewed and app-roved prior to insertion in the reactor, shall include at least: 9.2.1 The purpose of the experiment; 9.2.2 A description of the experiment; and 9.2.3 An analysis of the possible hazards associated with the per-formance of the experiment. 9.3 The value of the reactivity worth of any single independent experiment shall not exceed 2 dollars. If such experiments are connected or other-wise related so that their combined resctivity could be added to the core simultaneously, their combined reactivity shall not exceed 2 dollars. 9.4 The reactivity worth of any single independent experiment not rigidly fixed in place shall not exceed 1 dollar. If such experiments are connected or otherwise related so that their combined reactivity,could be added to the core simultaneously, their combined reactivity worth shall not exceed 1 dollar. 9.5 No experiment shall be installed in the reactor in such a manner that it could shadow the nuclear instrumentation system monitors. e e -,m.--,. - -, - 3 .--.,_. - - ~ ,,,-,-,w,,w~.-,---,w.-3,,.--,,---,v-,-m.,_y~~w.. w., y,---w---

6 / /' ^ ic; I 9.6 No experiment shall be installed in the reactor in such a manner that a-failure could interfere with the insertion of a reactor control element. 9.7 No experiment shall be performed involving materials which could: 9.7.1 Contaminate the reactor pool causing corrosive action on the reactor components or expe:Imants; 9.7.2 Cause excessive production of airborne radioactivity; or 9.7.3 Produce an uncontained vicient chemical reaction. 9.8 Experiments shall not be performed involoving equi nent whose failure could result in fuel element damage. ( 9.9 The amount of special nuclear material contained in an experi-ment shall be limited to 5 grams in tre1 form of solid samples or 3 grams in the form of liquid. Liquid special nuilear materials shall be doubly encapsulated. 9.10 Experiments having moving parts shall be designed to have reactivity insertion rates less than 10 cents /sec except that moving parts worth less than 5 cents may be oscillated or removed at higher frequencies. 9.11 Solid explosive materials may be broust into the facility for the purpose of being radiographed in the neutron radiography facilities located above the pool; provided that the following conditions are met; 9.11.1 Individual explosive devices shall be limited to 1000 grains equivalent TNT sncased in metallic sheathing. 9.11.2 The mexi=um quantity of explosive material that may be possessed at one time shall be limited to 50 pounds equivalent TNT. 9.11.3 Explosive material shall be stored in designated areas within the reactor facility. 9.11.3.1 Only the explosive devices to be radiographed i within 4 hrs not to exceed a maximum of ten l pounds equivalent TNT, may be removed from the storage area at one time for radiographing, in-cluding preparation but excluding packaged shipments.

[ p r 9.11.3.2 An accountability log shall be maintained to show the amount of explosive material ^ in the reactor facility at all times, and shall contain a description of the explosive, and the location within the facility (e.g.. storage, radiographing facility, or shipping' dock). 9.11.4 The maximum amount of explosive material con-tained in devices that may be placed in the radiography facilities at a time shall be limited to five pounds equivalent TNT. 9.11.4.1 Explosive material in the radiation field at one time shall be limited to 1 pound equivalent TNT. t 5 9.11.4.2 Explosive material contained in long device (s) shall be limited to 0.5 pound equivalent TNT per foot. 9.12 Personnel handling the explosive devices shall be trained and familiar with the devices being radiographed. 9.12.1 Personnel handling the explosive devices shall use special equipment, such as nonsparking tools and shoes, protective clothing, safety shields and grounded benches as required for the explosives being handled. 9.12.2 Unshielded high frequency generating equipment shall not be operated within 50 feet of any explosive device. 9.12.3 The explosive device shall be subjected to a total ex-posure not to exceed 3 x 1011 neutrons /cm2 and 3 x 103 roentgens of gammas. 9.12.4 Explosive devices that, upon ignition, have or provide a thrust in a definite direction shall be positioned so as to be aimed away from the reactor and components. 10.0 General Operating Limitations 10.2 The reactor shall not be operated wherever there are significant defects in fuel elements, control rods or control circuitry. 10.3 Upon occurrence of abneraal operation of the reactor, including its controls, safety systems and auxiliary systems, action shall be taken immediately to secure the safety of the facility and determine the cause of the abnorual behavior.

? 11.0 Fuel Storage and Transfer 11.1 The fuel storage pits located in the floor of the reactor room shall accommodate a maximum of 19 fuel elements (700 gm U-235)in storage racks dry or flooded with water. The fuel storage pits shall be secured with a lock and chain except during fuel transfer operations. l l 12.0 Administrative Requirements l 12.1 Organization 12.1.1 The Reactor Supervisor shall have responsibility of the reactor facility. In all matters pertaining to reactot operations and to these Technical Specifications, the Reactor Supervisor shall be responsible to the President, Aerotest Operations, Inc., a wholly-owned subsidiary of Explosive Technology, Inc. The President, Aerotest Operations Inc. shall report to the Board of Directors of Aerotest Operations, Inc. which includes the Presidents of bc th OEA, Inc. and Explosive Technology, Inc. 12.1.2 The Radiological Safety Officer shall revteu and approve all procedures and experiments involving adiological safety. He shall enforce rules, regulations and proc 0dures relating to radiological safety, conduct routine radiation surveys and is responsible to the !!anager, Aerotest Operations. 12.1.3 The Reactor Safeguards Committee shall be composed of not less than five members, of whom no more than three are members of the aperating organization. The committee

I L L shall meet on call of the chairman and they shall meet at least annually. The committee shall be responsible for, but not limited to the following: 12.1.3.1 Reviewing and approving nuclear safety standards associated with the use of the facility; 12.1.3.2 Reviewing and approving all proposed experiments and procedures and changes'thereto, and modifications to the reactor and its associated components. 12.1.3.3 Determining whether proposed experiments, procedures or modifications involve unreviewed safety questions, as defined in 10 CFR 50. Part 50.59(c), and are in accordance with these Technical Specifications; 12.1.3.4 Conducting periodic audits of procedures, reactor operations and maintenance, equipment performance, and records; 12.1.3.5 Reviewing all reported abnormal occurrences and violations of these Technical Specifications, evaluating the cause of such events and the corrective action taken and recommending measures to prevent reoccurrence and; 12.1.3.6 Reporting their findings and recommendations con-cerning the above to the Manager, Aerotest Operations. 12.1.4 The Reactor Supervisor shall have a Eschelor's degree in Engineering or Physical Science and shall have a minimum of 4 years experience in the operation of a nuclear facility during which he shall have demonstrated competence in supervision and reactor operations. He shall hold a Senior Reactor Operator License for the facility. 12.1.5 The Radiological Safety Officer shall have a Bachelor's degree in Biological or Physical Science and shall have a minimum of 2 years experience in persennel and environmental radiation monitoring programs at a nuclear facility. Certification as a Health Physicist by the Health Physics Society is acceptable in lieu of the education and experience requirements given abov'e. 12.2 Procedures 12.2.1 Detailed written procedures shall be provided and followed for the following reactor operations: 12.2.1.1. Normal startup, operation and snutdown of the complete facility and of all systems and components involving nuclear safety of the facility. 12.2.1.2. Refueling operations.

12.2.1.3 - Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, in-cluding responses to alarms, suspected primary system leaks and abnormal reactivity changes. 12.2.1.4 Paragraph omitted. 12.2.1.5 Preventive or corrective maintenance operations which could have an effect on the safety of the reactor. 12.2.2 Temporary procedures which do not change the intent of previously approved procedures may be utilized on approval by a licensed Senior Reactor Operator and one other qualified individual. Such procedures shall be subsequently reviewed by the Reactor Safe-guards Committee. 12.3 R,ecords In addition to those records required under the facility license and applicable regulations, the following recorde shall be kept when explo-sive materials are to be irradiated or radiographed: 12.3.1 The type and quantity of material irradiated. 12.3.2 Date, time of day, and length of exposure. 12.3.3 Tocal neutron and gamma exposure level. i

i-e LICENSE f i (

t UNITED STATES 9 ATOMIC ENERGY COMMISSION U WASHINGTON. D.C. 20$45 '4 October 22, 1974 Docket No. 50-228 Aerotest Operations, Inc. ATTN: Mr. R. L. Newacheck President 3255 Fostoria Way San Ramon, California 93583 Gentlemen: The Conunission has issued the enclosed Amendment No.1 to Facility License No. R-98 which includes Change No. 8 to the Technical Specifications. The Amendment transfers the license from the Aerojet-General Corporation to Aerotest Operations, Inc., a wholly-owned subsidiary of Explosive Technology, Inc., itself a wholly-owned subsidiary cf OEA, Inc., and redesignates the reactor at the Aerotest Radiography and Research Reactor (ARRR). A copy of the related Safety Evaluation is also enclosed. Also enclosed are two copies of Amendment No. 13 to indemnity Agreement 1 No. B-2 transferring the indenmity coverage for the facility from Aerojet-General to Aerotest Operations, Inc. Please sign and return one copy of the agreement to the Directorate of Licensing. Sincerely, i 1 Q &~ Robert A. Purple, Chief Operating Reactors Branch #1 Directorate of Licensing

Enclosures:

1. Amendnant No. i 2. Safety Evaluation 3. Amendment No. 13 to Indemnity Agreement No. B-2 (2 cys) cc: See next page ,-..w, p 9 -~ ~ * -T"'~* ^ ^ " ^' ' * ' '

e s g, UNITED STATES I' h / \\. ATOMIC ENERGY COMMISSION l wAsm NGToN, D.C. 20545 Vg L AER0 TEST OPERATIONS, INC. DOCKET No. 50-228 .\\ER0 TEST RADIOGRAPHY AND RESEARCH REACTOR (ARRR) AMEND:IENT 10 FACILITY OPERATING LICENSE Amendment No. 1 License No. R-98 1. The Atomic Energy Commission (the Commission) has found that: A. The appliention for transfer of license filed by OEA, Inc. for Aerotest Operations, Inc. (the licensee) complies with the ctendcrdo cad requircrents cf the Atomic Energy t.ct of 1954, cc auended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. Construction of the facility has been substantially completed in conformity with Construction Permit No. CPRR-86, and the application, as atended, tha provisions of the Act and the rules and regulations of the Co= mission; l C. The facility will operate in conformity with the applicatica, as i atended, the provisions of the Act, and the rules and regulations of the Commission; D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in conpliance with the rules and regulations of the Commission; l E. Aerotest Operations, Inc. is technically and financially qualified i to possess, use, and operate the facility in accordance with the rules and regulations of the Commission; e

( s' u. 3 I , F. The issuance of this operating license will not be inimical to the common defense and security or to the health and safety of the public, and does not involve a significant hazards con-sideration; G. The receipt, possession, and use of byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30 and 70, including _ Sections 30.33, 70.23, and 70.31; H. The licensee is qualified to be the holder of the license; and I. The transfer of the license is othervi== consistent with applicable provisions of law, regulations, and orders issued by the Commission pursuant thereto. 2. Facility Operating License No. R-98, previously issued to Aerojet-General Corporation, is hereby transferred to Aerotest Operations Inc. and the license is reissued in its entirety to read as follows t A. This license applies to the Aerotest Radiography and Research Reactor (ARRR), previously called the Aerojet General Nuclear Industrial Reactor (AGNIR), a peol-type nuclear reactor owned by the OEA, Inc. The facility is located at the Aerotest Operations site near San Ramon, California, and is described in the application dated September 14,1954 (the application), and in supplements thereto, including the application for transfer of license dated April 24, i 1974. I B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Aerotest Operations, Inc.. 4 (1) Pursuant to Section 104c of the Act and 10 CFR Part 50, j "Licensing of Production and Utilization Facilities", to possess, use, and operate the reactor at the designated j location in San Ramon, California, in accordance with the proceduras and limitations set forth,in this license; 3 (2) Pursuant to the Act and 10 CFR Part 70, "Special Nuclear Material", to receive, possess, and use up to 5.0 kilograms of contained uranium 235 in connection with operation of the reactor; and I (3) Pursvant *o the Act and 10 CFR Part 30, "Licensing of Byproduct Material", (1) to receive, possess, and use a i 2 curie americium-beryllium neutron startup source, and (2) to. possess, but not to separate, such byproduct material as may be produced by operation of the reactor. 1 4

p C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission r'egulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicabic provisions of the Act and to the rules, regulations, and orders of the Commission now or hereaf ter in ef fect; and is subject to the additional conditions specified or incorporated below: (1) Riximum Power Level The licensee is authorized to operate the facility at steady state power levels not in excess of 250 kilowatts (thermal). (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised, are hereby incorporated in the license. The licensec shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Chance No. 8. D. Reporte In addition to reports otherwise required under this licensu and applicable regulations: (1) The licensee shall report in writing to the Comnission within 10 days of its observed occurrence any incident or condition relating to the operation of the facility which prevented or could have prevented a nucicar system from performing its safety function as described in the Technical Specifications or in the Hacards Summary Report. (2) The licensee shall report to the Commission in writing within 30 days of its observed occurrence any substantial variance disclosed by operation of the facility from performance speci-fications contained in the Hazards Summ-, Report or the Technical Specifications. (3) The licensec shall report to the Commission in writing within 30 days of its occurrence any significant change in transient or accident analysis, as described in the Hazards Su= mary Report. E. Records In addition to those otherwise required under this license and appli-cable regulations, the licensee shall keep the following:

1 l J f, (1) Reactor operating records, including power levels. (2) Records of in-pile irradiations. (3) Records showing radioactivity released or discharged into the air or water beyond the effective control of the licensee as measured at the point of such release or discharge. (4) Records of emergency reactor scrams, including reasons for emergency shutdowns. F. This amended license is effective as of the date of issuance and shall expire at midnight spril 16, 2005, i FOR THE ATOMIC ENERGY COMMISSION ~ Karl R. Coller, Assistant Director for Operating Reactors Directorate of Licensing

Attachment:

Change No. 8 to the Technical Specifications Date of Issuance: October 22, 1974 i i l

ATTACIDtENT TO LICENSE AMENDMEYI NO. 1 CHANGE NO. 8 TO APPENDIX A 0F TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NO. R-98 DOCKET No. 50-228 Revise Appendix A as follows: 1. Change the name of the reactor to "Aerotest Radiography and Research Reactor (ARRR)". 2. Paragraph 2.1 - end the sentence after the words "exclusion area". 3. Paragraph 2.2 and 2.3 - change the abbreviation "AGNIR" in the first sentence to read "ARRA". 4. Paragraph 12.1.1 - revise the paragraph to read as follows: "12.1.1 The Reactor Supervisor shall have responsibility of the reactor facility. In all matters pertaining to reactor operations and to these Technical Specifications, the Reactor Supervisor shall be responsible to the President, Aerotest Operations, Inc., a wholly-owned subsidiary of Explosive Technclogy, Inc. The President, Aerotest Operations, Inc. shall report to the Board of Directors of Aerotest Operations, Inc. which includes the Presidents of both OEA Inc. and Explosive Technology, Inc." P i ( i

s.---. . ~ - - UNITED STATES I 6 {, ATOMIC ENERGY COMMISSION WASHINGTON. D.C. 20S49 1 SAFETY EVALUATION BY THE DIRECTORATE OF LICENSING SUPPORTING AMENDMENT NO.1 TO LICENSE No. R-98 (CHANGE NO. 8 TO THE TECHNICAL SPECIFICATIONS 1 AER0 TEST OPERATIONS. INC. DOCKET No. 50-228 By application dated April 24, 1974, OEA, Inc. requested transfer of title of the Aerojet-General Nuclear Industrial Reactor (AGNIR) from Aerojet-General Corporation to Aerotest Operations, Inc., a wholly-owned subsidiary of OEA, Inc. Aerotest Operations, Inc., will be the new licensee for the reactor facility. The applicant has stated that there will be no changes to the facility and that the personnel responsible for operating the resetor will continue in ( their present duties. Thus, the technical qualifications of the new licensee are identical to those found acceptable upon initial issuance of the operating license to Aerojet-General Corporation. No changes will be made in the license for the facility, other than the transfer of title, and the present Technical Specifications for the facility will remain essentially unchanged. We have reviewed the financial qualifications of Aerotest Operations, Inc., and have concluded that it possesses or can obtain the necessary funds to l meet the requirements of 10 CFR Part 50, Section 50.33(f) to operate the Aerotest Reactor Facility, and if necessary to permanently shut down the facility and maintain it in a safe shutdown condition. We find nothingin the application to suggest that the applicant or the other participating companies are owned, controlled or dominated by an alien. a foreign corporation or a foreign government. We also find that, in view of the nature of the proposed action, a transfer of title, there vill be no significant hazards involved. i i We have, therefore, determined that Aarotest Operations, Inc., is technically and financially qualified to operate the facility and that there is reasonable assurance that the reactor can be operated in the manner proposed without endangering the health and safety of the public. ( e

l SECTION I ADMINISTRATIVE PROCEDURES

i'. L l I,. ADMINISTRATIVE PROCEDURES A. Reactor Safeguards Committee Charter The Reactor Safeguards Committee shall be composed of not less than five members,. of whom no more than three are members of the operat-l ing organization. The committee shall meet on the call of the chair-1 man and they shall meet at least annually. Official committee action requires a quorum of a minimum of three (3) members, at least one of whom is not a member of the facility operating staff. The committee shall be responsible for, but not limited to the following: 1. Reviewing and appreving nuclear safety standards associated with the use of the facility; 2. Reviewing and approving all proposed experiments and proce-dures and changes thereto, and modifications to the reactor and its associated components; 3. Determining whether proposed erperiments, procedures or modifi-cations involve unreviewed safety questions, as defined in 10 CFR 50, Part 50.59(C), and are in accordance with the Technical Specifications; 4. Conducting periodic audits of procedures, reactor operations and maintenance, equipment performance,and records; 5. Reviewing all reported abnormal occurrences and violations of the Technical Specifications, evaluating the causes of such events and the corrective action taken and recommending measures to prevent recurrence, and; 6. Reporting their findings and recommendations concerning the above to the President, Aerotest Operations, Inc. To Be Incorporated As Procedure I,A APPROVED (original signed by) ,,,[R,L,NEW3 CHECK [,,, j g g President DATE ,,,1?,M3RCH_1??8,,,,,,, i Page 1 of 8 PCN 1 1

I. ADMINISTRATIVE PROCEDURES 8. Procedure Control 1-EWIE952 This procedure defines the requirement for procedures necessary for the safe and efficient operation of Aerotest Radiography and Research Reactor (ARRR). 2. Sgget All procedures required by the ARRR license, safety considerations, or any other deemed appropriate by the ARRR staff shall comply with these requirements. 3. Pggegdurg Wglling a. Procedures shall be written in a clear and concise manner to avoid confusion. Reference may be made to other documents provided that those documents are readily available to those using the procedures, b. Procedures may be generated by any Aerotest employee.' A member of the Aerotest staff shall prepare a Procedure Approval Sheet in accordance with Figure I and shall submit the same for review and approval by the Reactor Safety Committee (RSC). 4 Pggegdurg Fgrmat a. Procedures shall be written and issued in accordance with specific formating requirements. b. The general format shall be as follows: 1. General Title A. Specific Title (used when there is more than one area to be addressed such as "preventive maintenance" and "corrective maintenance". Category a. detail c. Each procedure shall include the following items where appropriate. Items marked with an

must be included (except in Procedure IA).

Page 2 of 8 PCN 1

I. ADMINISTRATIVE PROCEDURES Purpose

Data Retention Scope
Calibration Requirements Personnel Requirements Performance Checks Equipment Approvals / Signatures /

Restrictions Initials Required

Prerecuisites Instructions
i d.

Each page of the procedure shall be numbered as Page ___ of ___. If any item on that page has been revised the Procedure Change Number shall be on that page. The procedure number and name shall appear at the top of each page. 5. Rgylgy ggy AEEE9Yal a. All procedures shall be revised and approved by the Reactor Supers'sor and by the RSC in accordance with the following paragraphs of the Technir ', Specifications: 12.1.3.1. - Review and Approval 12.1.3.3. - Unreviewed Safety Questions All procedures af fecting radiological safety shall be reviewed and approved by the Radiological Safety Officer as required by Paragraph 12.1.2. of the Technical Specifications. b. Governing criteria for the review and approval shall be the following: ARRR License ARRR Technical Specifications 10 CFR as applicable Applicable federal, state, and local codes 6. [hggggg ggy ggylgliggg a. Temporary changes to procedures may be authorized by a Senior Reactor Operator and one other qualified 4 individual, provided that the changes are in compliance with paragraph 12.2.2. of the Technical i Specifications. Such changes shall be documented on a Procedure Change Notice (PCN). Temporary changes become void af ter 30 days unless submitted to the RSC for approval as permanent changes. Page 3 of 8 PCN 1

4 I. ADMINISTRATIVE PROCEDURES b. Permanent changes to the procedures require the same level of review and approval as the original. Such changes and subsequent approval shall be documented on a Procedure Change Notice (PCN) (Figure II) and ~ appropriate entries made on a Procedure Approval Sheet (Figure 1). c. Any ARRR Senior Licensed Operator may deviate from procedures as required during an emergency to' assure the health and safety of the staff and general public as required to assure plant safety, d. Deviations to procedures shall be reported to the Reactor Supervisor who shall determine the appropriate action required to make reports to the RSC as necessary, e. Typographic or spelling corrections may be made without issuance of a PCN. 7. Avallgbility a. One official and up-to-date copy of the procedures shall be maintained in the control room within easy access of the console operator. C. Operations Request Form 1-Pyrgggg This procedure provides guidelines and requirements for use of the Operations Request Form (ORF) (Figure III). 2-S1922 The scope of this procedure includes any situation in which the ORF is used but is specifically designed for maintenance activities. 3. Diliti21190 The ORF is a single page form which is designed to provide documentation and approvals required for various reactor related activites. It may be used for documentation only in any area where such documentation is required. i 4. Rgggiggd Ugg Use of the ORF is required when repairs are made to any portion of the Reactor safety system as described in j Procedure VIII.A.3.h. It is not required for j surveillance, calibration, or testing activities. Page 4 of 8 PCN 1 l I

I. ADMINISTRATIVE PROCEDURES l 5. &ggrgyglg The Reactor Supervisor or his designated alternate (s) shall determine the level of approval required for each act i vi t y. 6. Rgttg3j,og Completed ORF's shall be retained in the ORF file which is located in the reactor control room. 4 1 J l ) i i l Page 5 of 8

t i I FIGURE I AER0 TEST RADIOGRAPHY AND RESEARCH REACTOR (ARRR) P.RO.C _E DU_R.E.A.PP..ROVA.k EH..E.ET _6 .e SECTION I TITLE f DATE ISSUED Written by ..W...eeg...... Supervisor Approval .e.........e... RSC Approval ..........e RSO Approval i es..e e..me..ee (as required) t Ch e e l.no.al fnd R.ev.i.w t t .e .e R e.v.ifwe.d 5% Ch n9e #. DIlt .e! e..W.6..m.m.o......me.mememe.e...eeeeee.........me.e.e.eeeee.eem..e e.......e...e....e..e.....W......me.........Weg.e......... ...ee..e _.ee._e_____ .e .e.__e.e.6.me__me........ .........e ( _m._e__.__e.....__..___e..e _____.6ee.......__mee_..............

6. E.

6.. M e m.

6 m e... e e s e e..e.. e m.m.e m. e.. m e m e..e.. m.. m e.. e.... e.. e. M memme.6e..e..emeem m.em..mee......mee.e.e ee...m.memem.m..me..eem mW...e..e.ee.e..e.eeee...m..ee.g e..m..... 6 WW.e.66..S mmeme. 66e. ? .me-me.em.ee.ee. nee eem.m.eeem.o....ee-mee..e.eem m.em.me.em ee.eem W i ....e. .....e.......e...e...........e.....e.e.e-.6.e.ee......e..... j -e......o...e- .....e.ee....e.-6.......e.................m..e...... 1 Page 6 of 8 PCN 1 1 J. i

~ -~ F FIGURE II AER0 TEST RADIOGRAPHY AND RESEARCH REACTOR (ARRR) P__RO_C E DU__R_E _C H__A NG_ E N.OT.I _C E _( P_C N__) SECTION: PCN #: DATE : PERMANENT CHANGE TEMPORARY CHANGE ogsgRIPI1ON Q{ {HANGE .R.E A.S O.N..F O..R _C H__A N_G _E ' _s

Qualified Individual Approval.. __________
Senior Operator Approvat.________________
- Supervisor Approval.. ______________

Date_________________. l

- RSC Approval....__. __ __..........

Date... ____________......... ______

Required only for temporary change
- Not required for temporary change in sccordance with TS 12.2.2 Page 7 of 8 PCN 1 i

i j

[ s FIGURE III AER0 TEST RADIOGRAPHY AND RESEARCH RE' ACTOR (ARRR)' PROCEDURE _ APPROVAL SHEET memememme mememem e-mee 4 SECTION II TITLE

OPERATIllG PROCEDURES DATE ISSUED 5 March 1982 Written by (original signed by)

/J.eHASKINS/_ e L Supervisor Approval (original signed by) /J. HASKINS/ e e e RSC Approval (original signed by) /H. MONTG0MERY/ e RSO Approval,(original signed by) eeememeeme_Meme (as required) Chan d R vi w emee9el an eteete e mee Revi mepetwed be% Ch Deilt meln91 e ee e MeSemeeWeeSmWeeeeemmemmeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemmeseem megememememegemememememememememememegememmemmeeeeeeeeeeeeeeeeeeeeeg mee G We We seemem eGe m em m em e mee ge mm emmeme m e m e ge me memm emmemm e mmem ememem e meeeeeeeeeeeeeeeeeeeegemmememegemegemeWWWeeeeeeeeeeeeeeeeeemmememme

e. S e e e e. n e e.e e m - m e em... e m.... e.. m. m e m.. m e m.. m e m..e m. e.. e. e.. e ee. e.e eMememememememememmeeeeeeeeeeeeeeeeeeeeeeMeeWeeeeeeeeeeeemmeeeeemme ememmeemeWememememmemememmemememmemmemmeeeeeeeeeeeeeeememenemmemeem egememeememememepemeemmeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemmeeeeeeegem eme ee eeeeeeeeeee e eeee em m emee eeeeeeememmemmeeeeeeeeee e eee eee e e eemmm e meseegememememememesmemmemmememememepeeeeeeeeeeeememmememegemeemmee PCN 1 Page 8 of 8 P

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