ML20207A666

Exam Rept 50-288/OL-86-01 on 860520-22.Exam Results:Five of Six Reactor Operator Candidates Passed Written Exam & Five of Six Reactor Operator Candidates Passed Oral Exam

ML20207A666
Person / Time
Site:	Reed College
Issue date:	06/26/1986
From:	Apley W, Elin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
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ML20207A655	List: ML20207A653 ML20207A666
References
50-288-OL-86-01, 50-288-OL-86-1, NUDOCS 8607160048
Download: ML20207A666 (50)

Text

h U.S. NUCLEAR REGULATORY COMMISSION REGION V Report No. 50-288/oL-86-01 License No. R-ll2 Docket No. 50-288 Licensee: Reed College Portland. Oregon 97202 Facility Name: Reed Reactor Facility Examination Administered At Reed College, Portland, Oregon Examinations Conducted: May 20-22, 1986 e%n Chief Examiner: Walter J. Apl'ey c, /g /40 Dhte'

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Approved By: J. . Elin, hief O erations Section Ddte Examination Summary '

Examination administered on May 20-22, 1986. Written examinations were  !

administered to six reactor operator candidates on May 20, 1986. Oral I examinations were administered to four reactor operator candidates on May 21, 1986, and two reactor operator candidates on May 22, 1986.

Results: One reactor operator candidate failed the written examination and one reactor operator failed the oral examination.

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Report Details

1. Examiners W. J. Apley, PNL (Chief Examiner)

L. J. Defferding, PNL R. Maines, NRC (to certify LJ Defferding on 5/21/86)

2. Examination Review Meeting At the conclusion of the written examination, the examiners met with Michael Kay and Alana Boland to review the examination and answer key.

No questions were deleted. Some minor word changes were made in the answer key to clarify the expected responses. The facility reviewers were requested to provide comments with references to the NRC Regional Office within five days. Several major changes to the key were made due to out-of-date facility information. The summary of facility comments and their resolution is attached to this report.

3. Exit Meetina

, An exit meeting was held on May 22, 1986 following the last oral examination (M. Kay and W. Apley). No generic weaknesses were identified; the only item discussed was the need for Reed College to update training and SAR material prior to the next exam. Also the facility was again told that they had 5 days to get their comments in to the regional office regarding the RO written exam.

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Resolution of Facility Comments Reactor Operator Examination OVESTION A.04

" Rotation" must mean to a different core grid plate location; not rotation about the vertical axis of the individual fuel element.

i Resolution:

The examiner sees No reason to change the key.

QUESTION A.06 0.4% Ak/k (or $0.53). The % is missing in the key and $0.53 is the equivalent worth in those units.

Resolution:

Answer key modified.

QUESTION A.08b "to correct for the prompt negative temperature coefficient" is an equivalent i answer.

Resolutions  !

Answer key modified. l OVESTION B.02 i IntheTRIGAMARKIREACTORMECHANICALMAINTENANCEANDOPERATINGMANUAL(for Reed College, Portland, Oregon) GA-8605, Section 3.6 describes the " Control '

Rod Guide Tubes" to be installed in the proper locations in the grid plate where the control rods will be located. Another correct response is that the holes in the bottom grid plate are too small for a control rod to fall through the core. The main purpose of the control rod guide tubes is to keep the path vertical at all times. ,

Resolution:

Answer key modified to give full credit for " guide tubos" and "small holes."

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QUESTION B.04 The question is not correctly stated for RRF, and the answer given is not consistent with the question asked. The Reactor Bay is the entire confinement area. The three answers given are correct for the Reactor Bay being the confinement area.

Resolution:

The examiner sees no need to change the key; the question is clear as to what area is specified.

QUESTION B.05b The question is not dependent on whether or not the reactor is operating.

The answer to "How can a leak in the heat exchanger be detected?" is the same at all times for RRF. The pool level will increase eventually tripping the pool level alarm (buzzer in the control room, red light in the exit corridor, and red light on the roof of the Chemistry Building). Our Tech. Specs, Administrative Procedures, and Standard Operating Procedures all require that the pressure at the outlet of the secondary basket filter be greater than the inlet pressure to the primary filter; there is no radiation monitor on the secondary system; the pool is not radioactive to the extent a heat exchanger leak could be detected by any monitor on the secondary side; and the RRF SAR Section 5.2.6 makes no mention of radiation detectors in the water system.

Resolution:

Answer key modified to give full credit for pool level increasing.

QUESTION B.06 In training the phrases " breaks up the thermal column," or " disturbs the thermal column" are used to describe the action of the water directed across the core by the diffuser nozzle.

I Resolution:

Answer key modified.

QUESTION B.09 Also, the pool outlet ploe terminates 18 inches below the normal pool level to limit pumping and sipioning even if the hole is clogged and the primary pump continues to operate.

Resolution:

Answer key modified.

QUESTION C.02 i

There are 4 control rod drive indicator lights on the control censole:

White Magnet or Motor Down Red Magnet or Motor Up Blue Continuity (magnet in contact with armature or rod)

Yellow Magnets Energized (magnet power on)

The illuminated switches are labeled:

Down i

Up Cont /On The details of the system are given in the TRIGA MARK I REACTOR INSTRUMENTATION MAINTENANCE MANUAL for Reed College, Portland, Oregon, GA-8533, Section 1.2.1 Control-Rod Drive Switches and Circuits.

Resolution:

Answer key modified.

QUESTION C.10 Trainingandthestartupprocedure(SOP 01) indicate"twosquares"ofthe console chart which is 5 minutes to reach equilibrium. The half 1tfe of the i

longest group of delayed neutrons is 55 seconds. Equilibrium will be obtained l by five minutes.

Resolution:

Answer key modified.

OVESTION D.02 l i

RRF uses different names for the channels in training, daily usage, and in ,

the 50P's. The channels and scrams are:

Linear Power Scram

% Power Scram ,

Period Scram  !

Manual Scram (Loss of) High Voltage Scram (Loss of) (110 VAC or Site or facility) Power (Scram)

Resolution:

Answer key modified.

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QUESTION D.03 .~ .

RRF uses CIC's in an undercompensated circuit so that there is always a -

conservative indication and a reduced probability of being overcompensated.

Resolution The examiner sees no reason to change the key.

! OUESTION D.04 f The reference to S0P 01 is correct, however the paraphrasing is not accurate.

The entire primary water purification system is downstream of the outlet of the primary side of the heat exchanger, and the temperature at all points is that indicated by the " pool inlet" (or "demin") position of the temperature switch on the console.

Resolution:

The examiner sees no reason to change the key.

l OVESTION D.06 l There are only 4 neutron count rate or power indicator channels:

count-rate channel fission chamber l linear channel cic

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Iog channel cic

% power channel fission chamber The % power ion chamber failed many years ago and was replaced with a fission chamber.

Resolution:

Answer key modified.

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00ESTION E.05 i

Additional portable monitoring equipment is located in three places at RRF: 1

1. The West Wall Shelf of the control room is the primary source, if reachable during an emergency.

2. The Emergency Grab Bag contains portable monitoring equipment, s 3. The ESC (Director's Office in the Chem Building) contains portable monitoring equipment.

The order given is the hierarchy of where to go for such equipment.

l l Resolution:

l l Answer key modified to given 1/2 credit for answers 1 and 2.

OVESTION E.07b The evacuation alarm in the control room is located on the North wall just to the right of the right-hand panel of the reactor control console.

Resolution l Answer key modified.

QUESTION F.02 The 50P set point for the period scram is greater than 3 seconds. The current l set point is approximately 4.3 seconds as tested prior to each startup.

Resolution:

Answer key modified.

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I OUESTION F.05 l

1. "Two persons must be present within the Reactor Facility whenever the reactor is not shutdown...", which is taken to mean the controlled access area.

2. "A Senior Reactor Operator must be present in the Reactor Facility (or  ;

tha adjoining Chemistry Building) and the operator must know the l whereabouts of this individual prior to beginning operation." '

! Reed Reactor Facility Administrative Procedures Section 3.1.4 i Resolutions c ,

Answer key modified.

l QUESTION F.07 This question'is really a two-part question

1. Who must give permission before the reactor can be restored (taken to mean restarted and taken to previous level to continue operations) after an inadvertent scram?. An SRO (SOP 8.3 only refers to an inadvertent scram). ,

2. Who must give permission before the reactor can be restored af ter an ,

unexplained scram? "In case of an ' unexplained' scram, the committee will review the case,and determine whether the reactor will be restarted and the procedure for startup." RRF Administrative Procedures " Reactor Operstions Committee" (item number 4) page 7, and S0P 8.4. "SR0" is not the correct response for an unexplained scram.

Resolution The examiner seen no reason to change the key.

QUESTION G.Ola The facility has two usual storage areas referred to as 1) the storage cave (located in the mechanical room), and 2) the lead cave (or lead cage as on the startup checklist) located in the Reactor Bay. For radioactive experiments there are two more acceptable areas, the storage racks in the pool, and the storage pita in the floor of the reactor bay. The Administrative Proceduresi also give the catchall " properly shielded area roped off and labeled."

Resolution:

Answer key modified.

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QUESTION C.05c The current setpoint of the GSit is 118 cpm from the latest calibration with Ar-41.

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! Resolutions j i

l Answer key modified. l l l i

OUESTION C.08- )

1 During fuel iaspection the limit is no higher than the entrance to the j fuel inspection tool. l l

l Resolution: .

Answer key modified. '

QUESTION C.09, An equivalent description ist .Into the facility stack prior to the GSM sampling tube.

Resolution:

Answer key modified. -

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1-O U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION 6-J c -S q 6bded W Facility: Reed College Reactor Type: Test Yb rAnf-ba'4 jk/ggth & Date Administered: May 20, 1986

/e b9 N./ Examiner: LJ Defferding, WJ Apley f & //j'k' Rsn

//< 44 ., c. Candidate: Answer Key - M Astens 3/, A/ 4, g,g INSTRUCTIONS TO CANDIDATE:

Use seperate paper for the answers. Write answers on one side only.

Staple question sheet on top of the answer sheets. Points for each question are indicated in parenthesis after the question. The passing grade reqJires at least 70% in each category. Examination papers will be picked up six (6) hours after the examination starts.

Category  % of Candidate's  % of Value Total Score Cat. Value Category 14 14 Principles of Reactor A.

Operation v 14.5 14.5 .

B. Features of Facility Design 15 15 _

C. General Operating 7 Characteristics 14 14 D. Instruments and Controls 14.5 14.5 E. Safety and Emergency Systems 14 1 F. Standard & Emergency Operating Procedures 14 14 G. Radiation Control and Safety 1

TOTALS Final Grade  %

All work done on this examination is my own, I have neither given nor received aid.

Candidate's Signature

e Page 1 Reed College May 20, 1986 Points Available A. PRINCIPLES OF REACTOR OPERATION (14.0)

QUESTION A.01 Consider the " doppler broadening" effect that takes place in the fuel of the Triga Reactor.

a. Describe the phenomena of doppler broadening. (1.0)

b. Does this phenomena in the Triga Reactor lead to a positive or negative temperature coefficient and is the temperature coefficient considered a " slow (delayed)" or " fast (prompt)"

coefficient? (1.0)

ANSWER A.01 l

a. An increase in the fuel temperature causes a broadening of the neutron absorption peaks (the resonance peaks); on a graph of neutron absorption cross-section as a function of energy the cross-section peaks widening (and become lower in magnitude). The broadening is due to the increase vibrational energy as the temperature increases. The peaks in the absorption cross-sections of U-235 and U-238 are the primary contributors to the effect in the Triga Reactor.

[+1.0]

b. The fuel temperature coefficient is a negative temperature coefficient [+0.5] and is considered a prompt coefficient.

[+0.5]

REFERENCE A.01

1. Reed: Reed training document Technical Education Research Center-Southwest, " Nuclear Technology," pp. 12-7-8 to 12-1-9.

-Section A Continued on Next Page-L.

1 Page 2 Reed College May 20, 1986 Points Available OUESTION A.02 Numerically estimate the reactivity change in cents which occurs ingthe Triga reactor core if the fuel temperature is raised 35 C. (1.0)

ANSWER A.02 alpha (f) approx. equal to 10-4/C [+0.3]

delta K/k = (10-4)(35) [+0.3]

$ = 3.5 x 10-3/0.0075 [+0.4]

= 47 cents REFERENCE A.02 4

1. Reed: Reed Reactor Facility Training Manual, p. 12-7-12.

OVESTION A.03 A fissionable sample is to be irradiated. In which irradiation location would it have the greatest reactivity? h? (1.5)

ANSWER A.03 It would be worth more if inserted into the central thimble because of the higher flux in the center of the core. [+1.5]

REFERENCE A.03

1. Reed: Training Manual, p. 4-8.

-Section A Continued on Next Page-

Page 3 Reed College May 20, 1986 Points Available OUESTION A.04 Answer TRUE or FALSE.

It is expected that rotation of fuel elements in the core would not effect control rod worth. (0.5)

ANSWER A.04 FALSE [+0.5]

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REFERENCE A.04

1. Reed: Training Manual, p. 12-6-23.

QUESTION A.05 If delayed neutron population is only about 0.6% of the total neutron population in the core, why do the delayed neutrons have such a large effect on the operator's ability to control the plant? (2.0)

ANSWER A.05 Delayed neutrons give the reactor more manageable periods because ,

the delayed neutron fraction beta = 0.6% = 0.006 increases the l period (T) a substantial amount, because the weighted mean lifetime is greatly increased when beta is added in. [+2.0]

i REFERENCE A.05

1. Reed: Training Manual, p. 5-14.

-Section A Continued on Next Page-

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Page 4 Reed College May 20, 1986 Points Available QUESTION A.06 What is the allowable minimum shutdown margin as per the j TeEnical specifications? (1.0)

ANSWER A.06 op- [

\

l 0.4, delta k/k 3[+1.0]

N REFERENCE A.06

1. Reed: TRIGA Technical Specifications.

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-Section A Continued on Next Page-f

Page 5 Reed College May 20, 1986 Points Available QUESTION A.07

a. What three (3) riaterials serve as moderators for the Reed TRIGA reactor? (1.5)

b. In theory what are two (2) of the three (3) most important properties Tt a good moderator? (1.0)

ANSWER A.07 I a. 1. water [+0.5]

2. graphite [+0.5]

3. zirconium hydride [+0.5] -

b. 1. high elastic scattering cross section

2. neutron capture cross section low

3. low atomic mass 3

Any two (2) [+0.5] each, +1.0 maximum REFERENCE A.07

1. Reed: Training Manual, p. 12-6-17.

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-Section A Continued on Next Page-I

l Page 6 Reed College  !

May 20, 1986 Points 1 Available QUESTION A.08 l

a. At what power level is the estimated critical rod height to be corrected? (1.0)

b. WM is this correction necessary? (1.0)

ANSWER A.08

a. 500 watts [+1.0]

b. To correct for fuel temperature [+1.0]

G.e. prompt utgsket itmptMIMS REFERENCE A.08 g.g gg  !

1. Reed: SOP-4.0.

QUESTION A.09 Answer the following TRUE or FALSE.

After a reactor shutdown, decay heat rate and count rate will exactly track down with each other. (1.0)

ANSWER A.09 FALSE [+1.0] (decay will decrease at a slower rate due to fissionproducts).

REFERENCE A.09

1. Reed: Training Manual, p. 3-21.

-Section A Continued on Next Page-

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Page 7 Reed College '

May 20, 1986 Points Available OVESTION A.10 On a constant reactor period, which will take longer 1

(a.) to go from 10% to 20% power? )

(b.) to go from 20% to 35% power? (0.5)  !

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ANSWER A.10 (a.) [+0.5] (changes power by a factor of two, while the other changes power by only a factor of 1.75). -

REFERENCE A.10

1. Reed: Training Manual.

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-End of Section A-l l

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-Section A Continued op Next Page- '

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Page 8 Reed College May 20, 1986 Points Available B. FEATURES OF FACILITY DESIGN (14.5)

QUESTION B.01 Because of the relatively high concentration of U-238, what fissionable isotope is produced during reactor operation? (1.0)

ANSWER B.01 Pu-239 [+1.0]

REFERENCE B.01

1. Reed: Training Manual, p. 3-7.

QUESTION B.02 What design feature ensures that control rods will not drop out of the bottom of the core? (1.0)

ANSWER B.02 i Coa

~ -t +<pl

. : sydde 4mbes in ct:lled sw( ;-f

'- th_ !:r d p!:t:vid plak helt 64cthe t: prevent l i

rods from dropping through. [+1.0] '

REFERENCE B.02

1. TRIGA Instruction Manual, G A - 8( 06i Secfioed 3.4

-Section B Continued on Next Page-

Page 9 Reed College May 20, 1986 Points Available OVESTION B.03 What design features provide for neutron reflection in the radial and the axial direction in your reactor? (2.0)

ANSWER B.03 The end sections of the fuel rods are made of graphite, this provides axial reflection. Radial reflection is provided by a graphite jacket surrounding the core. [+2.0]

REFERENCE B.03

1. Reed: SAR, p. 5-3.

QUESTION B.04 What three (3) design features ensure that the reactor room, laboratory, and counting room act as a confinement area for contaminated air during operations? (1.5)

ANSWER B.04

1. All windows are fixed glass. [+0.5]

2. The doors have weather stripping. [+0.5]

3. The ventilation system is independent of the system for the radiochemistry lab. [+0.5]  ;

i REFERENCE B.04

1. Reed: SAR, p. 4-5.

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-Section B Continued on Next Page-

. I Page 10 Reed College I May 20, 1986 l Points i Available  !

QUESTION B.05

a. Explain how the pool water is prevented from mixing with )

the secondary water during reactor operation if a leak j should occur in the heat exchanger. (1.0) i

b. When the reactor is not operating, how can a leak in the  !

heat exchanger be detected? (1.0)

ANSWER B.05 l

a. Secondary side is maintained at higher pressure during l operation. [+1.0]

b. -*d-e- --i r d ' . ^. : . . ,,,v ii i w 1.

[+1.0] l pl Iewel ik ccean (Pesssst26 6vocE 'N08 MNd) '

REFERENCE B.05

1. Reed: SAR 5.2.6.

l QUESTION B.06 A portion of the oxygen in the pool water is activated to nitrogen-16 by a fast neutron reaction as the water passes upward through the core. What design feature helps reduce the dose rate at the top of the pool from N-167 (2.0)

ANSWER B.06 Downward slanted discharge of water and swirling motion into the tank through a diffuser nozzle. [+2.0]

A

(,kveaks up %e< mal colum4 REFERENCF B.06

1. Reed: SAR, p. 7-8. l

-Section B Continued on Next Page-

Page 11 Reed College May 20, 1986 <

Points Available QUESTION B.07 What two (2) design features inhibit the transfer of argon from the rotary specimen rack to the reactor room? (1.0)

ANSWER B.07 The access tube is long and slender, and there is a cover plate on the tube. [+1.0]

REFERENCE B.07

1. Reed: SAR, p. 7-7.

QUESTION B.08 Explain how a design feature of the control rod mechanism reduces the impact when the control rod reaches its full in position during a SCRAM 7 (2.0)

ANSWER B.08 The piston on the connecting rod, portion of the control rod, contains the 2-inch long dashpot portion of the barrel assembly where the water is displaced by the piston is forced out through 1 small holes thereby reduces the control rod speed. [+2.0] l REFERENCE B.08

1. Reed: SAR, p. 5-11.

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-Section B Continued on Next Page-

Page 12 Reed College May 20, 1986 Points Available QUESTION B.09 What safety feature is used to prevent pumping or siphoning alTthe water out of the reactor tank through the inlet and outlet water liiies? (1.0)

ANSWER B.09 A 1/2 inch diameter hole is drilled into the tank inlet and outlet water lines, one foot below the normal water level.,[+1.0]

M**pp.'pa 4 e< was4n It" lie toa womanpd lean .

REFERENCE B.09 F, MXOWC,50cTi00)

1. Reed: SAR, p. 7-3.

Chf d l$

QUESTION B.10

% [M The reactor core is cooled by (select one):

(a.) Natural convection (b.) Forced convection (c.) Radiation (d.) Natural conduction ANSWER B.10 l

(a.) natural convection [+1.0]  ;

REFERENCE B.10

1. Reed: Safety Analysis Report, p. 5-8.

-End of Section B-l l

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- --.- , , _ _ _ - -,,,.m.,.

Page 13 Reed College May 20, 1986 Points Available C. GENERAL OPERATING CHARACTERISTICS (15.0)

OUESTION C.01 List the three (3) locations where the reactor primary water temperatures are measured. (1.0)

ANSWER C.01

1. bulk tank temp

2. cooling in ",

3. cooling out

[+1.0]

REFERENCE C.01

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1. Reed: SAR, p. 5-12.

QUESTION C.02 What three (3) control rod drive mechanism indications are shown as lights on the control console? (1.5)

ANSWER C.02

1. magnet up

2. magnet down

3. magnet in contact with armature.

[+0.5] each Abe C.ted& &c -

Magueh SNWay*yd maw (mum t.T p REFERENCE C.02

1. Reed: SAR, p. 5-12.

-Section C Continued on Next Page-

, -.,.,c,. n , , . - - - -

9 Page 14 Reed College May 20, 1986 Points Available QUESTION C.03 The Reed reactor is critical at two (2) watt power and is being increased on a constant 15 sec period. How long (in seconds) will it take for the power to reach the maximum limit for manual operation? (Show calculations and list assumptions.) (2.5)

ANSWER C.03 Maximum manual operation [+0.5] 90% or 225 kW l t

P(final)/P(initial) = e / tau [+1.0] tau = 15 sec i

manual operation 90% or 225 kW l

in 250 x 0.00 x 1000/2 = t/15 t = 174 sec. [+1.0] )

REFERENCE C.03

1. Reed: SOP 4.3.

QUESTION C.04 How can the central thimble be used to create a well-collimated beam of neutrons? (2.0) l l

ANSWER C.03 There is a 1-1/2 inch OD aluminum tube that fits through the center hole of the top and bottom grid plates. Holes in the ,

tube ensure that it is normally filled with water; however, a

' special cap may be attached to the top end, compressed air applied, and the water column removed to obtain a well-collimated beam of neutrons. [+2.0]

REFERENCE C.03

1. Reed: SAR, p. 5-7.

-Section C Continued on Next Page-

_- -- .. .. . = _ _ . ._ ..- _ _ _ _ __

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Page 15 Reed College May 20, 1986 1 4

Points Available i QUESTION C.05

a. How long does it take to raise the safety rod to its full extent? (0.5)

b. When the mode switch is in automatic, with approximately what period are power changes made? (0.5)

I ANSWER C.05 l

a. 45 seconds [+0.5]

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b. about 20 seconds [+0.5]

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! REFERENCE C.05

1. Reed: Safety Analysis Report, pp. 5-9 through 5-11.

2. Reed: S0P 05.

QUESTION C.06

? Answer the following TRUE or FALSE.

If a rabbit sample when inserted had no noticeable reactivity I effect, then that ensures that the sample when returned to the terminal area will have no unreasonable amount of radioactivity. (1.0) i

! ANSWER C.06 I

FALSE. [+1.0]

REFERENCE C.06 1

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1. Reed: SOP 51.5,6. 4 I

-Section C Continued on Next Page-1

r. _ . , - . . - - - - ----,w ,---,_w-a . . - - - - , , --- .-- -

Page 16 Reed College May 20, 1986 Points Available QUESTION C.07 If a line supplying nitrogen to an experiment in the core were to break, causing bubble formation within the core lattice, i the core reactivity would: (Selectone.) (1.0)

(a.) increase (b.) decrease (c.) remain unchanged j ANSWER C.07 (b.) [+1.0]

REFERENCE C.07 1

1. Reed: Training Manual, p. 12-7-13.

QUESTION C.08 Answer TRUE or FALSE.

The equilibrium reactivity of Xe-135 at 10 kW is 50% of the reactivity associated with the equilibrium reactivity of Xe-135 at 20 ."' ,*_00^ kWF. (0.5)

ANSWER C.08 FALSE. [+0.5]

REFERENCE C.08

1. Reed: Training Manual, 12-7-25.

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-Section C Continued on Next Page-

Page 17 Reed College May 20, 1986 Points Available 00ESTION C.09 After a long period of full power operation a scram occurs.

What would you expect to see while monitoring tne nuclear instrumentation, both immediately and for the following five (5) minutes? Explain. (2.0) i 1

ANSWER C 09 Prompt drop followed by an 80 second negative period. [+2.0]

REFERENCE C.09

1. Reed: Training Manual, p. 5-24.

QUESTION C.10 The startup procedure directs that a calculation of core excess be conducted after allowing " sufficient time" at low power for stabilization. Why do you have to wait for stabilization? (1.5)

, ANSWER C.10 Because it takes minute 6for delayed neutrons to come into equilibrium. This necessitates making small control rod adjustments to ensure that reactor power has been leveled. [+1.5]

REFERENCE C.10

1. Reed: Training Manual, p. 5-16.

2. Reed: S0P 3. ,

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-Section C Continued on Next Page-

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l Points l Available 1

QUESTION C.11 What is the maximum allowable core excess including experiments? (1.0)

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1 ANSWER C.11 l

j $3.00 [+1.0] or 2.25% delta k/k. j 1 1 j l REFERENCE C.11  ;

1. Reed: Technical Specifications, E.2.

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-End of Section C-1 1

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Page 19 [ DRAFT] Reed College May 20, 1986 Points Available D. INSTRUMENTS AND CONTROLS (14.0) 1 OVESTION D.01 Give two (2) reasons why interlocks are provided on the rod control system. (2.0) 1 ANSWER D.01 Interlocks are provided to:

1. Assure minimum source strength before control rods can be withdrawn. [+1.0]

2. Prevent withdrawal of two control rods simultaneously on manual control . [+1.0]

REFERENCE D.01

1. Reed: SAR 5.3.4, p. 5-16.

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-Section D Continued on Next Page-f

Page 20 [ DRAFT] Reed College May 20, 1986 Points Available 1

OVESTION D.02 List six (6) channels, controls, or power failures that scram the reactor. (3.0)

ANSWER D.02

1. Power level channel, compensated ion chamber, micromicroammeter. -INur pemne sc. cam

2. Power level channel, ion chamber, adjustable by operator, from 20 to 110% of full power. - 9s p ee sc. yam

3. Reactor period channel, adjustable period scram between infinity and +3 sec.

4. Manual. l

5. Ion-chamber power supply failure. ( Less si Mi$ k Ve%')

6. Console power circuit failure. (%eu of Pedet)

[+0.5] each REFERENCE D.02 l

1. Reed: SAR 5.3.4, p. 5-16. l

-Section D Continued on Next Page-

Page 21 [ DRAFT] Reed College May 20, 1986 Points Available OUESTION D.03 How is gamma radiation compensated for in a compensated ionchamber(CIC)? (2.0)

ANSWER D.03 Neutron count rate is sensed in the outer can by interaction with boron paint. Gamma radiation is sensed in both the outer can and inner can. The lack of boron paint in the inner can causes only gamma interactions to take place. A compensating voltage is applied to the inner can to exactl being sensed in the outer can. [+2.0]y balance the gamma current REFERENCE D.03 I

1. TRIGA Manual, p. 2-39 and 2-40.

QUESTION D.04 Describe in detail how to read the primary conductivity meter. (2.0)

ANSWER D.04 i To read the primary conductivity meter one must first turn it on and give it time to warm up (about 15 seconds). The temperature dial is then set to the temperature of the inlet water and throttle switch to " inlet" as well. The conductivit dial is turned back and forth until the dark area ("V"-shaped)y is widest. The conductivity is read directly off of the dial.

The same procedure follows for the outlet, only the outlet temperature must be set and the throttle switch turned to

" outlet." After reading the outlet conductivity, the meter is turned off. [+2.0]

REFERENCE D.04

1. Reed: S0P 01.

4

-Section D Continued on Next Page-

Page 22 [ DRAFT] Reed College May 20, 1986 Points Available

. QUESTION D.05 When the rabbit is inserted into the core, the reactor operator is supposed to (according to SOP 51.6) monitor closely for an unreasonable amount of reactivity change.

a. What primary indication (s) should the operator be observing in the steady state mode? (1.0)

b. What primary indication should the operator be observing in the automatic mode? (1.0)

c. What would constitute an " unreasonable" amount of reactivity

• change? (1.0) l ANSWER D.05 i

a. Steady state: linear recorder and period meter. [+1.0]

b. Automatic: reg rod position. [+1.0]

c. + or - 10% on the linear recorder for steady state; a change

! of + cr - 100 on the reg rod position reading. [+1.0]

REFERENCE D.05 i

1. Reed: S0P 51.

l

-Section D Continued on Next Page-

Page 23 [ DRAFT] Reed College May 20, 1986 l

l Points Available QUESTION D.06 Name the four (4) ranges of neutrons count rate (power) l indication. For each indicator state what type of detector chamber provides its input. (2.0)

ANSWER D.06

1. source range (fission counter) - fission chamber

2. log n recorder - compensated ion chamber

3. linear recorder - compensated ion chamber i 4. percent power hii3 - r..:;.;10;n A;;..$

. . , ah Me.-

c ....

5.  ??:' ;::::: r :: ; ..xt:f ':: :P ":7

[+0.5] each REFERENCE D.06

1. Reed: SAR, Figure 5-7.

-End of Section D-

Page 24 Reed College May 20, 1986 l Points Available E. SAFETY AND EMERGENCY SYSTEMS (14.5)

QUESTION E.01 According to technical specifications l a. Corrective action shall be taken if during operation the poolwater is less than feet above the top grid plate. (1.0)

b. The reactor shall be shutdown if the poolwater temperature exceeds degrees F. (0,5) .

ANSWER E.01

a. 16 feet [+1.0]

b. 120 deg F. [+0.5]

REFERENCE E.01

1. Reed: Technical Specifications, D.1 OUESTION E.02 Whattwo(2)conditionswillautomaticallysettheventilation systems into isolation? (2.0)

ANSWER E.02

1. The activation of the CAM alarm [+1.0]

t

2. GSM alarm [+1.0]

REFERENCE E.02

1. Reed: Safety Analysis Report, p. 4-5.

l

-Section E Continued on Next Page-1 I

Page 25 Reed College May 20, 1986 Points Available OUESTION E.03 Technical specifications require that three (3) safety system SCRAMS be operable for reactor operation. Name all three (3). (1.5)

ANSWER E.03 a

1. manual [+0.5]

2. linear [+0.5]

percent power [+0.5]

3.

REFERENCE E.03

1. Reed: Technical Specifications, p. 9.

, QUESTION E.04 Technical specifications require that reactor instrumentation channels and safety circuits be verified to be operable at

least once every day the reactor is operated. What must be done if reactor operation extends beyond one day? (2.0) i ANSWER E.04 The safety circuits that cannot be tested without interupting the run are checked before running. Those that can be tested during operation are tested while running. [+2.0]

REFERENCE E.04

1. Reed: Technical Specifications, p. 3.

-Section E Continued on Next Page-

Page 26 Reed College May 20, 1986 Points Available QUESTION E.05

Where is additional portable monitoring equipment located? (1.0)

ANSWER E.05 In the Emergency support center (Directors Office Chem Bldg.).

[+1.0]

(+.s ;$ A t y

• West Ah *e Grab bay REFERENCE E.05

1. Emergency Implementation Procedures, 2-2.

)

QUESTION E.06 List the three (3) categories of emergency that are considered l feasible at the Reed reactor facility.

(1.5) 1 ANSWER E.06

1. nonreactor safety related event [+0.5]

2. alert [+0.5]

3. unusual event [+0.5]

! REFERENCE E.06 4 I

1. Reed: Reactor Facility Emergency Plan. i l

1

-Section E Continued on Next Page-l i

i

=

l l

1*

l Page 27 Reed College May 20, 1986 l

l Points Available OVESTION E.07

a. How many buttons are there to manually activate the evacuation alarm? (1.0)

b. Where are they located? (1.0)

ANSWER E.07

a. 2 [+1.0]

b. One each in Reactor Room and on control console. [+1.0]

ri REFERENCE E.07 (schgd y;4)ght WAt

1. Reed: Emergency Plan, p. 2.

QUESTION E.08 According to technical specifications what three (3) conditions must be met for the reactor to be considered shutdown? (3.0)

ANSWER E.08

1. Console key switch off, key in possession of licensed operator.

2. Reactor subcritical by a margin greater than 0.7 percent delta k/k, cold, without xenon.

3. No work is being done on the core or control mechanisms of the reactor.

[+1.0] each REFERENCE E.08

1. Reed: Technical Specifications, p. 1.

i

-End of Section E-l

Page 28 Reed College May 20, 1986 Points Available F. STANDARD AND EMERGENCY OPERATING PROCEDURES (14.0)

QUESTION F.01 In case of civil unrest, according to the emergency plan what two (2) specific actions are you required to do? (1.0)

ANSWER F.01

1. Shutdown the reactor. [+0.5]

2. Deadbolt lock the four (4) facility doors. [+0.5]

REFERENCE F.01

1. Reed: Emergency Plan.

QUESTION F.02 What is the SCRAM setpoint for the period channel? (0.5)

ANSWER F.02 qL.3 seconds. [+0.5]

(

REFERENCE F.02

1. Reed

Technical Specifications, p. 3.

-Section F Continued on Next Page-

Page 29 Reed College May 20, 1986 Points Available QUESTION F.03 Select from the items below the major concern regarding the irradiation of samples that are fissionable. (Selectone.) (1.0)

A (a.) Any amount of fissionable samples will insert > $1.00 of positive reactivity.

(b.) Irradiation of fissionabl.e materials may cause production (

of I-131 or Sr-90. ~

(c.) Fissionable materials are explosive.

(d.) Fissionable materials may melt.

ANSWER F.03 [

(b.) [+1.0] "

REFERENCE F.03

1. Reed: Training Manual, Chapter Reactor Physics.

QUESTION F.04 Why is core excess calculated at such a low power level during startup (SOP, Section 4.1.2)? (1.0)

ANSWER F.04 So that no reactivity effects caused by temperature change will interfere with the determination of core excess. [+1.0]

REFERENCE F.04

1. Reed: S0P 3.

-Section F Continued on Next Page-s.

. l Page 30 Reed College May 20, 1986 Points Available QUESTION F.05 According to the Administrative Procedures, what are the two (2) minimum staffing requirements for operating the Reed reactor? (2.0)

ANSWER F.05

1. Two persons within the reactor b1dg. one of which must be an NRC licensed operator. [+1.0]

2. An SR0 must be present in the Reactor Facility, and the R0 knows his whereabouts. [+1.0]

REFERENCE F.05

1. Reed: Administrative Procedures, 3.1.4.

QUESTION F.06 Give a short, one paragraph description of how a reactor power calibration is accomplished. (2.0)

ANSWER F.06 Reactor power is established at a constant high level and the thermal power is calculated by conducting a heat balance on the reactor pool. Ion chambers are compared and heights are adjusted to read the calculated value. [+2.0]

REFERENCE F.06

1. Reed: S0P 43.5.

-Section F Continued on Next Page-I l

Page 31 Reed College May 20, 1986 Points Available QUESTION F.07 According to S0P 08: SCRAMS, who (position) must give permission before the reactor can be restored after an inadvertent or unexplained scram? (1.0) l ANSWER F.07 An SRO. [+1.0] [54 ukeWLoth Cgoc, s **"#

REFERENCE F.07

1. Reed: S0P 8.3.

QUESTION F.08 The shim and Safety rods have such a high total worth that the worth at the lower end cannot be measured. How is the total worth estimated? (1.5)

ANSWER F.08 By doubling the integrated worth obtained for the exact halfway position on the rod. [+1.5]

REFERENCE F.08

1. Reed: S0P 33.12.

-Section F Continued on Ne c Page-

Page 32 Reed College May 20, 1986 Points Available QUESTION F.09 If an operator wishes to be relieved from console operation, when is the use of a shift change (status) stamp necessary? (1.0)

ANSWER F.09 If operator is gone for more than 5 minutes. [+1.0]

REFERENCE F.09

1. Reed: S0P 10.

QUESTION F.10 During reactor startup:

a. Which rod is withdrawn first? (1.0)

b. When withdrawing the shim rod what three (3) indicators should the operator be monitoring? (1.5)

c. What is the minimum percent of scale at which the linear channel range switch can be operated to shift to the next highest scale? (0.5)

ANSWER F.10

a. Safety [+1.0]

b. 1. period [+0.5]

2.

3. countrate [+0.5) [+0.5]

linear channels

c. 50 percent [+0.5]

REFERENCE F.10

1. Reed: S0P 04.

-End of Section F-

Page 33 Reed College May 20, 1986 i

Points Available G. RADIATION CONTROL SAFETY (14.0)  :

OUESTION G.01 l

a. List the two (2) acceptable storage areas for radioactive experiments. (1.5)

b. How long can any one (1) experiment be stored at the Reactor Facility? (0.5)  ;

ANSWER G.01 , g

a. 1. storage cave'[+0.5]

2. in a properly shielded area [+0.5] roped off and  !

labeled [+0.5]

&~M G me.6f% et

b.

• 1 year (unless it is to be used at some later time) [+0.5] .

REFERENCE G.01

1. Reed: Administrative Procedures, S.1, p. 20.

QUESTION G.02 Answer TRUE or FALSE.

Individuals on Entry list A who do not have a film badge can enter the reactor room if they are accompanied by a person with a film badge. (1.0)

ANSWER G.02 FALSE. [+1.0] They are required to have a pocket dosimeter.

REFERENCE G.02

1. Reed: Administrative Procedures, VI, p. 23.

l

-Section G Continued on Next Page-

Page 34 Reed College May 20, 1986 Points Available QUESTION G.03 What is the maximum dose (mrem) that visitors to the reactor TicT11ty who are under 18 may receive? (1.0)

ANSWER G.03 ,

i 10 mrem [+1.0]

REFERENCE G.03

1. Reed: Administrative Procedures, p. 23.

-Section G Continued on Next Page-

Page 35 Reed College May 20, 1986 Points Available QUESTION G.04 The radiation level due to a known small radioactive deposit in a pipe fitting is 1 rem /hr measured 15 feet away. An operator must operate a valve located 5 feet from the pipe fitting. If

it takes the operator 1 minute to operate the valve, will he receive a radiation dose in excess of 1/10th of the 10 CFR 20 quarterly whole body exposure limit? Show your work and assumptions. (2.5)

ANSWER G.04

1. dose rate (dr) = 1000 mrem /hr, distance (rg) = 15 feet, distance (r2) = 5 feet, time (t) = 1 minute = 1/60 hr 2

2. /r2 x hr/ min [+1.0]

dose / min =dratexrf5 dose / min = 1000 x 15 2 2 x 1/60 dose / min = 150 mrm [+0.5]

the yearly dose limit = 5 rem, quarterly = 1.25 rem, [+1.0]

1/10 of quarterly = 0.125 rem = 125 mrem, so the operator would receive a dose in excess of 1/10 of the quarterly limit for whole body exposure.

REFERENCE G.04

1. Reed: Training Manual, p. 2-2.

l Gw f

-Section G Continued on Next Page-

W Page 36 Reed College May 20, 1986 Points Available OVESTION G.05 Match the monitor (letter) with appropriate alarm setpoint

(number) given below

(2.0)

a. CAM

b. RAM

c. GSM

d. Particulate Stack Monitor

1. 1500 cpm j 2. 100 cpm

3. 218 cpm

4. 10 m/R/hr

5. 2000 cpm

6. 2 mR/hr f

ANSWER G.05 a-5 b-6 c - 3 (Credit hof 1 4lge ggg we gg(p( s H%

d-1

[+0.5] each REFERENCE G.05 1

1. F.eed: Checklists.

-Sect ion G Continued on Next Page-J

- - - , . w ,e m ,w -e- ..-.m, .m_m e,., ,.--,.- c.-w , ----c- .sy- , .

-,y- , . , - - - - - - - , - _.y-, -

-m

Page 37 ?eed College May 20, 1986 Points Available QUESTION G.06 1 S0P 51 states that the real potential hazard of a rabbit irradiation is the possibility of bringing back a rabbit to the operator that is super-hot sample (i.e., too radioactive).

a. Above what dose (in mR/hr) on the ion chamber should the rabbit not be removed from the terminal? (1.0)

b. List three (3) ways the rabbit operator can minimize the l possibility of receiving a high exposure from a hot sample. (1.5) 1 ANSWER G.06

a. 10 mR/hr [+1.0]

b. 1. Calculate activity prior to irradiation.

2. Use portable meter.

3. Time

4. Distance

5. Shielding Any three [+0.5] each REFERENCE G.06

1. Reed: SOP 51.

i

-Section G Continued on Next Page-f

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

Page 38 Reed College May 20, 1986 Points Available 1

OUESTION G.07 What does the acronym ALARA stand for? (1.0)

ANSWER G.07 As low as reasonably achievable. [+1.0]

l 1

REFERENCE G.07

1. TRIGA Training Manual

! QUESTION G.08 When moving an irradiated fuel element, how close to the surface can the element be lifted? (1.0)

ANSWER G.08 gggQ,- g. g Q No higher than the top of the fuel racks'. [+1.0]

REFERENCE G.08

1. Reed: S0P 40.7.

l l

l 1

-Section G Continued on Next Page-r

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

Page 39 Reed College May 20, 1986 ,

Points Available i 00ESTION G.09 To where is the air used by the send / receive station for the pneumatic sample transfer system exhausted? (1.0)

ANSWER G.09 OF INTCik iMillW5 AMPLS N K46t-ceJL S'CE ,E y

It is exhausted into the building exhaust system (for venting Ar) . [+1.0]

i REFERENCE G.09 ,

) 1. Reed: SAR 5-7.

-End of Section G-

-End of Exam-

)

i 1

]

1 1

r i

l I

I

I l

l l

l EQUATION SHEET l

Where mi = m2 (density)1(velocity)i(area)y = (density)2(velocity)2(area)2

) ...... __________ _..___________ ______ ........__________________________.

KE="{2 PE = mgh PEg + KEg+P Y 1 1 = PE +KE 2 2+P Y22 where V = specific volume i

P = Pressure O" p(Tout -Tin) Q = UA (T,y,-Tstm) Q = m(hi-h2 )

P = Po10(SUR)(t) p , p ,t/T SUR = 26.06 T = (B-p)t o T p delta K = (K,ff.1) CRg(1-K,ffi) = CR2 (1-Keff2) CR=S/(1-K,ff)

(1-K,ffg) (1-K,ff) x 100%

SDM =

M = (1-Keff2) K eff decay constant = In (2) , 0.693 A 1=Ae-(.iecayconstant)x(t) t t 1/2 1/2 Water Parameters Miscellaneous Conversions i

I gallon = 8.345 lbs 1 Curie = 3.7 x 10 10 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 1 ft 3= 7.48 gallons I hp = 2.54 x 103 Btu /tr 3 6 Density =62.4lbg/ft 1 MW = 3.41 x 10 Btu /hr, Density = 1 gm/cm 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch 2.54 centimeters 2 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft-lbm/lbf-sec

, _ __ _ - . . - . _ _ . . _. .-._..______ _- ,