ML20141E373

Submits Comments on Few Questions Re Exam Rept 50-027/OL-97-01 Administered on 970414-15

ML20141E373
Person / Time
Site:	Washington State University
Issue date:	04/16/1997
From:	Tripard G WASHINGTON STATE UNIV., PULLMAN, WA
To:	Doyle P NRC
Shared Package
ML20141E344	List: ML20141E358 ML20141E373
References
50-027-OL-97-01, 50-27-OL-97-1, NUDOCS 9705200418
Download: ML20141E373 (32)

Text

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] Washington StateUniversity E Nuclear Ra$abon Center P O Box 641300 Pullman WA 991641300 509 335 8641 Wednesday, April 16,1997 m s n 54433 l

A'ITN: Paul Doyle Mail Stop 0-11 B 20 United States Nuclear Regulatory Commission Washington, D.C. 20555 1

Dear Mr. Doyle:

On behalf of the facility and the examinees Keith Fox and Kent Marley, I would like to thank you for providing the operator exam on April 14 and 15,1997.

Jeny Neidiger (the reactor supervisor), Brian Bunce (Training Coordinator) and I went '

over the exam shortly afterits completion. We would like to make the following comments on a few of the questions:

Section A:  !

l Question 002 This is a good question and should be retained in this exam but if you use it again in the future we suggest that its clarity could be improved by slightly rewording the last sentence to read:

If temperature INCREASES by 9 deg F, how much and in what direction would the control rod have to move in order to maintain constant power during the temperature change.

Question 004 This question is flawed in the context of our reactor because our shutdown margin is defmed as "The core excess reactivity minus the sum of the reactivities of all but the highest worth of the 4 scrammable blades." As it stands, the question does not provide a correct answer.

Had the question said, "The reactor is suberitical by 2.5$" or "The reactor is shut down by 2.55" the meaning of the question would have been clear and the intended answer correct.

Question 005 'Ihis question requires knowing the relative thermal absorbtion cross sections of fourdifferent isotopes. If you had pasted into the exam the little boxes from the Chart of the Nuclides for each of these four isotopes this would have been an excellent question. This question is probably a "gimme" at facilities that use heavy water.

Section B:

l Question 008 Your key shows an arithmetic error. The concet answer is "c".

Question 014 Answers "a" and "b" are both correct depending on whether this is a first rabbit shot of the experiment or the next one in a series.

Section C:

9705200418 970514 PDR ADOCK 05000027 V PDR

Question 002 The conect answers are: b,r,b,b,r In the exit interview it was suggested that you may want to accept "1" or "r" where the answer should be "b" for both-Question 017 Both Nitrogen and Air are used depending on circumstances so both "a" and "C" are Correct.

Question 020 De correct answer is "b". The scenario described in this question presumes '

that the solenoid is energized. Otherwise how can one "deenergize it". One also may presume that the pulsing procedure and withdrawal sec uence was otherwise followed correctly. If that is the case then according to SOP #4.D 1. e, the Cylinder has been withdrawn to the desired height for the pulse before going to the rest of the withdrawal sequence in Appendix A. Deenergizing the solenoid would then cause the pulse rod to drop via gravityinto the core.

Sincy, rely, ,

NM Gerald E. Tnpard Director, Nuclear itadiation Center cc: Keith Fox, Kent Marley, Brian Bunce, Jerry Neidiger 1

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NRC RESOLUTIONS i l Section A l

Question 2: Agree with facility comment, question will be rewritten for next administration.

No change required to answer key Question 4: Agree with facility comment, question deleted from examination.

Question 5: Agree with facility comment, question deleted from examination.

l Section B '

l Question 8: Agree with facility comment, answer key changed to show c as correct answer.

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l Question 14: Agree with facility comment, question changed to show both a and b as correct answers. l l

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l Section C -

l; Question 2: Agree with facility comment, answer key changed to show b, r, b, b, r as correct, with the stipulation that both (b) and logic (1) are interchangable.

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Question 17: Agree with facility comment, answer key changed to accept either a or c as correct answers.

Question 20: This comment is unclear. However, based on comments made at the exit j mer'ing, the answer key has been changed to show either b or c as correct l answers.

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OPERATOR LICENSING EXAMINATION

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l WASHINGTON STATE UNIVERSITY April 14,1997 i Enclosure 3 '

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Section A Reactor Theory. Thermodynamics and Facility Characteristics Page 1

- QUESTION (A.1) [1.0]

Which ONE of the four factors listed below is the MOST affected by an increase in poison level in the reactor?

a. Fast Fission Factor (c)

b. Fast Non-Leakage Probability (%)

c.

Thermal Utilization Factor (f)  ;

d. Reproduction Factor (q)

QUESTION (A.2) [1.0) puestion modified per facility request, no answer key change.

Given a control rod worth of 0.1% AK/K/ inch and an at of-0.05% AK/K/*F. If temperature INCREASES by 9'F, how much and in what direction will the control rod move in order to maintain a constant power during the temperature change?

a. 4% inches inward i

b. 4% inches outward

c. 9 inches inward I' I

d. 9 inches outward

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QUESTION (A.3) [1.0]

A FAST neutron will lose the MOST energy per collision when interacting with the nucleus of I which ONE of the following isotopes?

a. H'

b. H*

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c. C

d. U2" i

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Section A Reactor Theory. Thermodynamics. and Facility Characteristics Page 2 QUESTION (A.4) [1.0] puestion deleted per facility request.

W.; rud;; h;d ; :hutd;;;n m;.rgin ;f 2.00, :nd ; nurn r;ng; nunt r;t; cf 10 ;;unt; p;r rn:aut;. ??;;.7 pln:ng nmpl= ln the in;";r th; ;;unt r;t; ;ne and t; 30 nunt; p;r n: nut;.

'/h,;; !; th; ;;;-th of th; n;np;g?

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5. :00; '

c. 1.200

d. 'i.200 QUESTION (A.5) [1.0] Question deleted per facility comment.

? TM0"""L n;utr;n hn th LE? T pr;b;bll;ti;f b;;ng ;tnrb;d by ;;h;;h ONE cf th; f;l c;;;ng ;;;;p;;?

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D.

O. C

d. L**

QUESTION (A.6) [1.0]

p for U2"is 0.0065. p., for the Washington State Univ. reactor is 0.007. Why is S ,

larger?

a. The reactor contains U2" which has a larger p for fast fission than U2".

b. The reactor contains Pu2" which has a larger p for thermal fission than Uru,

c. Delayed neutrons are born at a higher average energy than fission neutrons resulting in a greater amount of fast fissioning.

d. Delayed neutrons are born at a lower average energy than fission neutrons resulting in fewer being lost to fast leakage.

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! l Section A 9eactor Theory. Thermodynamics. and Facility Characteristics Page 3 l

! QUESTION - (A.7) [1.0) 1 Which ONE of the following is the MAJOR source of energy released during fission?

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a. Kinetic energy of the fission neutrons. 1 l

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b. Kinetic energy of the fission fragments.

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c.

) Decay of the fission fragments.

d. Prompt Gamma rays.

l QUESTION - (A.8) [1.0]

A reactor is exactly critical. What is the resultant K.,if all delayed neutrons were instantaneously removed from the reactor?

! a. 1007

b. 1.000

c. 0.993

d. 0.0000 l

l l QUESTION (A.9) [1.0)  :

As primary coolant temperature increases, control rod worth:

l a. increases due to higher reflector efficiency.

b. decreases due to higher neutron absorption in the moderator.

c. increat.es due to the increase in thermal diffusion length.

l l d. remains the same due to constant poison cross-section of the control rods.

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,, Section A Reactor Theorv. Thermodynamics. and Facility Characteristics '

Page 4 QUESTION (A.10) [1.0]

An initial count rate of 100 is doubled five times during startup. Assuming an initial K,=0.950, what is the new K,7 I

a. 0.957

b. 0 979

c. 0.988

d. 0.998 1

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! QUESTION (A.11) [1.0]

Which ONE of the following is the reason that reactor indicated power (count rate) stabilizes 4

several hours after a reactor trip? Assume all instrumentation is operable, and no reactivity j- changes, j- a. Suberitical multiplication of source neutrons.

b. Continuing decay of the longest lived delayed neutron precursor. -

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Neutron level dropping below detection threshold, the detector reading is due to a test l signal input from Nuclear instrumentation.

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d.

Gamma radiation due to decay of fission products below detection threshold, the j detector reading is due to a test signal input from Nuclear Instrumentation.

)~ QUESTION (A.12) [1.0)

! FLIP fuel contains a higher enrichment of US. Which ONE of the following is the correct reason for the addition of Erbium to FLIP fuel? Erbium is added as a bumable poison to allow j the higher concentration of US and ...

} a.

' Erbium has a high scattering cross-section thereby increasing the amount of neutrons absorbed by US in the epithermal range.

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! b.

Erbium has a low scattering cross-section for thermal neutrons, thereby, increasing the relative worth of neutrons absorbed by US in the epithermal range.

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Erbium has a high absorption cross-section for epithermal neutrons, thereby t

compensating for the reduction in US.

d.

Erbium has a low absorption cross-section for thermal neutrons, thereby increasing the relative worth of the control rods.

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Section A Reactor Theory. Thermodynamics. and Facility Characteristics Page 5 l QUESTION (A.13) [1.0)

You have shutdown the reactor. Reactor period has just stabilized and reactor power is at 1000 l cpm. Approximately what would you expect reactor power to read three minutes later?.

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.a. 500 cpm i

b. 333 cpm

c. 100 cpm l d. 10 cpm

, I QUESTION (A.14) [1.0)

If a $1.50 pulse has a peak power of 250 MW, a FWHM of 100 ms, and a fuel temperature rise l

l of 145'C, what would you estimate the peak power, FWHM, and fuel temperature rise values would be for a $2.00 pulse?

a. Peak power: 780 MW FWHM: 80 ms Temp. rise: 210*C

b. Peak power: 1000 MW FWHM: 50 ms Temp. rise: 290'C

c. Peek power: 1200 MW FWHM: 50 ms Temp. rise: 350'C

d. Peak power: 900 MW FWHM: 80 ms Temp. rise: 210'C QUESTION (A.15) [1.0]

Immediately after a pulse [ approx.1 millisecond) the HOTTEST part of a fuel element is ...

a. in the centerline of the cladding l b. at the edge of the fuel adjacent to the cladding

c. at the thermocouples, midway between the fuel axial centerline and the fuel edge,

d. at the axial centerline of the fuel elements I

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Sch A_3eactor Theorv. Thermodynamics. and Facility Characteristics Page 6 QUUSTION fa.1'd) [1.0]

Which ONE of the following statements correctly describes the diffe ences between prompt and delayed neutrons? Prompt neutrons . .

a. account for less than 1% of the neutron population, while delayed neutrons account for the other 99%.

. are released during the fission process, while delayed neutrons are released during the decay process,

c. . are reiwm juring the fission process, while delayed neutrons are released during the delayec re. :ron process.

d. s.re im d :minating factor in determining the reactor period while delayed neutrons have little e&c' on reactor period QUESTION (A.17) [1.0]

During a reactor startup, the Reactor Operator notes that the source is not in. After inserting the neutron source he notes reactor power is increasing LINEARLY. Whst was the condition of the reactorjust prior to inserting the source?

a. Substantially suberitical

b. Slightly suberitical

c. Exactly critical

d. Slightly supercritical ,

QUESTION (A.18) [1.0]

Which ONE of the listed reactivity coefficients will be FIRST to tum reactor power following a rod withdrawal. [ Assume no manual, (i.e. experiment insertion) or automatic (i.e. scram) reactivity additions.]

a. Fuel-Moderator

b. Water-Moderator

c. Void

d. Pressure

l Section A Reactor Theory. Thermodynamics. and Facility CharactMaitc.a Page 7

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QUESTION (A.19) [1.0] i Which ONE of the following correctly describes the behavior of the reactor as you approach criticality? ,

Time to stabilize neutron count j

a. Size of chance in eouilibrium neutron count longer larger i

b. shorter larger

c. longer smaller

d. shorter smaller QUESTION (A.20) [1.0]

Which ONE of the following is the correct definition of REACT /WTY? A measure of the core's

a. . deviation from criticality I I

b. fuel depletion

c. state with all control rods fully withdrawn

d. state at prompt criticality.

Section B Nomial. Emeroency and Radiolooical Control Procedures Page 8 QUESTION

" (B.1) [1.0] Question Deleted due to editorial error.

. sin;0;; num; gn;mt;; ; dn; ;f 100 mr/hr :t ; i;inc; ;f 10 f;;t ".'ith t;;; !=hn of

';;d ;h!;;ing th; m;ing drep; t; 50 mr/hr et ; i;;;n;; cf 10 f;;t. lf you ;;;r; t; ;dd -

ANGTHER4ete- nh;; ;f th; ;;m; typ: cf :h::ldag, th; madng ;t 10 f;;t ;;nid isp t; .

. 25 mr/hr

h. 12 % mr/hr C% mrlhr

d. S'/.'mr/hr QUESTION (B.2) [1.0]

The governor requests radiation workers to clean up an accident at Hanford Reservation.

While helping out you receive a dose of 6 Rem.10 CFR 20 requires that this dose be tracked as a Planned special exposure. Who is responsible for maintaining a permanent record of this dose?

a. Federal Emergency Management Agency (FEMA)

b. Washington State University.

c. Nuclear Regulatory Commission.

d. State of Washington, (an agreement state).

QUESTION (B.3) [2.0]

Identify each of the actions listed below as either a Channel Check, Channel Test, or Channel Calibration.

a. Verifying overlap between Nuclear Instrumentation meters.

b. Replacing an RTD with a precision resistance decade box, to verify proper channel output .'or a given resistance.

c. Performing a calorimetric (heat balance) calculation on the primary system, then adjusting Nuclear Instrumentation to agree.

d. During shutdown you verify that the period meter reads -80 seconds.

i Section 8 Normal. E. arggnqv and Radiolooical Control Procedures Page 9 QUESTION {~.1) i13] -

Match the requirements for maintaining an active operator license in column A with the correct time period from colurnn is.

golumn A Column B '

a. Renewal oflicense 1. 1 year

b. Medical Examination 2. 2 years

c. Requalification Written examination 3. 4 years

d. Rcqualifi ation Operating Test 4. 6 years  !

QUESTION D.5) (1.0)  !

An experimenter fell while carrying an irradiated sample. He broke his arm, and is bleeding. In i addition, the sample container broke and the experimenter is contaminated by radioactive i

powder. Where would you send the experimenter for treatment?

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a. Moscow Clinic

b. Memorial Hospital

c. Whitman Hospital

d. St. Joseph Regional Medical Center l QUESTION (B.6) [1.0]

Identify the lowest level of management who may authorize a substantive change to the l Technical Specifications:

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! a. Any Reactor Operator l b. Any Senior Reactor Operator  !

l c. The Facility Director

d. The NRC l

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, Section B Normal. Emeroency and Radiolooical Control Procedures Page 10 QUESTION (B.7) [1.0)

When pulsing, you are required to be at a power levelless than one KW. Which ONE (1) of the following is the reason for this limitation on power level prior to the pulse? To prevent exceeding ...

a. the maximum power levellimit

b. the fuel element temperature limit T

c. the pool temperature limit

d. the reactivity insertion limits QUESTION (B.8) [1.0]

Your annual dose received to date is 900 mrem. You are preforming maintenance on the reactor, in an area with a average dose rate of 300 mrem /hr. Which of the following is the i

bngest you may work without exceeding the 10 CFR 20 TEDE limit? (Assume no committted dose.)

a. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

b. l 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> '

c. 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> i

d. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> QUESTION (B.9) [1.0)

Total Effective Dose Equivalent (TEDE) is defined as the sum of the deep dose equivalent and the committed effective dose equivalent. The deep dose equivalent is related to the ...

a. dose to organs or tissues.

b. extemal e>posure to the skin or an extremity,

c. extemal erasure to the lens to the eyes.

d. extemal whole-body exposure i

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Section B Normal. Emeroenev and Radiolooical C.0fdrol.EC94Adutta Page 11 ,

QUESTION (B.10) [1.0]

Limiting Safety System Settings (LSSS) are ...

s. limits on very important process variables whic Je found to be necessary to reasonably protect the integrity of certain physical barriers which guard against the uncontrolled release of radioactivity. .

b. settings for automatic protective devices relatad to those variable having significant safety functions.

c. combinations of sensors, interconnecting cables of lines, amplifiers and output devices which are connected for the purpose of measuring the value of a variable.

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d. the lowest functional capability of performance Isvels of equipment required for safe operation of the facility.

QUESTION (B.11) [1.0]

Which ONE of the following conditions does not meet the requirements of an IRRADIATION?

a. Dose equivalent rate of 5 Rem /br et 1 foot upon removal from the reactor shielding.

b. Irradiation resides in the reactor br 12 days.

c. R'eactivity worth is $0.45

d. The sample contains natural uranium.

QUESTION (B.12) [1.0]

A system is found to be inoperable during the Pre-startup Reacter Checkout. The system being 4 inoperable will not violate technical specifications, written procedure., nor safe practices. What is the minimum level of authorization required before a Reactor Operator may startup the reactor?

a. Oral approval by the Senior Reactor Operator.

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b. Written approval by the Senior Reactor Operator.

c. Oral approval by the Facility Director

d. Written approval by the Facility Director.

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i Section B Normal. Emeroenev and Radioloaical Control Procedures Page 12 QUESTION (B.13) [1.0)

Which ONE of the following conditions is a violation of a Limiting Condition for Operation?

a. During a reactor power calibration actual power was found to be 1.2 Mwatt.

b. Peak temperature reached 810'C in a standard fuel element during a pulse.

c. The actual excess reactivity for the core is found to be 8.00$.

d. Pool conductivity was found to be 6 x 10-5 mhos/cm.

l QUESTION (B.14) [1.0]

An experimenter has requested permission to use the pneumatic transfer system (rabbit) to inject an experiment into the reactor. After granting the request, the reactor operator depresses the ...

a. " POWER" switch

b. " REQUEST / GRANTED" switch

c. " AUTO / TIMING" switch

d. " DELAY" switch -

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QUESTION (B.15) [2.0]

Match the general area radiation levels in column A with the corresponding 10 CFR 20 radiation area definition from column B. (Note: Only one answer per item in column A. Items in column B may be used more than once, or not at all.)

Column A Column B

a. 15 mrem /hr 1. Unrestricted

b. 65 mrem /hr 2. Radiation

c. 205 mrem /hr 3. High Radiation

d. 752 mrem /hr 4. Very High Radiation

Section B Normal. Emeroencv and Radioloaical Control Procedures Page 13 QUESTION (B.16) [1.0)

Which ONE of the SCRAMS listed is NOT required for reactor operations by Technical Specifications (Table 3.1)?

a. Nuclear Instrumentation Detector High Voltage Failure

b. Short Period

c. High Fuel Temperature

d. Nuclearinstrumentation High Flux QUESTION (B.17) [1.0]

There'are two SROs and one unlicensed RO trainee in the control room with the reactor operating. If one of the SROs becomes sick, what restrictions are placed on reactor operation.

a. The trainee may operate the reactor as long as the remaining SRO remains within the confines of the Nuclear Radiation Center,

b. The trainee may operate the reactor as long as the remaining SRO directs actions from within the confines of the control room.

c. The reactor may continue to operate with the SRO on the control panel, the trainee may be "on call".

d. The reactor must be shutdown, until a second licensed individual comes to the facility.

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i Section C Facility and Radiation Monitorina Systems Page 14 QUESTION (C.1) [1.0) 4 During operations at high power (950 kWatt) you lose compensating voltage for a compensated ion chamber. Which ONE of the following would be the resulting change in indicated power?

a. Small decrease in indicated power b.

Lcrge decrease in indicated power (Scram, due to loss of compensating voltage.)

i c. Smallincrease in indicated power.

d. .Large increase in indicated power.

QUESTION (C.2) [1.0,0.4 each]

identify each of the listed scrams as having input into the logic element, the low scram relay or both.

a. .High Fuel Temperature

b. Building Evacuation

c. Safety Channel # 1

d. Short Period i

e. Manual QUESTION (C.3) [1.0]

Which one of the following methods is used to prevent freezing in the secondary system during l cold weather?

a.

A heater in the secondary sump, controlled by the control room operator,

b. A heater in the secondary sump, automatically controlled by a thermostat. '

c.

Addition of chemicals to reduce the freezing temperature of the secondary coolant.

d.

At low temperatures an auxiliary operator is sent to heat the cooling fans with a heat gun (i.e. E hair dryer).

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Section C Facility and Radiation Monitorino Svstems Page 15 QUESTION (C.4) [1.0)

Which ONE of the following is NOT a design feature of the demineralizer system? l

a. Reduce radiation due to dissolved ions.

b. Reduce radiation due to gases in solution.

c. Reduce radiation due to suspended solids.

d. Reduce corrosion due to dissolved ions.

QUESTION (C.5) [1.0]

A pipe breaks just downstream of the primary coolant pump. What design feature of the system prevents draining of the pool?

a. Signal from a pool float which shuts a valve in the pump suction line.

b. Signal from a pool float which shuts off the primary pump.

c. Levelin the pool drops below a minimum required to supply suction pressure to the pump. (Net Positive Suction Head)

d. Level in the pool drops below siphon break holes in the suction pipe.

QUESTION (C.6) [1.0)

Which ONE of the following detectors is used primarily to monitor N released to the environment?

a. None, because of its short half-life, there is no need for environmental monitoring of N.

b. Continuous Air Monitor (Particulate)

c. Area Radiation Monitor

d. Gaseous Effluent

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Section C Facility and Radiation Monitorina Systems Page 16 QUESTION (C.7) - [1.0)

Which ONE of the of the following components is primarily responsibie for maintenance of pool water pH?

t l a. Water Filter l

b. Mixed Bed lon Exchanger

c. Skimmer

d. Chemical addition pot l

QUESTION (C.8) [1.0]

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How does the purification system ensure that impure make-up water is not added to the pool?

When the conductivity cell ...

a. downstream of the culligan system filters detects a high conductivity, it closes a solenoid '

valve upstream of the culligan system,

b. at the suction of the mixed bed ion exchanger detects a high conductivity, it closes a solenoid valve upstream of the culligan system.

c. at the suction of the mixed bed ion exchanger detects a high conductivity, it shuts down the purification system pump.

d. at the discharge of the mixed bed ion exchanger detects a high conductivity it shuts down the purification system pump.

QUESTION (C.9) [1.0)

How is the signal supplying the control element continuous position indication generated?

a. A series of limit switches located every % inch of control element length open and close as the magnet passes generating a signal proportional to control element position.

b. A servo generator chain driven by the drive motor generates a signal proportional to control element position,

c. A lead screw at the top of the control element moves in and out of an induction coil

- generating a signal proportional to the control element position.

d. A servo generator located in the control panel, is energized by auxiliary contacts in the in-out switch generating a signal proportional to the control element position.

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Section C Facility and Radiation Monitorina Systems Page 17 QUESTION (C.10) [1.0]

During which ONE of the following conditions is the Absolute filter in the ventilation system in use? ,

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a. Automatic and Isolation Modes

b. Automatic and Dilute Modes

c. Automatic Mode only 4

d. . Dilution Mode only QUESTION (C.11) [1.0)

How is radioactive effluent discharged using the dilution method?

a. The Dump /recirc pump supplies water to the eductor, which in tum provides motive force for the raw water, ,

b. The Dump /recire pump supplies water to vacuum break, which in tum provides motive force for the raw water.

c. The raw water flow through the eductor provides motive force for the radioactive effluent from the sample tank.

d. The raw water flow through the vacuum break provides motive force for the radioactive effluent from the sample tank.

QUESTION (C.12) [1.0) 1 Which ONE of the following nautron absorbing materialis NOT used in any of the control i elements?

a. Borated Graphite

b. Boron-Aluminum Alloy (Boral) I

c. Hafnium

d. Stainless Steel i

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Section C Facility and Radiation Monitorina Systems Page 18 QUESTION (C.13) [1.0)

What is the purpose of the Q coils in the ventilation system.

' a.

Tc maintain a negative pressure in the containment during automatic mode of operation.

b.

To transfer heat (cooling) from the exhaust system to the supply system during automatic mode of operation.

c.

To purify air admitted into the facility during dilute mode of operation.

d.

To provide a vacuum break for the pool room during isolation mode of operation.

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QUESTION . (C.14) [1.0)

The operability check for the ARMS requires you to depress a lighted green button on the face of the monitor. Depressing the green button ...

a. grounds the meter output, so that you may check the zero position on the meter.

b.

exposes the detector to a test source so that you muy check operability.

c.

inserts an electrical test signal into the circuitry to test operability.

d. checks the operability of the battery backup for the detector.

i QUESTION (C.15) [1.0)

An experimenter drops a radioactive source in a laboratory in the Nuclear Radiation Center. He leaves the room and is standing outside the door. You have two meters with you, an ion j

chamber and a Geiger-Muller. Which meter would you use first (holding it up to the door) j before entering the laboratory?

a. Geiger-Mueller, to detect contamination a

b. Geiger-Mueller, to detect radiation field

c. lon chamber, to detect contamination

d. ion chamber, to detect radiation field f

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Section C Facility and Radiation Monitorina Systems Page 19 QUESTION (C.16) [1.0)

Which ONE of the following is the purpose of the diffuser pump?

a. Increase heat transfer rate due to increased mixing in the pool.

b.

Decrease the activation rate of O to N due to reduced time in core.

c. Increase transport time for N to reach surface of pool.

d. Break up of O bubbles in pool, thereby decreasing production of N.

QUESTION (C.17) [1.0]

Which ONE of the following gases is used to propel the rabbit in the pneumatic tube system?

a. Air l

b. CO, l

j c. N,

d. He QUESTION (C.18) [1.0]

i Which ONE of the following is the neutron source use for reactor startup?

i j a. Am 'Be (Americium Beryllium) l b. 28'Pu 'Be (Plutonium Beryllium)

c. 2' Po 'Be (Polonium Beryllium) 12:

d. Sb 'Be (Antimony Beryllium)

1 I Sagtion C cacility and Radiation Monitorina Systems Page 20 t QUJ37lON (C.19) [1.0) -

Which ONE of the following is the main function performed by the DISCRIMINATOR circuit in i the startup channel?

a. To generate a current signal of equal and opposite polarity as the signal due to gammas  ;

ponerated within the Log-N channel Detector.

{

b. To filter out small pulses due to gamma interactions, passing only pulses due to neutron

] events within the Log-N Channel Detector.

l c,

1. . To convert the linear output of the Log-N Channel Detector to a logarithmic signal for metering purposes.

1 d: To convert the logarithmic output of the nietering circuit to a 5t (differenti'l u' me) output

for period metering purposes.

4,

QUESTION (C.20) [1.0) l You are withdrawing Control Blade #2 per SOP-4, Appendix A, part D, Withdrawal sequence for j pulsing coeration. A trainee inadvertently deenergizes the solenoid between the accumulator i tank and the transient rod cylinder. Which ONE of the following describes the effect on the i

transient rod (#3)?

a. Move out to its maximum upper limit. l' i b. Drop via gravity into the core. 1 4

l c. Remain at its present position (fully in).

i d. Move out to its maximum upper limit, then scram after 15 seconds.

4 4

?

s 1

.= - . . . .. . . - .. ..

.- .. ~-

StgliQDA Ettador Th.eorv. Thermodynamics and Facility Characteristics Page 21 l AM3WER (A1) 4 i

C REFERENCE (A.1)

WSU RO Training Manual, Unit 5, p.119 ANSWER (A.2) b i

t REFERENCE (A.2) '

bK 9'F x 0.0005 K *F

~

0.001 bK = 4.5 inches K-Inch ANSWER (A.3) a REFERENCE (A.3)

WSU RO Training Manual, Unit 5, p. 76.

' ANSWER (A.4) Question deleted per facility comment.

d REFERENOE (A 4)

SD*' - 0.0$ - 0.0170 APJM P,- 1/(1.0170) r 0.0020

% (1 FwN- M.,. "

• l(1 Fw)CNGRd 4-1 l(i 0.0020) r ".] [ 0.0172 x 0.0 ; - 1 0.0000 r 0.0014 p = (0.0020 - 0.0014)/(0.0020 x 0.0014) = 0.0 = 01.20 ANSWER (A.5) Question deleted per facility comment.

b REFEn N OE (A.0)

WEU no T dn:npunu ', Unr. O, ; ll,0. A::: ch:r. ;".h: tt;':c; ANSWER (A.6) d REFERENCE (A.6)

WSU RO Training Manual, Unit 6, 9 2.2 Delayed Neutrons ANSWER (A.7) b REFERENCE (A.7)

WSU RO Training Manual, Unit 5, p. 7.

I i'

Section A Reactor Theory. Thermodynamics. and Facility Characteristics Page 22 ANSWER (A.8)

, c REFERENCE (A.8) '

WSU RO Training Manual, Unit 5, ANSWER (A.9) e REFERENCE (A.9)

WSU RO Training Manual, Unit 5, pp.121 - 126.

ANSWER (A.10) d l

REFERENCE (A.10) t WSU RO Training Manual, Unit 5, $1V.A Approach to Critical p.174 I CR,/CR, = (1 - %)/(1 - Q) 1/32 (1 - 0.95) = 1 - % .

3 1 - 0.05/32 = %

% = 0.9984

)

ANSWER (A.11) a 1

REFERENCE (A.11)

, WSU RO Training Manual, Unit 5,9 IV.A Approach to critical pp. 130 - 140.

ANSWER (A.12) c REFERENCE (A.12)

, WSU RO Training Manual, Unit 11, p.13 ANSWER (A.13)

C REFERENCE (A.13)

P = Po e", Reactor period stabilizes at - 80 seconds. Time (t) = 180 seconds (three minutes). ,

P = 1000 e* = 1000 (e*) = 1000 (0.1054) = 105.4 i ANSWER (A.14) b REFERENCE (A.14)

RO Training Manual, Unit 11, second page 4. Simplified Pulsing Equations: Peak Power is 8

proportional to A$m , FWHM is proportional to 1/A$m and temperature increase is proportional to A$m where A$m = (p-E)

ANSWER (A.15) b REFERENCE (A.15)

WSU, Reactor Operator Training Manual, Figure 6.21, p. 6-51.

a 4

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

1 l

Section B Normal. Emeroenev and Radioiooical Control Precedures Page 23 j

ANSWER (A.16) i b i

- REFERENCE (A.16)

RO Training Manual, Unit 5, $ l.D Fission, pages 30 - 34.

' ANSWER (A.17) e REFERENCE (A.17)

RO Training Manual, Unit 6, pages 6-21, & 6-22.

ANSWER (A.18) a REFERENCE (A.18)

RO Training Manual Unit 6, page 1-2.  ;

l ANSWER (A.19) 1 a

REFERENCE (A.19)

Standard NRC question ANSWER (A.20) a REFERENCE (A.20)

WSU, RO Training Manual, Unit 6, 9 6.2.1, p. 6-11.

1 l

Section B Normal. Emeroenev and Radioloaical Control Procedures Page 24 ANSWER (B.1) PEl.ETED due toeditorialerror, b

ntrtntNOC (c.1) 9h :: en: 5:!f tS! ,::: gg,. U;:n; 3 h:: th;c=:: .;m drcp the d;;; by f;;;;r af (4)' = '/. 100/0 r i2.5 ANSWER (B.2) b REFERENCE (B.2) 10 CFR 20.

ANSWER (B.3) 1 t

a, check; b, test; c, calibration; d, check j

REFERENCE (B.3)

WSU Technical Specifications, 61.0 Definitions, p. 4. ,

ANSWER (B.4) a,4; b,2; c,2; d,1 REFERENCE (B.4) 10 CFR 55 t ANSWER (B.5) b l REFERENCE (B.5)

WSU Emergency Plan,6 3.1.12, p.13.  !

ANSWER (B.6) d j 1

REFERENCE (B.6) '

10 CFR 50.90 ANSWER (B.7) b REFERENCE (B.7)

WSU T.S. $ 3.6.3, BASES ANSWER (B.8) b c Answer changed per facility commentif(Editorial error.)

REFERENCE (B.8)

Stay time = (can get - got) divided by dose. Can get is the 10 CFR 50 limit = 5.0 Rem.

(5.0 - 0.9) + 0.3 = (41)/3 = 13%.

ANSWER (B.9) d REFERENCE (8.9) 10 CFR 20.1201 I

l i

. _ . _ . . _ . _ _ . _ _ _ . _ _ _ . . _ _ _._._ m _ _ _ . . _ _ _ . _ _.

Section B Normal. Emeroencv and Radiolooical Control Procedures Page 25 I ANSWER (B.10) b )'

REFERENCE (B.10)

Technical Specifications 51.4 ReactorInstrumentation '

. ANSWER (B.11) 1 c j REFERENCE (B.11)

SOP-2,6 A, second paragraph,1-4, pages 1 and 2, and SOP-1,6 B.1 a-d, page 2.

ANSWER (B.12) b REFERENCE (B.12)

SOP 4,5 A.9, pages 2 & 3. i ANSWER (B.13) d REFERENCE (B.13)

Technical Specifications,3.0 Limiting Conditions for Operation, $$ 3.1,3.3,3.4 & 3.13.

{

ANSWER (B.14) Second correct answer per facility comment.

a or b 1

REFERENCE (8.14)

SOP 2, 5 C, Procedure for Pneumatic Transfer System Irradiations pp. 3 - 6. i ANSWER (B.15) a,2; b,2; e,3; d,3 REFERENCE (B.15) 10 CFR 20.1003, Definitions ANSWER (B.16) b  ;

REFERENCE (B.16)

RO Training Manual, Unit 11. Scram Circuitry Figure, and Technical Specifications, Table 3.1.

ANSWER (B.17) s, b'

REFERENCE (B.17)

SOP-4, $$ A(2), (3) & (4), page 1.

i

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

1 i

Section C i~acility and Radiation Monitorina Systems Page 26 ANSWER (C.1) c j REFERENCE (C.1)  !

l Reactor Opert ter Training Manual, Unit 7,9 2.2.2, Compensated lon Chambers #2.

l ANSWER ,. (C.2) Pmswer modified per facility comment.

a, both or l'%ic; b, relay; c, both or logic; d, teley both orlogic; e, both relay REFERE CE (C.2)

RO Train ig Manual, Unit 11, SCRAM CIRCUlTRY DIAGRAM i

i 1

ANSWE.f: (C.3) b 4 REFERE NCE (C.3)

WSU, S; .R page 4-30 second paragraph. )

! I ANSWE1 (C.4) 1 b

REFERE NCE (C.4)

WSU, SAR S 4.10, page 4-30 i

}

ANSWE l! (C.5) d l REFERE WSU S.op{WCE figure 4.9 (C.5)

ANSWER (C.6)

, B REFERENCE (C.6)

WSU Safety Analysis for Conversion to FLIP fuel,6 6.0 Environmental Effects of Faci!ity

Operation, (d) Radioactive Discharges, (1) Gaseous pp. 9 & 10. l ANSWER (C.7) b REFERENCE (C.7)

WSU SAR, figure 4.10.

ANSWER (C.8) a REFERENCE (C.8)

WSU SAR, Figure 4.10 ANSWFR (C.9) b REFERENCE (C.9) 4 WSU SOP #8, Standard Procedure for Control Element Maintenance, Removal and Replacemeat, CAUTION on page 4.

i Section C Facility and Radiation Monitorino Systems Page 27 ANSWER (C.10) d l i

REFERENCE (C.10)

WSU, SAR, S 3, Figures 3.2.1 (new) & 3.2.1a.

ANSWER i (C.11) '

c-REFERENCE (C.11)

WSU, SAR, Figure 3.4-1, p. 3-13, and WSU SOP #11, Standard Procedure for Liquid Waste Samples, $ D Dilution System, pp. 6 - 8.

l ANSWER (C.12) c i REFERENCE (C.12)

WSU SAR, $$ 4.5'& 4.6, pp. 4 4-16.

ANSWER (C.13) i b

REFERENCE (C.13)

WSU SAR,9 3.2, Ventilation, page 3-9.

ANSWER (C.14) b j

REFERENCE (C.14)

SOP-17, $ B.1 p.1.

ANSWER (C.15) d REFERENCE (C.15)

ANSWER (C.16) e REFERENCE (C.16)

Standard NRC question. SOP 4,9 B.c.b p. 4.

ANSWER (C.17) Second correct answer added per facility comment.

a orc REFERENCE (C.17)

Verified at Facility.

' ANSWER (C.18) Answer modified per facility comment.

db REFERENCE (C.18)

Unit 11, Table: WSU TRIGA Reactor Characteristics

i 1

l Section C Facility and Radiation Monitorinc Systems Page 28 '

1 ANSWER (C.19) b REFERENCE (C.19) -

RO Training Manual, Unit 8, p. 31,15.

ANSWER (C.20) e REFERENCE (C.20) l~- FSAR $ 4.7, pages 4-19 & 4-21, also SOP-4, Appendix A page 12.

l l

l l

e l

l l

4 4

.