Text

Exam Rept 50-184/OL-93-01 on 930713.Exam Results:Applicant Passed Both Portions of Licensing Exam
	ML20056E443
Person / Time
Site:	National Bureau of Standards Reactor
Issue date:	07/26/1993
From:	Caldwell J, Guenther S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20056E442	List: ML20056E441; ML20056E443;
References
	50-184-OL-93-01, 50-184-OL-93-1, NUDOCS 9308240053
	Download: ML20056E443 (39)
	v • d • e

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1 ENCLOSURE 1 i

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U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT i

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REPORT NO.:

50-184/0L-93-01 t

j FACILITY DOCKET NO.:

50-184

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FACILITY LICENSE NO.:

TR-5 l

i FACILITY:

National Institute of Standards and Technology (NIST)

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EXAMINATION DATES:

July 13, 1993 l

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EXAMINER:

Sie fried Guent er SUBMITTED BY:

(.vv wt 7/2,., j e 3 f

S 4tFnther, Ch ef xaminer

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i APPROVED BY:

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7[,26[93

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Ja fe3 L. CaldieR, Criief

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N,dn-Power Reactor Section l

pperator Licensing Branch i

Division of Reactor Controls 1

and Human Factors, NRR t

SU t:1ARY.

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A written examination and an operating test were administered to one instant i

i senior reactor operator (SRO) applicant on July 13, 1993.

The applicant passed both portions of the licensing examination.

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i 9308240053 930803 PDR ADOCK 05000184.

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i REPORT DETAILS

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1.

Examiners:

S. Guenther, Chief Examiner 2.

Results:

r R0 SR0 Total 7

(Pass / Fail)

(Pass / Fail) l 0/0 1/0 1/0 i

3.

Written Examination:

The chief examiner provided Dr. Tawfik Raby with a copy of the written l

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examination and answer key for review after the applicant started the examination. Although Dr. Raby declined the opportunity to submit i

2 formal written comments on the examination, he and the applicant did j

l provide some verbal questions and comments during the course of the examination that resulted in minor changes and clarifications to the l.

following items-l

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A.13 The four distractors were changed to "O seconds," "-20 seconds,"

" 80 seconds," and "-120 seconds," respectively, because a heavy

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water reactor has a longer post-trip period than light water reactors.

i A.16 The tog N recorder runs from top to bottom and could not draw a I

straight horizontal line. The stem was clarified to indicate that

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the reactor period is infinite.

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_ i B.9 The stem of the question was clarified by specifying that only-the operations shift crew be considered.

C.10 The " thermal shield cooling flow" indication was changed from "440 gpm" to "390 gpm."

The incorrect reading was based on an error in facility procedure 0. I. 5.7, " Operation of the Process j

Instrumentation Safety System." Checklist-A, " Reactor Startup i

Checklist (Shutdown >24 hours)," of Facility procedure 0. I. 1.1, i

" Reactor Startup," supports the new reading.

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C.18 As the result of a tfpographical error, the units for the shim rod l

position were incorrectly specified in percent (%) rather than degrees (*).

None of these changes-required the answer key to be modified and no items were deleted.

The appropriate changes have~been entered on the.

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enclosed master examination.

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Operating T sts:

9 The operating test, including the reactor startup and the facility walk-(

through, were completed withont incident.

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Exit Meeting:

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The chief examiner held a brief exit meeting with Dr. Raby after i

completing the examination. No generic concerns or findings were ident i fied..

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f ENCLOSURE'2 1TRC-Of ficial Use Only 6

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.f Nuclear Regulatory Commission l

Operator Licensing r

Examination 3

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

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i NRC Official Use Only

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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS i

During the administration of this examination the following rules apply:

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j 1.

Cheating on the examination means an automatic denial of your application and could

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result in more severe penalties.

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

3.

Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the j

appearance or possibility of cheating.

4.

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

5.

Print your name in the blank provided in the upper right-hand corner of the examinatie1 cover sheet.

6.

Print your i.ame in the upper right-hand corner of the answer sheets.

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7.

The point value for each question is indicated in parentheses after the question.

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8.

Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. NOTE: partial credit will NOT be l

given on multiple choice questions.

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i 9.

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

i 10.

When turning in your examination, assemble the completed examination with examination l

questions, examination aids and answer sheets. In addition, turn in all scrap paper.

l 11.

When you are done and have turned in your examination, leave the examination area as l

defined by the examiner. If you are found in this area while the examination is still in i

progress, your license may be denied or revoked.

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EQUATION SHEET f

Net Work (out)

Q - m c, AT Cycle Efficiency -

j Energy (in)

Q = m Ah SCR - S/(1-Keff)

Q - UA AT CR (1-Keff)3 - CR, (1-Keff),

3 26.06 (1,,,p)

(1-Keff),

SUR -

M-(1-Keff)3 l

(# - p)

SUR - 26.06/r M - 1/(1-Keff) - CR /CR 3

g P = P,10"It)

SDM - (1-Keff)/Keff tt P - P e /r)

Pwr - W, m o

J(1-p)

P-P, t - 7 x 10" seconds p-p 1

r - (t /p) + [(f-p)/1,,,p]

r - t /(p-8) p - (Keff-1)/Keff 1,f, = 0.1 seconds-3 p - AKeff/Keff 0.693

'#2 J=0.008 1

DP1D

-DRD DR - DR,e'At 2

2 3

2g 3D I Curie - 3.7x10 dps I kg - 2.21 lbm I hp - 2.54x10 BTU /hr 1 Mw - 3.41x10 BTU /hr 3

6 1 BTU - 778 ft-lbf F = 9/S*C + 32

C - 5/9 (*F - 32) l l

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RX THEORY, THERMO & FAC OP CHARS Page 3

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QUESTION: 001 (1.00) f i

During reactor operation at 20 MW, one shim rod with a total worth of

$8.00 inadvertently scrams into the reactor.

WHICH ONE (1) of the i

following is the power level after the prompt drop?

a.

1935 KW

b. 2080 KW

c. 2364 KW j

i d.

2674 KW i

QUESTION: 002 (1.00) l Given the following neutron generation life cycle:

1020 fast neutrons 40 fast neutrons lost by leakage

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120 neutrons absorbed in U-238 j

80 thermal neutrons lost by leakage y

302 thermal neutrons absorbed in poisons, moderator and core materials.

75 thermal neutrons undergo non-fission capture in U-235 and U-238 i

1006 fast neutrons are produced by thermal fission to start the next generation.

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WHICH ONE (1) of the following is the resonance escape probability?

a. 0.88 I

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0.91 I

c.

0.96

d. 1.02 i

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(*****

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

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RX THEORY, THERMO & FAC OP CHARS Page 4

r QUESTION: 003 (1.00)

The reactor is operating at a constant period.

WHICH ONE (1) of the following power changes will take the SHORTEST time?

a. 1% to 6%

b.

10% to 20%

c. 20% to 40%

d. 40% to 70%

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QUESTION: 004 (1.00)

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A number of instrument indications fail during reactor operation.

The only indications available to the reactor operator are the following:

Primary flow 5500 gpm Core inlet temperature 98 deg F

-l Secondary flow through GE-1B 4000 gpm HE-1B secondary inlet temperature 83 deg F HE-1B secondary outlet temperature 95 deg F WHICH ONE (1) of the following is current reactor power?

a. 7.1 MW

b. 7.8 MW

c. 9.7 MW j

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d. 10.7 MW r

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

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RX THEORY, THERMO & FAC OP CHARS Page 5

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QUESTION: 005 (1.00) f During reactor startup the multiplication factor, Keff, is increased from 0.825 to 0.978.

WHICH ONE (1) of the following is the reactivity i

that has been added to the reactor?

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a. 0.022 delta K/K

b. 0.153 delta K/K

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c. 0.173 delta K/K l

d. 0.'190 delta K/K I

l QUESTION: 006 (1.00) t The reactor is being restarted 30 minutes after a full power scram.

i After returning to full power the reactor is operating in automatic.

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WHICH ONE (1) of the following is the MAJOR reason that the regulating

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-rod inserts into the reactor?

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a. Xenon decay i

b. Xenon burnup

c. Samarium buildup i

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d. Samarium decay

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QUESTION: 007 (1.00) l l

WHICH ONE (1) of the following is the principal source of heat one hour following reactor shutdown from full power?

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a. Photoneutrons l

b. Delayed neutrons j

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c. Fission product decay j

d. Energy stored in reactor components l

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(*****

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

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A.

RX THEORY, THERMO & FAC OP CHARS Page 6

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QUESTION: 008 (1.00) l WHICH ONE (1) of the following is the reason that delayed neutrons allow l

' control of the reactor?

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a. Delayed neutrons shorten the average period for a reactivity l

addition.

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b. Delayed neutrons increase the average neutron generation time.

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c. There are more delayed neutrons than prompt neutrons.

d. Delayed neutrons are born at higher energies than prompt neutrons and take longer to thermalize.

~i QUESTION: 009 (1.00) 4 I

Given the following:

i Moderator temperature coefficient

-S.02/deg F Regulating rod worth / inch S.03/ inch l

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During automatic reactor operation the moderator temperature slowly i

increases by 6 deg F.

WHICH ONE (1) of the following is the direction i

and distance that the regulating rod will move to compensar.e for the g

change in moderator temperature?

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a. The regulating rod will move IN 2 inches.

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b. The regulating rod will move OUT 2 inches.

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c. The regulating rod will move IN 4 inches.

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d. The regulating rod will move OUT 4 inches.

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

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RX THEORY, THERMO & FAC OP CHARS Page 7

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i QUESTION: 010 (1.00)

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WHICH ONE (1) of the following interactions in the reactor core is most j

efficient in thermalizing neutrons?

a. Hydrogen atoms in the coolant molecules.

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b. Oxygen atoms in the coolant molecules.

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c. Aluminum atoms in the fuel cladding.

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d. Carbon atoms in the reflector.

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i QUESTION: 011 (1.00)

Given the following conditions:

Reactor is shutdown Shutdown margin 5%

Source range power level 1500 cps An installed experiment is worth

-$1.06 l

Xenon is decaying Following removal of the experiment, source range power level is 2500 l

cps.

WHICH ONE (1) of the following was the approximate change in reactivity due to Xenon.

a.

$.96 b.

$1.51 c.

$2.57 I

a d.

$3.67

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

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RX THEORY, THERMO & FAC OP CHARS Page 8

QUESTION: 012 (1.00)

The following data was obtained during a core loading:

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(Assume all rods are out)

Number of Fuel Elements Count Rate (CPS) 0 20 4

27 6

32 8

40 10 53 12 79 WHICH ONE (1) of the following identifies the number of elements necessary to attain criticality?

a.

14

b. 16 c.

18

d. 20 l

P QUESTION: 013 (1.00)

The reactor is operating at 100% power at the end of core life with all rods out.

An automatic scram is inserted.

WHICH ONE (1) of the following is the final, stable reactor period 60 seconds after the

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scram?

i a.

O seconds

-2p

b. -f seconds

.go

-)2tf seconds c.

d. -M seconds

-12.o l

(*****

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

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RX THEORY, THERMO &.FAC OP CHARS Page 9

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i QUESTION: 014 (1.00)

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Reactor power increases from 20 watts to 1.6 Kw in 500 seconds.

WHICH ONE (1) of the following is the approxinate doubling time?

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a. 79 seconds

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b. 198 seconds

c. 240 seconds

d. 347 seconds QUESTION: 015 (1.00)

During a change in reactor power, WHICH ONE (1) of the following will f

affect reactivity first?

a. Change in fuel temperature.

b. Change in moderator temperature.

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c. Change in void concentration

d. Change in reactor pressure.

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QUESTION: 016 (1.00) g When entering the control room, the reactor o rator notices that the Log N recorder has a straight hor 4aont-a4 line.

There is no rod motion.

WHICH ONE (1) of the following can NOT be true?

a. A neutron source is in the core.

b. The reactor is sub-critical.

c. The reactor is critical.

d. The reactor is super-critical.

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

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RX THEORY, THERMO & FAC OP CHARS Page 10 QUESTION: 017 (1.00) l WHICH ONE (1) of the following conditions describes a reactor that is l

exactly critical?

a. Keff equals 0; delta K/K equals 0

b. Keff equals 0; delta K/K equals 1

c. Keff equals 1; delta K/K equals 0

d. Keff equals 1; delta K/K equals 1

' QUESTION: 018 (1.00) 1 WHICH ONE (1) of the following is the reason for controlling with thermal neutrons instead of fast neutrons?

a. The fission cross section of the fuel is much higher for thermal energy neutrons than fast neutrons.

b. Fast neutrons are such a small percentage of the total neutron population they would have little effect.

c. Neutron efficiency increases since thermal neutrons are less likely to leak out of the core than fast neutrons.

d. Doppler and moderator temperature coefficients become positive as neutron energy increases.

QUESTION: 019 (1.00)

WHICH ONE (1) of the following is the approximate energy released by a single fission?

a. 2 MeV

b. 100 MeV

c. 200 MeV

d. 1000 MeV

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

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RX THEORY, THERMO & FAC OP CHARS Page 11

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i QUESTION: 020 (1.00)

WHICH ONE (1) of the following defines the thermal utilization factor?

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a. Thermal neutrons that cause fission divided by thermal neutrons absorbed in fission, l

b. Thermal neutrons absorbed in the fuel divided by thermal neutrons absorbed in the fuel and the core materials.

c. Fast neutrons produced by thermal fission divided by thermal reutrons absorbed in the fuel.

d. Neutrons that reach thermal energy divided by fast neutrons that start to slow down.

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END OF CATEGORY A *****)

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NORMAL /EMERG PROCEDURES & RAD CON Page 12 QUESTION: 001 (1.00) l WHICH ONE (1) of the following is the MAXIMUM radiation exposure authorized to perform lifesaving activities during a high radiation

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release WITHOUT prior approval of the Emergency Director?

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a. 5 rem E'

b. 25 rem

c. 50 rem

d. 100 rem l

QUESTION: 002 (1.00) l The following information is given on a qualified NIST radiation worker.

Male, 37 years old Current week whole body exposure 210 mrem Current quarter whole body exposure 1130 mrem Lifetime whole body exposure 3670 mrem q

Current exposure history is on file No.special approvals have been given WHICH ONE (1) of the following is the MAXIMUM time that the worker can stay in a 30 mrem / hour radiation field without exceeding whole body limits?

a.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

b. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

c. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months i

d. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months i

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(*****

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

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NORMAL /EMERG PROCEDURES & RAD CON Page 13 f

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QUESTION: 003 (1.00)

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WHICH ONE (1) of the following is used as a basis for downgrading.a radiological emergency classification?

a. Approval of the NRC.

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b. Isolation of the release point,

c. Adequate core cooling is established.

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d. Survey conducted at the site boundary.

QUESTION: 004 (1.00) l 1

A RWP is issued for non-repetitive work in a high radiation field.

l WHICH ONE (1) of the following is the length of time that this RWP will remain in the " Active Radiation Work Permit" file?

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a. Until the job is completed.

b. Until the end of the current shift.

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c. Until the end of the current work week.

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d. For 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i QUESTION: 005 (1.00) i WHICH ONE (1) of the following reflects the MAXIMUM limits for contamination in the Restricted Areas?

ALPHA BETA-GAMMA j

a.

20 dpm/100 sq cm 200 dpm/100 sq cm b.

50 dpm/100 sq cm 500 dpm/100 sq cm j

c.

100 dpm/100 sq cm 1000 dpm/100 sq cm l

i d.

0.05 mrad /hr 0.25 mrad /hr I

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

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NORMAL /EMERG PROCEDURES & RAD CON Page 14 f

QUESTION: 006 (1. 0 0)

A point source of gamma radiation is measured at 4 Rad /hr at 3 feet.

WHICH ONE (1) of the following is the dose rate at 12 feet from the source?

a. 83 mR/hr i

b. 250 mR/hr

c. 1000 mR/hr

d. 3000 mR/hr P

QUESTION: 007 (1.00)

WHICH ONE (1) of the following experiment configurations meets the Technical Specifications?

a. One experiment worth +0.77% rho.

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b. One experiment worth -0.68% rho.

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c. Two experiments, one worth -0.53% rho and one worth +0.45% rho.

d. Seven experiments, four worth -0.45% rho each and three worth l

-0.25% rho.

p QUESTION: 008 (1.00)

The reactor has failed to scram.

A moderator dump has been initiated.

WHICH ONE (1) of the following components is required to be secured manually as part of the operator immediate actions?

a. Main primary coolant pumps

b. Main secondary cooling pumps

c. Primary shutdown cooling pumps

d. Secondary shutdown cooling pump

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

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,B.

NORMRL/EMERG PROCEDURES & RAD CON Page 15 QUESTION: 009 (1.00) cytreems WHICH ONE (1) of the following is the MINIMUM ^ shift complement during fuel transfer from the core to the storage pool?

a. 5

b. 4

c. 3

d. 2 QUESTION: 010 (1.00)

During the life of the plant, data is kept on the leakage of primary coolant into the secondary system.

WHICH ONE (1) of the following exceeds the limiting conditions for operation?

a. 24 gallons in one day.

b. 42 gallons in one week.

c. 73 gallons in one month,

d. 194 gallons in one year.

QUESTION: 011 (1.00)

WHICH ONE (1) of the following is the basis for the limiting condition for operation that requires reactor shutdown if the Deuterium gas concentration in the helium sweep system is greater than 4% by volume?

a. To maintain the gas mixture below explosive concentrations.

b. To reduce the formation of. tritium.

c. To prevent corrosion of vessel internals.

d. To assure that the recombination is complete.

(*****

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

B.

NORMAL /EMERG PROCEDURES & RAD CON Page 16 r

i QUESTION: 012 (1.00)

The reactor is operating with an outer plenum flow of 4000 gpm and an inner plenum flow of 720 gpm.

WHICH ONE_(1) of the following is the MAXIMUM power that the reactor can operate at without exceeding the

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limiting safety system trip settings?

a. 9 Mw i

b.

12 Mw

c. 17 Mw

d. 20 Mw 7

I QUESTION: 013 (1.00) i WHICH ONE (1) of the following is the MINIMUM amount of U-235 that the reactor can contain to be considered OPERATING?

a. 0.9 kg b.

1.3 kg

c. 1.9 kg

d. 2.2 kg l

QUESTION: 014 (1.00)

A laboratory will contain an experiment for 60 days.

The average radiation levels in the laboratory will be 80 mrem / hour.

WHICH ONE (1)

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of the following is the required actions for the laboratory?

a. Posted Restricted Area only

b. Posted Radiation Area only l

c. Posted Resticted Area and Radiation Area l

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d. Posted High Radiation Area with an entry control device and l

audible alarm.

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( * * * *

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

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NORMAL /EMERG PROCEDURES & RAD CON Page 17 fj i

QUESTION: 015 (1.00)

WHICH ONE (1) of the following is the purpose of the tritium monitor?

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a. Monitor the tritium concentration within confinement.

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b. Monitor for a primary to secondary heat exchanger leak.

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c. Measure the tritium release through the stack.

d. Measure the tritium release to the sanitary sewer.

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QUESTION: 016 (1.00)

The Reactor Supervisor has authorized a clearance and Tag #1189 has been hung on a piece of plant equipment.

Under WHICH ONE (1) of the following conditions may the equipment be operated?

a.

Only by the person to whom the clearance was issued.

t

b. Only after permission is granted by the Reactor Supervisor.

c. Only under specific conditions. listed on the tag.

d. Only after the work has been finished and the tag has been i

removed.

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B.

NORMAL /EMERG PROCEDURES & RAD CON Page 18 i

QUESTION: 017 (1.00)

The reactor is shutdown and the MCC supplying electrical power to the shim rods has been isolated for breaker maintenance.

Testing must be performed on Shim #2 and a jumper is being installed to provide temporary power.

This is considered a minor modification and no special test procedure has been issued.

WHICH ONE (1) of the following is required to approve the temporary jumper installation?

a. Reactor Supervisor

b. Chief, Reactor Operations

c. Chief, Reactor Radiation Division

d. Safety Evaluation Committee 1

QUESTION: 018 (1.00)

Approval has been given for use of RT-4 pneumatic tube.

WHICH ONE (1) of the following pneumatic facilities is also approved for use?

a. RT-3

b. RT-1

c. RT-2

d. RT-5 I

QUESTION: 019 (1.00)

WHICH ONE (1) of the following is the MINIMUM power at which the reactor can be operated in automatic control?

a. 10 Kw b.

100 Kw

c. 1000 Kw

d. 2000 Kw

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B.

-WORMAL/EMERG PROCEDURES & RAD' CON Page 19 t

QUESTION: 020 (1.00)

WHICH ONE (1) of the following is NOT a proper line-up for the emergency diesel generators during reactor operation?

a. The diesel manual disconnects are closed.

b. The diesel auxiliary circuit breakers are open.

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c. The diesel day tank pump is in AUTO.

d. The diesel cooling water surge tanks are 3/4 full.

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-(*****

END OF CATEGORY B *****)

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"-C.

-PLANT AND RAD MONITORING SYSTEMS Page 20 i

i i

1 r

f QUESTION: 001 (1.00)

WHICH ONE (1) of the following is the MAXIMUM number of fuel elements i

that may be removed from their storage racks at any one time during refueling?

I

a. 4 I

b.

6 i

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c. 8 l

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d. 10 t

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QUESTION: 002 (1.00)

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i WHICH ONE (1) of the following is the purpose of the activated charcoal filters in the emergency exhaust system?

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a. To remove moisture i

b. To trap particulate i

c. To protect the absolute filters

d. To absorb radioactive iodine l

I QUESTION: 003 (1.00) i A trace of driven shim movement over the length of travel of each shim is performed annually.

WHICH ONE (1) of the following is the purpose of the trace?

I

a. Detect slow clutch release time.

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b. Provide a measure of the first five degree drop.

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c. Provide indication that the shock absorber is operable.

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d. Reveal possible obstructions along the travel of the shim.

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i "C.

PLANT ?.ND RAD MONITORING SYSTEMS Page 21 i

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QUESTION: 004 (1.00)

.WHICH ONE (1) of the following detectors is used for nuclear

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instrumentation channels ND-1 and ND-27 i

a. Boron-10 proportional counter

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b. Compensated ionization chamber

c. U) compensated ionization chamber

d. Fission chamber i

i QUESTION: 005 (1.00) l WHICH ONE (1) of the following is the neutron poison found in the regulating rod?

l

a. Aluminum t

b. Cadmium l

c. Boron i

d. Hafnium QUESTION: 006 (1.00)

Following a rupture in the primary cooling system, the Emergency Cooling Tank level drops to 9 inches.

WHICH ONE (1) of the following is the immediate operator action?

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a. Start the shutdown cooling pumps.

b. Start light water cooling.

C.

Close DWV-12, reactor quick fill.

d. Close DWV-34 and DWV-35, plena feed.

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PLANT AND RAD MONITORING SYSTEMS Page 22

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- QUESTION: 007 (1.00) i WHICH ONE (1) of the following is used to control the pH of the secondary cooling system?

a. Hydrochloric acid

b. Sulfuric acid i

c. Sodium hydroxide j

d. Ammonium hydroxide i

QUESTION: 008 (1.00) l WHICH ONE (1) of the following will NOT be powered by the diesel generators during a loss of commercial power accident?

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a. Helium blowers I

b. Secondary shutdown cooling pump l

1

c. Main primary coolant pumps j

d. Thermal shield cooling pumps 1

1 QUESTION: 009 (1.00)

WHICH ONE (1) of the following is the purpose of the Carbon Dioxide system?

a. Corrosion inhibitor in the primary coolant.

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b. Backup to the Helium Sweep system.

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c.

Plant fire suppression system.

d. Minimize Argon activation.

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

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s C.

PIJsNT AhD RAD MONITORING SYSTEMS Page 23 l

)

QUESTION: 010 (1.00) i Given the following indications:

Stack Monitor RD 4-1 3600 cpm l

Reactor level 147 inches Reactor differential temperature 18 degrees F i

Reactor outlet flow 6600 gpm Reactor outlet temperature 125 degrees F Therral column tank flow 35 gpm l

Thermal shield cooling flow 390 449 gpm i

Emergency cooling tank level 55 inches Primary coolant overflow 14 gpm WHICH ONE (1) of the following identifies the current condition of the reactor?

a. A startup prohibit condition exists.

b. A rundown is in progress.

l

c. A minor scram has occurred.

d. A major scram has occurred.

QUESTION: 011 (1.00)

WHICH ONE (1) of the following uses an ion chamber detector?

a. Gaseous fission product monitor

b. Ventilation tritium monitor

c. Secondary coolant monitors

d. Stack monitors

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PLANT AND RAD MONITORING SYSTEBG Page 24 l

QUESTION: 012 (1. 00 )

The containment building has isolated and the normal ventilation has l

shutdown.

Building pressure is being maintained at -0.25 inches water f

by the emergency exhaust system.

WHICH ONE (1) of the following i

I automatic actions will occur if the building pressure increases to -0.10 inches water?

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a. The emergency fans will be powered by the DC emergency bus.

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b. The standby fan will start.

j

c. The normal ventilation will re-start.

i

d. ACV-10 will close.

QUESTION: 013 (1.00)

WHICH ONE (1) of the following conditions allows the process scram logic selector to be placed in the "2 of 2" position while the reactor is j

operating?

a. When checking channel operability.

f

b. When power is maintained below 10 Mw.

c. When there are no experiments present in the reactor.

I

d. When the reactor control is in MANUAL.

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C.

PLANT AND RAD MONITORING SYSTEMS Page 25 QUESTION: 014

{1.00)

Given the following:

The reactor is shutdown.

Critical Power Transfer Switch is in "T-10" position.

Rod Drive Power Transfer Switch is in "T-10" position.

Diesel B Master Selector Switch is in AUTO.

Diesel A Master Selector Switch is in STANDBY.

The feeder breaker at SBA substation supplying MCCA-3 with commercial power trips open.

All other electrical equipment and components function as designed.

WHICH ONE (1) of the following provides continuous power to the Critical Power portion of the facility distribution system?

a. Diesel Generator B

b. MCCB-6 via SBB substation c.

Inverter / Diverter via the Emergency battery

d. Static Inverter via the Emergency battery

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

i C.

PLANT AND RAD MONITORING SYSTEMS Page 26 QUESTION: 015 (1.00)

Alarm AN 2-17, CRYOSTAT TROUBLE, has actuated.

The following readings f

are reported from the Cryostat Instrument Panel:

i Insulating Coarse Pressure 0.5 psia Insulating Vacuum Ion Gauge 4x10-3 torr Outer Jacket Cooling Flow Indicator flow indicated

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Space Jacket Cooling Flow Indicator flow indicated j

Cover Gas Pressure 19 psia WHICH ONE (1) of the following states the automatic action that should have occurred?

a. Refrigerator shutdown

b. Vacuum valve closed

c. Outer Jacket Cooling supply valve opened

d. Helium Sweep started i

QUESTION: 016 (1.00) i Alarm AN 2-29, SECONDARY COOLANT HIGH RADIATION, has actuated.

Pritrary heat exchangers HE-1A and HE-1B are being isolated and drained.

Heat i

exchanger HE-2 is being placed into service.

During performance of this task, the operator is required to start an auxiliary booster cooling pump.

WHICH ONE (1) of the following states the reason for this requirement?

a. auxiliary pump flow is inadequate to supply heat exchanger HE-2

b. auxiliary pump pressure du less than storage tank pump pressure l

c. booster pump is supplied electrical power from the emergency bus

d. booster pump operation allows use of a redundant radiation l

j monitoring instrument e

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

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PLANT IdC RAD MONITORING SYSTEMS Page 27 QUESTION: 017 (1.00)

Alarm AN 2-28, HE SWEEP GAS HIGH RADIATION, has actuated.

According to NIST alarm response procedures, WHICH ONE (1) of the following systems provides a source for confirmation of a fuel element cladding failure?

a. Filter monitor RD 1-11

b. Secondary Coolant monitor RD 3-1

c. Air Exhaust monitor RD 3-5

d. Liquid Effluent monitor RD 4-3 QUESTION: 018 (1.00) agree, (*)

During startup, the four shim rods are at 8kfwhen both -10 volt power supplies to the nuclear instrumentation are simultaneously lost.

WHICH ONE (1) of the following states the expected response?

a. Rods will remain in position, but experience a ROD STOP.

b. Rods will experience a RUNDOWN.

c. Rods will fully scram into the reactor.

d. Rods will only partially scram into the reactor.

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'C.

PLANT AND RAD. MONITORING SYSTEIG Page 28 QUESTION: 019 (1.00)

WHICH ONE (1) of the following describes how the signal for Regulating Rod position on the console is generated?

a. As the lead screw moves out, the impedance of a pick-up coil changes generating a changing voltage.

b. A mechanical position indicator connected to the drive motor generates the signal.

c. Position indication transmitters are connected to the motor shaft through servo gear, trains.

d. A circuit with input from switch 7S3 generates a signal proportional to rod travel for the time the switch is in either the RAISE or LOWER position.

QUESTION: 020 (1.00)

WHICH ONE (1) of the following Rabbit system tips is located in the central plane of the core and must be immediately evacuated if cooling flow is lost from the D20 Experimental Cooling system?

a. RT-1

b. RT-2

c. RT-3

d. RT-4 l

1 A

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(*****

END OF CATEGORY C *****)

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

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A.

RX THEORY, THERMO & FAC OP CHARS Page 1

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-ANSWER KEY t

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MULTIPLE CHOICE l

001 c

i 002 a

003 d

i 004 a

005 d

006 b

007 c

008 b

009 d

010 a

011 b

012 b

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( 013 d

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014 a

t i

015 a

i 1

016 d

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017 c

018 a

i 019 c

j i

020 b

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END OF CATEGORY A *****)

B.

WOPERL/EMERG PROCEDURES & RAD CON Page 2

ANSWER KEY MULTIPLE CHOICE 001 b

002 c

003 d

004 a

005 a

006 b

007 d

008 b

009 c

010 d

011 a

012 b

013 d

014 c

015 a

016 d

017 b

018 d

019 b

020 b

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

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C.

PLANT'AND RAD MONITORING SYSTEMS Page 3

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ANSWER KEY l

MULTIPLE CHOICE 001 b

002 3

003 d

004 a

005 a

006 b

a 007 b

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008 c

009 d

I 010 b

i 011 b

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012 b

013 a

014 b

i 015 b

l 016 b

t 017 c

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i 018 d

i 019 c

f 020 a

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

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

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