IR 05000225/1990002

Exam Rept 50-225/90-02OL on 900309.Exam Results:Both Senior Reactor Operator Candidates Passed Partial Retake Exams

ML20034B878
Person / Time
Site:	Rensselaer Polytechnic Institute
Issue date:	03/26/1990
From:	Eselgroth P, David Silk NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20034B877	List: IR 05000225/1990002
References
50-225-90-02OL, 50-225-90-2OL, NUDOCS 9005010107
Download: ML20034B878 (22)

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U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EX/JilNATION REPORT i

.

REPORT NO.:

50-225/90-02(OL)

FACILITY DOCKET NO.:

50-225

,

FACILITY LICENSE NO.:

CX-22 LICENSEE:

Rensselaer Polytechnic Institute

Troy, New York 12180 FACILITY:

Rensnelaer Polytechnic Institute Critical Facility

EXAMINATION DATES:

MARCH 9, 1990 i

SUBMITTED BY:

b l

3/26/9 4 David M. Silk

'Oa t(

Senior Operations Engineer 2kf/

APPROVED BY:

2/

</

Peter W. Eselgroth h<ef~

' Date PWR Section, Oper ons Branch SUMMARY:

Partial written retake examinations were administered in the regional office l

to two SRO candidates.

Sections I (Radioactive Material Handling, Disensal and Hazards) and K (Fuel Handling and Core Parameters) and-Sections K and L (Admi-nistrative Procedures, Conditions and Limitations) were administered to the

!

respective candidates.

Both candidates passed the retake examination and were

issued licenses.

-l There was no exit interview held because the examination was conducted in the regional office.

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DETAILS

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TYPE OF EXAMINATIONS:

Replacement EXAMINATION RESULTS:

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RO ll SRO l TOTAL l

Grading IPass/ Fail Pass /Faill Pass / Fail l l

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Written l

0/0 l 2/0 l 2/0 l

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l Simulator l

N/A l N/A l N/A i

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l Operating l

0/0 l Waived l N/A l

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0/0 l 2/0 l 2/0 l

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l ATTACHMENT:

1.

Written Examination with Answer Key l

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an?extremel.radiologica$[emergencyc

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9 AntwerJ.the following: questions;assumingic

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%.jIn:accordance withcthe! Personal' External (Exposure!Proceddre,(exp6sures

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exceeding 10;CFR 20' limits'can-be^ approved by:(CHOOSEiONLYi.ONE):t.g

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-1.-Radiation)Shfetyt 0,f fic er :

,

.

2..SeniorL Operator

c'n L. duty..

pp-3.f0perations Suporvisor

+

4.rRadiati'on Safety-Of1icer!and Operations Supervisor-

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J 5.-Facility, Director b.

'The total (WHOLE BODY dose exposure for-an;adultishal17beil'imited'to-y WHICHLONE(of the'following:

!?

'i.

7.5 Rem 2.-

12.-5 Rem-3.

-la.5 Rem 4.

25.0 Rem-5.

50.O' Rem

.* ANSWER

.a.34.[1.03-

"

'b.'2nE1.O]

-

-* REFERENCE

^

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LEmurgency Procedure, 9.3, Personal External Exposure

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n 40 VAL 1.0

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. * QUESTION?

WHAT can the-wearer'of a TLD do that'wi'11 enable aETLD-to, DIFFERENTIATE

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• b3 tween types of radiation exposureLto his body? ' CHOOSE-the ONE;BEST-:

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. c n f.w e r.

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a.

. Wear multtple TLDs t

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U b.- Use different filters on the TLD 7 c..i Change the locaticn of tiir: TLD-on the. body at regular ntervals.

.

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'd.. ETLDs cannot. dif ferentiate between dif ferent' types of exposure

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.* ANSWER 1

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[1.O]!

• REFERENCE '

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• KA

• OUESTION

'WHICH-ONE of the isotopes listed be.loH is the MOST commonly expected

airborne radioactive effluent produced et the RPI reactor?

a.

N-16 b.

1-131 c.

Ar-41-d.

H-3 e.

He-4

• ANSWER c.

(i.03

• REFERENCE SER Sect 11.3 tGNUM

• ODAT-1989/09/06

• FAC 225

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• EXMNR SILK, D.

• GVAL 1.5

• SEC.

I

• KA

• QUESTION According to the Personal Safety and Radiation Monitoring Manual, WHAT are the THREE aspects of shielding the reactur?

• ANSWER 1. Slow down fast neutrons (0.53 2. Capturing the slowed down neutrons

[0.53 3. Attenuating all forms cf gamma radiation EO.53

• REFERENCE PSRM manual, p2 i

• GNUM

• ODAT 1989/09/06 4FAC 225

,

• RTYP TEST

• EXLV S

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D.

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• SEC I

• KA tGUESTION WHICH ONE of the following is the 10 CFR 20 permissible limi+, for WHOLE BODY done to a radjotion worker during a CALENDAR QUARTER 7 a.

O.1 Rem /qtr b.

1.25 Rem /qtr c.

7.5 Rem /qtr d.

12.5 Rem /qtr e.-1S.75 Rem /qtr

• ANSWEP b.

(1.0)

'* REFERENCE 10 CFR 20.101

• GNUM-

• QDAT 1989/09/06-9,

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A ** QUESTION ~

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[Rodt, are.ful'ly.[innertediand! the reactor $ ter.K is complete 4v drained. ' Work r

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lib beingt performed on the: control: rod f dr.tves...With the(console; energized,-

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'WHAT2 feature (s)l.-listedibelow would"PROHIL4TTIthe-neutron source ~driQe from.

lowering 4 the' source s out;:of ' the, c.on tainar!. -

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Y f a. t Water:. level fin terlock

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s by Neutron fluk % 2 cr.slinterlocF t.c:i Dump valve open -:in te~rlock

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dd. s No (prchibi ti've S TeatureJ

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'WHICH-ONE of-the f ollowing is: the.:MOST;ef f ective sha eldfagainst. GAMMAS?

,

c..? Graphite '

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b.. Water

c. Lead

__d. l B o r o n o.Jconcrete-

• ANEWER c.

(1.0)

• REFERENCE

~.' intro:to Nuc Eng., Ch 10, r,ect 10.1

• GNUM

~

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'*FAC 22S 4.g

• RTYP TEST

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'* QUEST.IONJ

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L Listed-below are f our types of. ifanizing radiation.

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1.-Alpha 2.-Beta.

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3.1 Gamma

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4 ~. Neutron

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A. :WHICH.ONE of the_following choices'best-represents the different; types Dof-ionizing'radiationL-in. order of HIGHEST TO LOWEST ~ relative'

jpenetrating ability 7-

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WHICH ONEIof dheffol'1owingfisLDOSE.'EQUIVALENTfto1 rasfiation. exposure.[to ?1.OD

[A 1,

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. RAD-OF1 GAMMA' radiation?'

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r Personal Safety and Radiation. Mon.itoring, p.z3-e

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.*QDAT 1989/09/06

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'* QUESTION

'

WHICH ONE of the f ollowing BEST represents HOW LONG it wil'Il take. S.'O' grams

--of a five curie Co-60 source -(T 1/2== 5.26 yrsi' to decay so that.it will.

>

cmit only ONE curie?

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. a.--- O. 2 1 y r s

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eb.;1.22~ yrs-c. 1.61 yrs

i d.<2.32 a. S.26[ yrs j=

yrs

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ys

.s..mr-

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• REFERENCE

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1 Intro to Nuc Eng, Ch 2, p.22

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L*QNUM

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1989/09/06

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.WHICH-ONE of:the' dosages below*BEST represents-the ac'ute radiation exposure-that1wil'l.' result in death;within 30, days for 50% of the people that are

xposed?

]

c. 0.5 Rem

-$

.

.b.

5.0 Rem c.

Rem

'

d.

500 Remi

. a. 5(N-18) Rem

.* ANSWER'

,

d. (i.0)

tREFERENCE.

-Intro to Nuc Eng, Ch 9',

p.-379

+

• QNUM

-*QDAT 1989/09/06

• FAC 225 e

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TEST

• EXLV-S

• EXMNR.

SILK, D.

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• SEC I

'*KA

• QUESTION

,,

aWHICH of'the 1ollowing are the LEAST. EFFECTIVE ways to. protect.against.

CONTAMINATION?

More-than one answer is possible.

.a.

Minimi:e leakage of contaminated substances b. Control access to S contaminated area c. Maximite distance from a source in a contaminated' area.

d. Wear protec tive clothing while in.a contaminated area

,

"

p. Increase shielding in an contaminated' area

Use respiratory protection

• ANSWER

.c.

(0,5)

,

o.

(0.5)

• REFERENCE CAF

• QNUM

• QDAT

'1989/09/06

• FAC 225

-*RTYP TEST l

• EXLV S

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- * SEC -

I

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• OUESTION MATCH the detector in COLUMN A with the appropriate-radiation

,

particle it is designed to measure in COLUMN B.

More than one response may be required.

COLUMN A COLUMN B

a.

G-M tube 1.

Fast neutrons b.

Cutie Pie 2.

Alpha c.

Gas filled (Argon & Methane) tube 3.

Low level beta-fields 4.

Thermal neutrons 5.

High gamma ~ fields 6.

Low level gamma fields

• ANSWER s

c.-

3 CO.3), 6 [0.5]

b.

~ 2-EOsR], 2 (0.51

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' 'L*0UESTION:

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CA/poin tisource (df; radioac tivity measur;i.ng;: 80f Red /hrsofl gammai radlation

-

F onWmeter hasibeen:ndetected.? f Assuming '100%sdetector ef ficiency.';forngam; at,_

-

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mai Jr:diation,- at WHAT - DISTANCE ((CHOOSE-lONE J below).Wrom! thelsoi. tree Twilliyotir?

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[-Oxposuretbe reduced toi20' Rem /hr?;

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,

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-10.i0.25-meters l

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c.M31 meters:

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4.';8 meters

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' b e '( 11. 0 ) -

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• REFERENCEl lInverseiSquare LawL

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,:1989/09/06-

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• QUESTION

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w

?Irf order for.~ an. individual to exceed.the lower 310CFR2Otwholeebody quarterl

...

,

,axposure limit,1WHAT THREE' criteria must be< met??

m

'

..,* ANSWER; 11.-Individual.'can not< exceed 3 Rem"in any-quarter

..

.

(0.5)

2.. Individual can not. exceed 5(N-18)<Remslifetime ' limit.

- ( 0. 5 ).;

3. Individual"s NRC-FORM 4 must be on file'

S( 01. 5 ) :

.* REFERENCE 10~CFR 20.101 1*END s

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'*QUESTIONEi

,

In accordanceLwithTthe Fuel Handling" Procedure kal'1-;fue1VhandlinglNillEbes l.l

'

?dccomplished underdthe supervision of thef

.' -> ( C H O O S E l O N E '. M ' <

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• af Operator-on duty v:

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ib.0Seniorlope'dtor;ontdutyi r

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,c.fHealthlPhysicisti

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fdp Radiation; Safety Off.icer?

-

Y'

-

e.;Resctor?Supervisorf

-* ANSWER

-

- ^ ^

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-

x b.:[1.O].

,

'

'

• REFERENCE

'

'

Oparating(Procedure,'FuelJHandling;

'

• QNUM-i

• QDAT-

1989/09/06

'

~*FAC'

225

,

+-

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TEST t

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L*SEC K-

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• KA L* QUESTION

'In accordance with the Fuel. Handling Procedure,'WHAT;must-be_.. performed byD.

'

fu21-handlers BEFORE proceeding-with a transfer?

'* ANSWER-

. Survey the area [0.SJ'and'the fuel [0.53

• REFERENCE

OpDrating Procedure, Fuel-Handling

• QNUM.

-*QDAT 1989/09/06

'

'*FAC 225

'*RTYP'

TEST

_.*EXLV S

• EXMNR SILK, D.

• QVALL 1 ~.~ O

• SEC K

q

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• KA'

• QUESTION

- Listed below. are core cocpu r'en,,

.

-

'1. Control rod basket

.

2.$ Carrier plate

.

3MControl rod: guide and' bushing

' 4WReactor) core sand reflector support plate

.

<

'.

,4-Sc Topfplatefundl grid assembly-

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.o f h;k h h E M $ h 2 n A s ik W N M -3 6 h E

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2,: 3,:4 b.--

da.

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3, 1,-5, 2,

d'-

L i', 2,= 5, 3, 4 --

.

o. : 2, ' T, / 1, S,. 4 '

• ANSWER-b.

[1.03

• REFERENCE-SER Fig 4.2

• 0NUM

• 0DAT 1989/09/06-

'*FAC 225=

.*RTYP-

TEST

• EXLV

'S 4EXMNR SILK, D.

a.

• GVAL 1.0

• SEC K

'*KA'

• QUESTION WHICH ONE of the fol' lowing is the ren'ctivity worth'of the FOUR. CONTROL RODS when removed as a. BANK?

a.

$0.41 b.

$1.00 c. $1.49 d.

$2.43 e.

$4.33

.

i

• ANSWER e.

[1.O]

• REFERENCE SER p 4-8

• GNUM

• QDAT 1989/09/06

• FAC 225

• RTYP TEST i

• EXLV S

• EXMNR SILK, D.

' j i

• QVAL 1.0

• SEC K

,

• KA

• CUESTION Fill in the blank below with DNE of the choices that follows.

>

During fuel loading if at any time the count rate on any channel all fueling opert-_

during a single fuel element additien ns will cease.

'

i

.a.

increase by more than two decades

.-

-b. increases by more than one-half decade c. decreases by more than one-half decade j

d.

increases by mora than 10 cps e. decreases by more than 10 cps f..shows no change

)

• ANSWER b.,(1.0)

-* REFERENCE

. Manual of Experiments for the Rensselaer Reactor Facility, p.

'*0NUM

>3 T,

oso/no/ __ ----

• aniW I Lb i -

'*EXLV-S

'

,*EXMNR

- Slut, = D.

• OVAL 1.0

'

'

'

'

• SEC K

• KA

'

40UESTION

' ~ When_ irradiating foils to perform a Reactor Power Calibration, WHY.are gold

= foils covered by'cedmium foils?' CHOOSE ONE response-from below-.

a. To stiield the gold from fast neutrons

,

b.

To shield:the gold from-thermal neutrons-c.

To have duplicate results of neutron activation d.

be able to dis tinguish between gamma and neutron activation e.

be able to distinguish between fast and thermal _ neutron activation

-*A WER e.

(1.0)

• REFERENCE Manual of Experiments,for the Rensselaer Reactor Facility, Ch 8, Relative Flux Mapping and Power Calibration

• DNUM l

• QDAT

'1989/09/06-

• FAC 22S

,j

• RTYP TEST l

• EXLV S-

• EXMNR SILK, D.

• OVAL 3.0

• SEC K

4KA

{

• OUESTION g

l Using the Inverse Multiplication Plots on the next_page, answer the l

following questions.

~

WHICH ONE plot best represents a condition in which the detector is too a.

close to the source?

b. WHICH ONE plot best represents a condition in-which-the' detector is too i

far from the source?

c. If three detectors are providing readings which result in 1/M plots 1,

and 3; WHICH detector would be used to predict criticality?

• ANSWER a.

2 (1.0)

,

I b.

1 (1,0)

i c.

1 (i.0)

• REFERENCE i'

Manual of Experiments for the Rensselaer Reactor Facility, Ch-3, Fig III-1

• 0NUM

' '

• ODAT 1989/09/06 i

• FAC 225

• RTYP-TEST

• EXLV S

• EXMNR SILK, D.

• OVAL 1.0

]

• SEC K

• KA

• QUESTION

'WHICH ONE of the following BEST states the purpose of the VOID / GAP REGION in the fuel pin?

a. Holds the fuel pellets in place I

b. Insulates the fuel from the cold moderator i

c. Accommodates fuel expansion d.:Is used to hold thermoccuplee to measure fuel temperature

.

'I q

c.- Collects fission product cases tn ho -nienend in s ---*

^1'

" -- --

,

.,

tw eg. 414n;-

3s

~

+ ~ ~ - + --

~

'

• REFERENCE.

'

. Conversion. f rom HEU nto LEU,Esec t %.1.13 : Fig 4.1

.

.

• QNUM

'

'

WODAT 1989/09/06

• FAC 225

• RTYP TEST-

• EXLV, S.

-*EXMNR SILK..D.-

'

• GVAL-1. 0

• SEC K

• KA

• OUESTION

'WHICH~ONE of the following1 statements regarding fuel loading'is.NOT-correct?

'

,

a.' Fuel additions will be' limited'to.one half-the difference between the

loaded mans and the extrapolated critical mass or to f our: stationary.

_

pins, whichever is highest.

=

l 6..Each fuelLpin.will be placed in a lattice position that vill

..

.,

preserve,-

R

_

xas:nearly as possible, a symmetric core

.

c. The number of. pins to be addedoat any given~ step can never exceed that

-

of the-previous step

.

.

)

d. After the' minimum critica1' mass is attained and until the coreLis. loaded'

i

.

.

to achieve desired response, fuel additions will be limited to one fuel j

e

=

pin

• ANSWER i

l

?

a.

(1.0)

• REFERENCE-i

'

Manual of Experiments for the Rensselaer Reactor Facility, Ch 3-

• GNUM i

• GDAT.

1989/09/06 i l

• FAC 225

.*RTYP TEST

• EXLV S

• EXMNR SILK, D.

• QVAL 2.0 e

• SEC K

[

• KA l

• QUESTION

<

'

While loading fuel in a new core configuration, a 1/M plot is being recorded, it is noted the the subcritical. multiplication-factor change-

-from 2.5 to 5.0.

HOW MUCH REACTIVITY was added to the core during the t

change in the subcritical multiplication factor?

SHOW ALL WORK AND STATE ALL ASSUMPTIONS.

,.

• ANSWER 1/M = 1 - Keff (0.5)

M1 = 2.5 = 1/(1 -K1) => K1 0.6 (0.5)

=

112 = 5. 0 = 1/ (1 - K2 ) => K2 = 0.8 (0.5)

i Delta rho = rho 2 - rhol (K2 - K1)/(K1K2) = 0.42 delta-k/K (0.5)

=

• REFERENCE Manual of Experiments for the Rensselaer Reactor' Facility, Ch 3, p.26

• 0NUM

• QDAT 1989/09/06

• FAC 225 i

• RTYF TEST y

• EXLV S

j

• EXMNR SILK,-0.

• OVAL 1.0

• SEC K

• KA

_._.__. _ __ __.l..-

..-.... -.

. -

Ev&us tn require. tne alrect? control' of the:

". (CHOOSE ONE )1 wu

.

, 'a. Radiation-Safety Officer b. Ch' airman of-the'NuclearfEngineer'ing?Departmentc

-

+c%' Director of RPI Critical-Facility d.1 Reactor Supervisor'

e.-Health Physicist

• ANSWER od.- [ 1. 0.] ~

• REFERENCE

'

j

'

Ogarating Procedure, Fuel Handling

'*QNUM'

• QDAT

'1989/09/06

.

-*FAC 225

!

• RTYP.

. TEST

.*EXLV S

{

• EXMNR SILK,'D;

• QVAL 2.5-

• SEC.

.K

4KA

• QUESTION

During. fuel loading, the reac tor is subcritical by -0.6667 delta k/R with=

an: inserted source contributing 1000 neutrons lper generation.

WHAT COUNTRATE is the detector seeing?'

a.

(1.0)-

i

i b~ Some' time later, fuel pin additions insert +0.50 delta R/k reactivity

.

to the core.

WHAT will be the resultinr COUNTRATE, and WHAT is the resulting value.of Keff?

1.5)

(

• ANSWER a.

Keff1 = 1/(1-rhol)

(0.25)

q

'

Keffl = 1/(1-(.6667)) = 0.60 (0.25)

CR = S/(1-Keff1)

(0.25)

=

CR = 1000/(1-0.6) = 2500' (0.25)

b. Rho 2 = -0.6667 + 0.50 = -0.1667 delta k/k ( 0. 5 )-

Keff2 = 1/(1-rho 2) = 1/(1-(-0.1667)) = 0.8571 (0.5)

i CR = 1000/(1-0.8571)

6998 (0.5)

=

• REFERENCE Equation Sheet i

Manual of Experiments for the Rensselaer Reactor Facility, Ch 3 40NUM

• QDAT 1989/09/06 j

!

• FAC 225

• RTYP

' TEST

• EXLV S

• EXMNR SILK, D.

]

• QVAL 1.0

• SEC K

• KA

• QUESTION 1WHICH ONE of the following statements is CORFuCT regarding the reactivity coefficients of the RPI reactor?

a. Doppler coefficient is positive over all operating temperatures

,

b.-Moderator temperature coefficient is positive over all operating temperatures i

'

c.

Moderator temperature coefficient is negative over all operating l

temperatures d. Doppler coefficient is positive between 50-and 100 F and negative.ebove 100 F

e. Moderator temperature coefficient is positive between 50 and 100 F.and negative above 100-F

• ANSWER.

_ _ _ _ _ _ _ _ _ _ _ _.....

..

.

.

.

.

.

_-_ - - _ _ _ _ _ _ _ _ _ -.

-. ' =* htF t:.HE.NLt:Jl

'

" - - ~ ~ - - ~ ~

--i - - -

--

- -*

v-,

- Conyersion'.from HEU'to:.EUo" sect 4.6,

-

• END,:

-,)

'

.,

,

.

• ,,

a

~.

!

' l

.

.j

i k

)

__-_---___-__-_----_-____:--___-_.__

_ -- _

. -

..

,

i,.

-

'

,

.

~

-

,-

.

'

.

_..

• .

~,]

• 0NUM

-[

-*GDAT 1989/09/'i6-j

• FAC-225

• RTYP TEST.

• EXLV S

• EXMNR.

SILK.

D.

• GVAL-1.0

• SEC L-

• KA

.*OUESTION Per the. RADIATION EMERGENCY PROCEDURE, WHO has authority to bypasscthe water dump and under.WHAT-condition can this be done?

.

• ANSWER-

'l Senior operator [0. 5) -if it is.determ.eed that water shielding is

.

y beneficial-[0.S]

l

• REFERENCE j

Emergency' Procedure p 12

l

• QNUM

-*GDAT 1989/09/06-

• FAC 225

• RTYP'

TEST

-

• EXLV S

• EXMNR SILK, D.

• QVAL

.1.0

!

'

• SEC L

'i x

.

-*KA

• OUESTION

'

SUBSTANTIVE' CHANGES to procedures required by. Technical Specifications i

shall be made only with the prior approval of the (CHOOSE ONE.)

.

a.

Operations Supervisor b.

Facility Director c.

Chairman of the NSRB d.

NSRB i

e e..

Radiation Safety Officer f.

NRC 4 ANSWER d.

[1.O]

.*"EFERENCE

)

TS 6.2

'

• QNUM

• QDAT 1989/09/06

• FAC 225

• RTYP TEST

-*EXLV S

• EXMNR SILK, D.

• QVAL 1.0

,

• SEC L

'

• KA

• OUESTION I

~ TEMPORARY NONSUBSTANTIVE CHANGEL to procedures

. approval of the may be made with the (CHOOSE-ONE.)

.

a.

Operations Supervisor t.;

The operator at the console-c.'

Facility Dirmct r

.

_.......

p gy%WT q/..

_

w 2_ 9 ' M_,..,.

,

,,~ J

. <:..

.%

y'

..

,

pO fp i'J,H;cT1:5tionJbatoty;Off1ctra

,,

-

-,

m :.

T e-#,

-

c.

<

,

,

i

~yG y..

- *, L: -

n*Ar q" o m

"

'

'

sfy [S::nio.r?dpWatori on'dutyg

~

'

,

s

,.

,4

.

q"_

e

,

,

4* ANSWER '

"

,.

'

^

,

1. 4

i. 'dW C'i.O]!,

,-

"M

_

,

,

'

-

'

'

<

'J ' > / *REFERENCEJ

-

'

'

'

' >>

-

(TST622;

'

>

'

'

>

'

'

* QNUM

,

-

y

-

, -'

'

qt*QDATJ 1989/09/06-

<

-

>*FACJ J25.

+

y

'

-*RTYP TEST;

'

'?

F*EXLV;

-S:

..

-*

'k

$

3EXMNRi SILR4-LD.

'

lt '

'

'

• QVAL'

-2.O I'

'

"

'

/*SEC:

.a -*KA" '

'L- -

'

'

~

,

,

'

>

" -* QUESTION.

-

.~

~

d,M

'

.Whilef-the/reactorfis operatingfa' safety Elimif dio'lationdoccbhd.: JWHAT:'

'

'

ACTIONS, both4.immediate and: subsequent,

'

l*ANSWERl

'

'

' shall?be performed?j

,

y

' '

-11D LShutdown!the reactor [

s N

u.::- ?.2 P- ; Noti f y"RCF. man agemen t?

,

13.

Nc' tit y NRC

,

.

f;4.. :~ Prepare.'a saf etyylimitiviol'ation ' reporti

. [025;(p'ts L eac h 3[

j

• REFERENCE

'rS 6.4.1-

'

-*QNUM'

'i

<

• QDAT--

1989/09/06!

,

..FAC-225

• RTYP 1 TEST

.' EXLV S~

'*EXMNR SILK.

D.

• QVAL 2.0

• SEC'

L

'

• KA 1* QUESTION-JAftnr completing work on a control-rod drive 3 f a5 tec!hnicianL asksNhe[ Senior -

Operator for permission to use rod. control'-tol MOVE the rod =,to4 ftest?.thefwork iwhich-had just'been completed.

EXF' LAIN -WHY; or' WHYeNOT :this(request 1 cant be igranted.

.

• ANSWER l

Thm, request should be denied [0.SJ - because ' coly. licensed iridividun1h [0.5]I or individuals in training under the supervisionE.of;ai; licensed 1operatori

-[0.5] are allowed to manipulate the' controls!that{af. fact!the reactivity.of s

the: core [0.5].

• REFERENCE io CFR 55.4, 13

• QNUM h

• QDAT 1989/09/06.

'd

'*FAC 225

• RTYP TEST

'

• EXLV S

• EXMNR SILK,,D.

• QVAL~

'

1.0.

-*SEC L

)

'

.c

• KA

• QUESTION-WHAT -is the SAFETY LIMIT for the_RPI reactor?

~

.

M.'"I3S watts b.~270 watts 3"

ic. 200-kilowett-hours. integrated power over one year b

d 5Less than a five second period

a.900

Cl11uel temperature a

ifJ.J20004C fuel ~ temperature ~

J yptigpl

~'

'

'

g;;

_

.

y "p n., ;

-

.

n,

--

7n..

-,

y hkbl* thclbtL

"

'

~

.

r iTCchTCpec c},

,s

.

(

' \\d

~ J.;

Ih

%O c t'.J 2; 1t

-

<

J

'

>

'

'

,

-

g

,--*QNUMT <,

, _

'

,

"

'

'

'

'

'

,

_.

-

o*QDATI s1989/09/061 t

-

>

^* FACE-223r

'

a- -

'

,,

.

,

s (*RTYP1" TESTe

-

4-b*EXLV:

.S

j

'v

4 EXMNR-SILK, D.:

's

-

'

"'

r * avgL'

(1,o:

-

'

~

>

M

'*SEC

L

' '

'

'tKA-

'

__ "J*OUESTION'

i.

R A

WHICH ONE.of.the following.is:)thef MINIMUM - OPERAT ING ' TEMPEFIATUNE?!

l

'

-

T. : 35. F -

_ l

'

.

_

yif

'

'

'

t b.iiSO 'F.

'

<

q

.

'

c.-SO.C v

<

'

-

>

d.'100 F'

-

'

,

'

'

'I e.H1354FL

-

,

,

,* ANSWER.

,

'

yb. :y ( 1 ~. 0) 1 s

'

'

(* REFERENCE:-

4:

i

'

" Tech: Spec 3.2, p 3-4-

,

+

• 0NUM

.

,

,

-*QDAT 1989/09/06

~

'.

'

.*FAC 2L

'

- :*RTYP

TEST

• EXLV S'

.i

.*EXMNR SILK, D.

,

<

• OVAL'

.1,O

• SEC L

.

l'

• KA u

1 QUESTION LListed

.

..

.

-

below are several Technical: Specification requiredisurveillances.-

-Iacluded with the surveillances are the,specified surveillance:. frequencies

,

with the dates of the'_~1ast two ~ survei'l lances.: :It is tosbe; assumed;that the-reactor-has!been operated between the surveillance; dates.a

_

1.

Radiation' Monitors 11/13/89 and.12/15/89-(Tested monthly)

y 2. -. Control rod drop time 5/5/89 and.11/9/89 (Measured semi-annually)

3.

Safety system channel 12/1/88 and 12/5/89

'

(Calibrated annually)

,

'

"

4.

Safety system channel 1/5/90'and 1/10/90'

(Test daily)

,

WHICH ONE statement below is CORRECT-as it relates to the information prasented above?

'There are NO tolerances permitted -in missing a ':.urveillance dhte-c.'

b.-

ALL-the above are: reportable occurrences

.

q 3 and 4 are VIOLATIONS-of Tech Specs because they involve = safety.

c.-

channels d.

ONLY 4 is a VIOLATION of Tech Specs s.

ALL the above are PERMITTED by Tech Specs

})

NONE of the above

~.* ANSWER-j

'

> d.,,(1. 0 ) -

.

j,1 F

• REFERENCE jTec h tl Spec 'see t. - 1. 0,;.p,1-3 )

.)TCch Spec 5 sect.c4.O!

..-

}

,

.

'

, :. Mg,,,g

-..

.

MK

.

~

• u

~ ~ -

'>'

-

-

• FAC 225

• RTYP!.

' TEST

• pXLV.

S

.

.

'

• EXMNRl cSILK, D.

• QVAL i.0 4SEC-L

-*KA

• OUESTION WHICH ONE, 11 any. of t'he followingLevents can be performed and the reactor would still be considered SECURED?

'

a.

A control rod is being inspected for wear b.

Eight-fuel pins are. symmetrically added to the' core c.

The contents of the reactor storage tank are discharged to_the river T

d.

The nuclear instrumentations are under acing their' regular surveillance e.

None of the above-

,'I

• ANSWER c.'(i.0)

• REFERENCE RPI Tech Spec sect 1.O

• QNUM

• GDAT 1989/09/06'

i

• FAC 225'

• RTYP TEST i

I

• EXLV S

• EXMNR SILI.

D.

• OVAL 1.5

• SEC L

• KA j

• QUESTION

As defined in Tecnnical-Specifications, LIST THREE conditions, besides

'(

those related to SAFETY LIMITS or LCOs, thet are considered Reportable Occurrences.

• ANSWER 1. Unplanned or uncontrolled radiation release from-restricted area 2.

Safety system component failure 3. Degradation of a fission product barrier 4. Uncontrolled or unanticipated change in reactivity greater than $0.70

_

S. Natural or man-made event that affects or threatens to affect safe operation 6. Inadequate controls that could lead to unsafe conditions

[Any three, 0.5 pts each]

-* REFERENCE TS Section 1.0

• 0NUM

• 0DAT 1989/09/06

• FAC 225

• RTYP TEST

• EXL V S

.*EXMNR SILK, D.

• QVAL 1.0

• SEC L

• KA

• GUESTION In accordance with Technical Specification Table i the reactor door SCRAM may be bypassed during maintenance checks and radiation surveys with the specific permission of the Operations Supervisor provided that (CHOOSE ONE.)

.

a.

reactor power is less than 0.01 watts

.

-

_

.

,.

.

..

w_

e mmq m;.V M..x:.s

,-.

gy%!iUR* n;,TtttgrF SCHAM; ch nnbic56raibypendd 7 71..,_.....

%,

W

'

zy

-

,.4

. Und"%

.

..,,.

~

,

-

m*

fj

% /M thesnrutron courem bw binnt rotrce tOd ?intofito: contdinar;7

'

'

• ANSWER w" jd N i l. O') P...

-

a

N

+<

'

[

~

<,

.

,

,

.

E,*BEF.ERENCEL

.-

.,

V {TJS WTable 1<

,

' , 1. s w..

~

g(*QNUMa

.

.

.

,

~ J tODAT/.e

'1989/09/064 J

>

- E*FAC'

22S

~

> *RTYP; LTEST

~

<

I d*EXLVO.

'\\S

~

~

'

s

-*EXMNR:

LSILK.Ee

<

'

" QVAL?

1.04 i

'

-k:,5EC-L'

a

'

c*KA:

,

' - '* QUESTION-

'

'

j;Accordingl to(Technical Specifications,.~a REACTOR SCRAhl'is)tiest' defined: ast

.

(CHOOSE.ONE.).

~

.c

ta. Ful1[innertion-:of the~ control rodsi

,

.

'

j' - b.? Control; rods ~ are inserted / and theireactorhis Estiutdowrk dyla tfl ess t.1~.'00.$..

'

ck:AL gravit,Cdrop 1of :the. contro11 rods accompariied ;'ay Jthe)c'pening of.q the;

~

p (modebatt,r dum'p! valve '

a-

'

'

'

,

d.1A reactor.: shutdown due:

.

,

<

'

,

c4 ANSWER-~ ~

Lto laLloss'of A.C.

power 1to?thetfacility-

.

^

-x

'

i-l c', L( 1, o ),

-

/

i <

'

• REFERENCEL

'

'

s

-

T.S.!p.'?1l-2-

-

.:

.. * 0NUM L i4GDAT'

1989/09/06

• FAC

22SL

• RTYP-4 TEST S

• EXLV

'S

• RXMNR:

" SILK, D.

,

1*UVAL'

.1.O.

~*SEC.

.L'

• KA.

?OUESTION-

' Contaminated moderator'(a Category I event) has.beenJdiscovered;- WHICH'ONE-of.' the41ollowing orgeni::ations is to be contacted FIRST? ~

-

a.'NRC b.

DOE

'

c..

ANf d. NYS Bureau of Rad. Hea'lth o. FBI

-*ANOWER

- d i: (t.0).

!* REFERENCE

'

Em:irgenc'y Prorsdure pp. 17, 18

'*QNUM

-*ODAT-1989/09/06 w

• FAC:

225-

..l

• RTYPJ TEST

• EXLV S

• EXMNR.

SILK, D.

- *QVAL:

l '. 0 :

• SEC L

-

i'

• KA

'* QUESTION-6WHICH~cif any, of the following statements is NOT TRUE regarding~.the RPI!

,

1 EMERGENCY;-PLAN 7'

-

<v.

c 1c. 5The Jintrusion Ealarmitor thef f acility. alarms ~ at ',the1 GE Nott St. guardt

.

-

i m

-

-

.

.,

_

v ag m$g 3,

,

,

.

y_

g

.

_ -,;,,, y.

%(.wQs i3Q D)O;med icato ( by } thf F,ccilit;yj Supgrv%VG,%.

...

_.

3,

.

-k>

.~.

.. - --g

..&, _.7Minaea m.s w...csu N a,. ^v > w

.

.,..

~

'

n dfi.

-..,

-%

s

?

.

icor,.

'L >-

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'* REFERENCE

' Emergency Plan-

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a. -- Emergericy Ac tioni Level s-~

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Emergency! Classes =

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c.

Emergency' Plan '

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t i'. Documented instructions >that'detai1[.the:implementa6 ion!' actions 1and.

methods ' required - to, achieve - the :obj ectivesiof Jthe 7 emergency" plans J

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that provides-the basis for actions:to'Lcopejwit;hian-

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. emergency. 4It outlines the : objectives to be cmet by.theEemergencyf proce 6 os and defines.the< authority and responsibilities to achiev'e-;

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t 3. Accident groupinge by severity level.for which.predeterminedJemergencyc d

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'4. Specific instrument readings,.or observations; radiologicalfdose or"-dose rates; or specific contamination'; levels oftairborne,...or-

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r surf ace-deposited 'r adioact z' e materials-tha t may lbe used as.itr r e< aolds

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for establishing' emergency classes andlinitiating; appropriate; emergency q

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A condition'that calls for immediate actione beyond)the; scope'of normal.

r operating procedures, to avoid an accident or.toimitigate the

consequences of-one 6; Area for which offsite emergency planning is.performedito assure that, prompt and effective actions can be taken to protect the.publ-ic.in the

'I event of an accident.

The area depends on the. distance'beyond/the site

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boundary at.which the Protective Action Guide (PAG) could:be exceeded i

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P = (reV)/(3 x 1010)

I d) 2,2 2 gd g

2 g = oN R/hr = (0.5 CE)/d (meters)

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R/hr = 6 CE/d2 (feet)

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Water Parameters Miscellaneous Conversions-1 gal. = 8.345 ibe.-

1 curie = 3.7'x 1010dps 1 ga1. = 3.78 liters 1 kg = 2.21 lba

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1 ft+ = 7.48 gal.

I hp'= 2.54 x 1 Btu /hr Density = 62.4 lbs/ft3 1 mm = 3.41 x 1 Stu/hr-

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Heat of vaporiration = 970.Stu/10m

• F = 9/5'C + 32 Heat'.of fusion = 144 Stu/lbe

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1 Atm = 14.7 psi'= h.

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