ML20247K995

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Errata to Exam Repts 50-498/OL-89-02 & 50-499/OL-89-02, Consisting of Master Exam & Answer Key & Facility Exam Review Comments
ML20247K995
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 05/22/1989
From:
NRC
To:
Shared Package
ML20247K994 List:
References
50-498-OL-89-02, 50-498-OL-89-2, 50-499-OL-89-02, 50-499-OL-89-2, NUDOCS 8906020066
Download: ML20247K995 (54)
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F a

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S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 4

FACILITY:

Sggib_Igsgg_1Jgd_1_______

REACTOR TYPE:

EWB-WEQa_________________

DATE ADMINISTERED:

QQ4Dd4Qh_________________

IU118UQIl0NE_IQ.QaNQ1QaIE1 Uae separate' paper for the answers.

Write answers on one side only.

Staple question sheet on top of the answer sheets.

Points for each question are indicated in parentheses after the questien.

The passing grade requires at least 70% in each category and a final grade of at least 80%.

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

% OF CATEGORY

% OF CANDIDATE'S CATEGORY

__VaLUE_ _IDIaL

___EQQBE___

_VaLUE__ ______________GaIEQQBI_____________

_21100__ _25tDa

________ 1.

REACTOR PRINCIPLES (7%)

THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)

._2ZzQQ__ _2ZtQQ

________ 2.

EMERGENCY AND ABNORMAL PLANT CVOLUTIONS (27%)

_dQtQQ__ _dQ&QQ

________ 3.

PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)

_1DQuQ__

TOTALS FINAL GRADE All work done on this examination is my own.

I have neither given nor received aid.

I Candidate's Signature q

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NRC RULES AND GUIDELINES'FOR LICENSE EXAMINATIONS

During the administration of this examination the following rules apply.

.1..

Cheating-on the examination meens an automatic denial of your application and could result in more severe penalties.

l2..

Restroom trips are to'be limited and only one candidate at.a time may

' leave. -You must avoid all contacts with'anyone outside the examination room to avoid.even the appearance or Possibility of cheating.

l 13.

Use black ink or dark'p-

il only to facilitate legible reproductions.

~4.-

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

' 5..

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

.6.

'Use only the paper provided for answers.

7+

Print your name in the upper right-hand corner of the first page of.each section of'the answer sheet.

8.

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

9.

Number each answer as to category and number, for example, 1.4, 6.3.

110. Skip at least three lines between each answer.

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

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

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
15. Partial credit may be given.

Therefore, ANSWER AlL PARTS OF THE

)

DUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

1 If' parts of the examination are not clear as to intent, ask questions of I

16 '.

the examiner only.

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

completing the examination.

This must be done after the examination has l

been completed.

0 1

1 1

3

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iBo When.you complete your examination'you shall

'a, Assemble your examination as follows!

(1)

Exam questions:on top.

(2)

Exam aids - figures, tables, etc.

I (3)

. Answer pages'includin3.fi Sures which are part of-the~ answer.

~b.

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

I the examination questions.

'c. ' Turn in.-all' scrap paper and the balance of the. paper that you did-not use for answering the questions.

e F

d.

Leave the examination area, as' defined by the examiner.

If after leaving,.you are found in this 9tes while the examination is still

,in progresse,your license may La denied or revoked.

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fDUESTION-

'1. 01 '

(1.00)-

- t

-Whichsone of the following terms'is defined as the. fractional change in-neutron population from one generation to the next?

.a.-

delta K h

I Reactivity b.

c '. -

1/Keff

'd. -

.Keff

'0UESTI'ON 1 02-(1.00)'

.What two (2) characteristics of Xe-135 result in it bains a significant

' fission product poison?

(1.0)-

QUESTION.

1.03 (1.00)

J Which'one (1)Hof.the following statements concerning the power defect is correct?

(1.0) i a.

The power defect is the difference between the measured power coefficient and the predicted power coefficient.

b.

~The power. defect is more negative at the beginning of core life due to the higher concentration of boron.

,c.

The power defect increases the rod worth requirements necessary to maintain the desired shutdown margin following a reactor trip.

[

d.

The power d'efect necessitates the use of a ramped Tave program to l

maintain an adequate RCS subcooling margin.

I QUESTION 1.04 (1.50)

The overali power coefficient is a combination of three coefficients.

List these three-(3) coefficients in order from the largest to the smallest L

contributor.

Assume beginning of life.

(1.50) 1' i

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l0UESTION:

1 ~. 0 5 (0.50)-

,The decay heat seneration rate immediately followins a; reactor trip from

extende'd full: Power oper.ation -is approximately _______ of, rated' thermal'
power.;(Fill in the: blank with.the one correctJanswer below.')

(0.5)

L

.a.

10. 7 % -

b.

l '. 0 % -

4[

^

' 6. 0 %.

c.

d.

.14.0%

4 QUESTION-1.06 (1.00)

JGuadrant'PowerfTilt-Ratio (GPTR) is defined as aL. -

'The ratio of the. maximum upper (lower) detector normalized. current'to

- ?he avera'se of the upper (lower) detector normalized currents, whichever is larger.

b. --

The ratio of the upper detector normalizeo current minus the bottoa detector normalized current to_the upper detector normalized current H

plus the lower detector normalized current.

c

.The ratio of the top detector current to its 100 percent equivalent-current'plus the ratio of the bottom detector current to its 100 percent ~ equivalent current.

'i

?

Jd.

The ratio of the top detector current to its 100 percent equivalent l

current minus the ratio of the bottom detector current to its 100 percent equivalent current.

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00ESTION.

'1 07 (1.00)

Which one of1the following. describes a reason fo'r.the height correction factor', K(z)i used in?the heat' flux hot channel factor, F-0 (z)?

(1 0) a'. -

'K(z) compensates for the increased. coolant. temperatures that occur. in Lthe upper half of the coolant channels.

b.

'K(z).is.an. Uncertainty factor:that takes into account both experimental error-and manufacturing tolerances.

c.-

K( ) allows for' greater power-production in the upper-regions of the core near the end of life due to axial flux chiftins.

~

d.-

-K(z)' takes'into account that there is some resistance,toarefillins the core completely f.o'11owing a small break LOCA.

-QUESTION 1.08 (1.00)

What'areJthree-(3) conditions which must exist for brittle fracture to occur?

(1.0)

'0UESTION.

1.09 (2.00)'

Using the information'below, CALCULATE' total reactor thermal power in MW.

j Show all your. work.

(2.0)

Total feedwater flow to all steam sencrators is 15.0'E 6 lbm/hr.

The enthalpy of the feedwater entering the steam senerators is 350 Stu/lbm.

SSteam exits the steam senerators as a saturated vapor ~at 985 psis.. Assume the. net heat sained.from non-reactor sources is neglisible.

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GUESTION

.1.10

-( 1. 0 0 ) '

l

' Choose the correct order of the'b' oiling phasesilisted below as,.they would

occur l:in a: coolant' channel with normal-flow and.high. heat flux.

(1.0) c 1.

. transition boiling 127-

.bulkJboiling

'3..

Lfilm' boiling 4..

local! boiling.

I a t.

2,,4,-3r 1

, b.-

2,1'4,T1, 3'

,;c..

4,'c2,':3,-1 d.

'4,'2,(1,,3 1.11'

'(1.00)

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QUESTION.

Which ONE:of1theifo11owing actions or occurrences will increase'the likelihood c6 water-hammer in a fluid system?

(1.0)-

's.

Maintaining the discharge line from an auto starting pump filled'with fluid'

,b.-

Water collecting in a steam line e.

Pre-warming of the steam lines d.

Slowly' closing the discharge valve of an operating pump

'1

. QUESTION'

'1.12

-(1.00)

'For steam.(at 1000 psia) going through a throttling process, which ONE of the'following parameters will remain the same?

Assume ideal conditions.

a..

Enthalpy b.

~ Pressure c.

Entropy-d+

. Temperature i

-c

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!GUESTION 1.13 (1.00)

[h:

HowIwillLRCS loop' hot leg temperature indication be affected if the.

7.,

associated resistance temperature detector (RTD).becomes: open-circuited?

1.

f'.

L a.

-Hot-les' temperature indication will be equal to' actual hot.les' l

temperature..

L f.

b.

Hot les temperature indication will fail-as is.

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c..

Hot les temperature indication will be higher than actual hot leg b

temperature.

~d..

Hot 1les temperature. indication will be lower than~ actual' hot les

. temperature.

GUESTION 1.14 (1.00)

The. plant is operating at 30 percent load during a load ramp to full power.

If steam' flow density compensation fails at its 30 percent load value,

~

which Ot1E of theLfollowing describes the affected steam flow indication

  • l' when.at full power?

L a.

Indicated' steam flow is greater than 100%.

l l b '..

Indicated steam flow is greater than 30% but less th n 100%.

-c.

Indicated steam flow is equal to 10Q%.

d.

Indicated steam flow is equal to 30%.

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LOUESTION 1.15 L(1'.00)

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SA; centrifugal'. charging pump isyrunning with the discharge flow. control

[

lvalvefin mid posit' ion.

If the. discharge valve'lis' fully openede.'which one.

l y

'ofEthe1fc110 wins' statements correctly describes'the changes in:the,ligted

~

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-parameters?

8 La.<

.Di-scharge flow, motor ampsr.and available NPSH touthe pump'will

-increase.

v.

'b.

. Discharge flow will increase,1 motor amps and available'NPSH.to the-

.3 pump...willfdecrease.

c.

' Discharge > flow =and~' motor amps will decreaser available' NPSH 'tcr the 1

pump will:-increase.

id.

. Discharge flow,and motor' amps will increaser available NPSH to the

.l

. pump will. decrease.

i

0UESTION 1.16 (1.00)'

1 t

'Aicorrect' statement regarding pump runout. conditions for a motor driven centrifugal Pump is that:

ca.

'The system' backpressure is greater than the pump inlet pressure and

' fluid flows thr" ugh the pump without absorbing eriergy.

I b.

Current-through the pump motor increases to oppose the flow' induced I

increase'in shaft speed.

c.a

? Damage to the pump and motor are unlikely since they are designed to

. operate.without failure under pump runout conditions.

E d '..

.The potential for pump runout is minimized by ensuring that sufficient I

net positive suction head exists.

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2 1

f GUESTI'ON-

' 1 '.17 (1.00)'

cWhichistatement-below' describes the reason'for the, anti-reverse'. rotation 1

device.on-the' Reactor.. Coolant Pumps?-

ja.

, Prevents' DND' by"increasirig pump coastdown time in'the event ofLa loss-of power.

. bi..Preverits. mechanical' damage to the; pump' seal package.due to. reverse

l rotation of the pump.-

.c.-

Enhances >the establishment of natural circulation by preventing

, reverse flow in;the loop 1following a station blackout.

d..

Prevents-overheating'of the pump motor;in.the event ~of.a pump start 3

withLreverse flow inLthe-loop..

Hl

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f0UESTION 1.18 (1.00'

-Feedwater flow and1 pressurizer level detectors use differential p'ressure:

. hich' (D/P) cells to measure flow and'1evel.

If a D/P cell diaphram fails, w

one ofLthe following statements is correct?

i

a.

' Level indication.will indicate 100% (full range), flow indication wills indicate 0%-

'b. -

Level indication will indicate 0%, flow indication will indicate 100%

(full range)

'cF..

Level and flow indication will indicate 100% (full range) f Ed.

Level and flow indication will indicate 0%

GUESTION-1.19 (1.00)

.What is'the purpose of the loop seals upstream of the pressurizer safetyivalves AND how do they accomplish this purpose?

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'GUESTION

.l i 2 0' (1.00)

An,' increase iin circulating water flow through the main; condenser may cause l

_a' DECREASE.in overall plant efficitney.by:

~ 't :

a.

' Increasing condenser vacuum b '.

Decreasing condenser vacuum c.-

' Increasing condensate depression

-d.

.D'ecreasing condensate depression QUESTION.

1.21:

(1.00)

HowLdoes the'rackout interlock on a breaker function to prevent personnel I

injury. or equipmentLdamage?

(1.0)

' GUESTION:

1.22 (1.00)

A caution in 1 POP 02-CV-0004, Chemical and Volume Control Subsystem, states

'that care should be exercised when placing the mixed bed demineralizers in service to prevent unanticipated reactivity changes.

How could such a reactivity change occur.

(1.0)

QUESTION 1.23 (1.00)

Why is the number of starts for larde motors during a given time period limited and what causes this conce.n?

(1.0) 00ESTION 1.24 (1.00)

Why is the startup rate (SUR), after the initial prompt drope limited to

-1/3 decade per minute after-a reactor trip?

(A numerical proof is not required.)

(1.0) l i

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[ QUESTION'-

2.01

'(2.00)

=a..

In accordance with OPOPO4-RS-0001, STUCK,0R DROPPED CONTROL R0D, what are two---(2) different methods for recovering from a misaligned rod?

.(Aidetail'ed description of how each method is accomplished IS NOT r e a v i t e d,' )

(1.0).

b.:

Whac are two (2) criteria fer determining'which methoduis.used?

'(1.0)

. QUES 1 ION.

2.02 (1.50)

'What three'(3) automatic' actions will occur as a direct result of lowering icondenser. Vacuum?E(Include any applicable setpoint' values)

(1.50)

',0UESTION' 2'03-(2.00)

LAs'ume? steady scate' operation and the pressurizer spray valve has just s

opened at'100% power when.the Pressurizer Pressure Master Controller

,setpoint is inadvertently changed to 2370 psis.

Assume a step change in the setpoint and assume that pressurizer' pressure control remains in automatic.-

a.'

Which.ONE~of the following describes the automatic actions that will.

occur immediately?

(1.0) 1.

Power Operated Relief Valve PCV-655A opens, spray valves open, pressurizer heaters de-enersize.

2.

Spray valves open,-pressurizer heaters energize.

~

3.

. Spray valves close, pressurizer heaters energize.

4.

Power. Operated Relief Valves PCV-655A and PCV-656A open, spray valves open, pressurizer heaters energize.

b.

. Describe the pressurizer pressure transient that will occur'if no

. operator action is takeri.

Include in your answer any other automatic actions, besides alarm / annunciator actuations, that take place.

(1.0)

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QUESTION' 2.04 (1'50) i,.

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-CCW Surge Tank; level-is decreasing due to a leak.in the CCW system.

l

'Which ONE of the following indicates the two (2) surge tank levels at-

'whichLautomatic valve-closubes occur in.an attempt tc isolate the

. leak?

(.75) l83%'and 67%.

.1. '

. 2.;

63%iand~60%

3.-

72% and 67%;

'4..

L49% and :10%

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b-

..b.--

If theLsurge' tank. level continues to decrease fo11'owing the first I

valve.: isolation setpoint but stops decreasing following the second valve 'isolstion setpoint"r 'which ONE of the following components should

'beychecked-for leaks?

(.75) 1~

Boron Recycle' Evaporator L 2.-:

Spent Fuel Pool Heat Exchanger

.3.

Seal: Water Heat Exchanger 4.

Excess Letdown Heat Exchanger 1

{

GUESTION' 2.05 (2.50) h a.-

According to 1 POP 05-EO-E020, FAULTED STEAM GENERATOR ISOLATION, what lf

'are two (2) symptoms (conditions) that identify a faulted steam I.=

senerator?

(1.0)

L I

b.

If Steam Generator 1D is determined to be faulted, what are six (6) actions taken or verifications made to isolate the faulted SG? (Assume that the MSIV and bypass valve have already been shut.)

(1.5) 1 l

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_gdgRGENCY1AND'ABNORMALLPLANT. EVOLUTIONS'

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-i QUESTION

'2 '. 0 6 ?

. (1.50)

I m

,11PO.F:05-EO-FRCli RESPONSE TO INADEQUATE 1 CORE COOLINGi directs thecoperator-

to'depressurize all intact steam. generators after' attempts t'o'reinitiate.

Esafety; injection are ineffective.in restoring adequate core cooling.-

a.

Mhat.are two ' (2) ways..in.'whichidepressurizing2all intact steam generatorscwill improve core cooling?-

(1.0) l b.

Explain!why the-steam' generators-should NOT be depressurized below

'308 psi's.

(.5)-

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f 00ESTION:-

2.07-(1.00)'

L.

.l'Hetchfeach class of--fire listed below with.the extinguishing agent or

~ 1 agents that1should be used onsthat class of-fire.

(Agents may be.used'.

W. ore.than.once.).

(1.0)'

L CLASS OFfFIRE.

AGENT

'1 a.

. Class A 1+

Water L

b.

. Class'B-2.

Dry Chemical l

'c.

Class C 3.

Ca'rbon Dioxide

'0UESTION' 2.08 (1.00)

~ Match each-of the actions listed below wi^.h the corresponding Instrument Air pressure at which'each action occurs or should begin in accordance with

-1POPO4-IA-0001, LOSS OF INSTRUMENT AIR.

Assume instrument air pressure is decreasing and cannot be stopped.

(1.0)

~

. ACTION INSTRUMENT AIR PRESSURE-

's.

-Trip the reactor 1.

70 psis 2.

75 psis b.

Backup instrument air compressor 3.

80 psig

. star.ts and loads 4.

90 psig

]

5.

100 psis

-c.

. Commence a unit shutdown 6.

110 psis d.

. Service air _ system / Instrument air system crossover valve (IA-PV-8559) opens

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100ESTION 2.09-(l'00)

U pt (Hith the pressurizer level control selector switch'in'the'CH.:465 position,-

' choose.the ONE' statement;below'that'cott'ect,1y.describesLsystem-response to-1 L

Pressurizer Level. Transmitter 465 f.iling low?

Plant.ir -t;100% with.all

' ; systems /in automatic and no operator action.is-taken.

f( 1. 0 ),

L

.A11Lopen;1etdown orifice 1; isolation valves. closer'both letdown k

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s

. isolation valves'(LCV-465 and.LCV-468)' closer charging flow goes'to maximum flow rateifpressurizer heaters de-energize.,

o I

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!All'.open letdown orifice isolation valves close, letdown isolati'on l

' valve LCV-465 closes, charging flow goes to maximum rate,; pressurizer L

'heatersLde-energize.

c.. ;

lAll.open. letdown-orifice isolation. valves remai'n oPen, letdown isolationDLCV-465 closes, ' charging flow decreases, pressurizer heaters li

'de-energize,

'd.:

lAll-open letdown orifice isolation valves remain.open,-letdown isolation valves (LCV-465 and LCV-466) remain open,-charging flow

. increases,. pressurizer variable heaters.de-energize.'

GUESTION-2.10 (1.00)

In'the event.of'an uncontrolled RCCA bank withdrawal from suberiticality, which ONE of the.following will terminate the fast power rise associated with'this accident?

(1.0)

I a'.

. Moderator' ten.perature coefficient

l. b '.

' Pressure coefficient

.c.

Void. coefficient a

d.

Doppler coefficient

-QUESTION 2.11 (1.00) l f

A Primar'y to secondary leak exists in a steam generator.

What are four (4)

[

indicat-ions used to-determine which of the steam generators is affected?

E (1.0) l

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'FOUESTION: ~2312 (2.50) l Answer 1the followingJg'vestions. as they : apply ~ to 1 POP 05-CO-FRS1,: RESPONSE TO s

JNUCLEAR: POWER GENERATION /ATWS.

q

.a.)

After the: operator has; verified a. reactor trip, he is'tiirected to Everify a_.turbineLtrip.7,Why is the turbine tripped?

(1.0)~

i b '..

If the-'. turbine does not/ trip automatically.and cannot be-tripped'from
t h e
M C B e r w h a t.t h r e e !.( 3 ).. options (contingency actions)'are.available:to the operator perr1P0P05-EO-FRS1?

(1.5')'

.GUESTION

~2.13 '

(1.50).

For..eachiof the following process and effluent radiation monitors,' state'

- the automatic actions which will occur due.to a high'rediation condition-in othattsystem.g'(Do'not include alarms or< annunciators).

If no, automatic

-actionsLoccur, state.this in'your answer. (A' detailed. description oftfans.

s

.thatistartfor stoplor' dampers'that open or.close is not required.)

. ( 1. 5 ).

!a..

RT-8012.

LRCB Purge Exhaust'

~

b./

RT-8027

~.CondenserLVacuum. Pump c.-

RT-8038 Liquid, Waste' Processing System Discharge d.

RT-8043 5 team Generator Blowdown Demineralized Outlet l

'e. -

RT-8040 CCW Pump Discharge

-f..

RT-8035 FHB Exhaust L

1 I

L..

(*****.

CATEGORY.

2 CONTINUED ON NEXT PAGE

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. h O'UESTIO'Ni 2'.14 -

'(1'.00) 3',

a Intermediate' Range (IR) compensating voltage fails low for.one of the IR

  • -detectors.

The. reactor subsequently trips,..d u e to otherreauses, but':the IR ;

JA< cureent'.on.the f ailed detector does not so below 5 E--5 -amps.

s LWhich one ofotheifollowing-describes how the operator will monitor' reactor.-

,.7 A

power throughtthe' Source Range?

.( 1. 0 )

a Once'the.non-failed IR.-detector decreases to less than 1LE-10 ampsel

~

a '...

the Source Range'Hanual Reset.pushbuttons will be'used'to manually re-energize.the. source range detectors.

b..

C ice the non-f ailed IR detector decreases to.less tharF1 E-10. amps, the. failed 4IR-detector will be bypassed allowing the source range.

' detectors.'to energize..

c;.

'Once the non-failed'IR detector decreases to less than 1 E-10 amps, P-6 wil.1 be unblocked and the source range detectors will j

' automatically re-enersize.

l f d '. -

Oncelthe non-failed detector decreases.to less than 1;E-10 amps, one t

s'ource= range, detector.will automatically re-energize and'the other s

will be manually re-energized using the Reset pushbutton.

I L

LGUESTION 2.15 (2.50)'

2

> La..

According to.1 POP 05 EO-F010, LOSS OF REACTOR OR SECONDARY COOLANT, I?

Twhen should1.the following events occur?

(1.0) 1.:

Transfer to Cold Les Recirculation-following a LOCA 2.

Preparations begin for Hot Les Recirculation l-3.-

. Transfer to Hot Les Recirculation following a LOCA k

b.-

List three-(3) reasons why Hot Les Recirculation is used subsequent to l

's.:LOCA.

(1:5) l l

-(*****

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          • )

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(1223L I

b, b

00ESTION 2.16' (2.50);

?

r l.

' Unit 1 is in: cold. shutdown.and.the~RCS is'being' drained for mid-loop operation.'

!a..

Whit are'two (2) ' indications that:the RHR pump is cavitating?-

(0.5)

(

b..

Ifithe RHR pump. trips on.. low flow, what must the level in the reactor.

be. Prior to starting.the standby pump?

(0.5)>

L f

Ec.

If all iccoling is' lost'when-in mid-loop operatione.how soon-will.

'boilingJincthe RCS begin? (Assume worst 1caser most limiting plant conditions)

(0.5) d.

-If-RHR cannot'be restored, what ate two'(2) alternate means of, decay-r,.

heat: removal available during taid-loop operatione as described :in-

<0POPO.4-RH-0001,' LOSS OF RESIDUAL HEAT REMOVAL?

(1.0)

L

00ESTION' 2.17-L(1.00)

[

0 POP 0"4-RS-0001 r STUCK ' OR DROPPED: CONTROL ROD r has two (2) options for 2

~ maintaining Tavs within.1.5 degrees F of Tref following a dropped: control' rod.-

What areithese<two'(2) options?

(1.0) i L.

l l?

l-(*****

END OF CATEGORY 2

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[GUESTION-3.0'1L

'(2.00) o

..g

?d St?ei$ht.(B)3automaticimain; feed. pump (MFP..)-turbine trips and the.

r associated setpointsiaiffapplicable. (2 0)

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-l l#" GUESTION

~3.02.

"(2 50)'

f'

~

l.f p

ja[. -

Unit liexperienced an SI actuation due to'.a spuriously generated S H

K

' signal... SI.has-been reset"and the.SI pumpsLhave been. stopped and placedEin; AUTO;in<accordance with 1 POP 05-EO-ES11, SI TERMINATION.. At

[-

' this':. point, ! a valid S L signal. is generated.

What affect will this have

i Lorn the. SI Lpumps?.. Nustif y your answer.

(,1.0)

'b.

1What:are'.sik.(6)1 signals (other than SI system start) generated by an

S signal?-

(1.5)

L 1

i b.~

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[GUESTION. ' 3 ' 0 3 '-

- ( 2. 00 )c

,j

a..

Mbprding pump discharge flow-is 112-spm-.an6 the; pressurizer and,VC' levels' ace constant.

Describe the,distrib; tion'of:this 112 spm h

INCLUDING what.letdowri flow: is'. necessary to. maintain constant:-

?

pressurizer and'.VCT levels'(CVCS Flow Balance).

' ( 1. 0 ).

bi..

Matchsthesvalves listed below with the' correct moti've force:and direct-ion..ofl failure' listed in the right hand column.

(1.0)~

' VALVE' MOTIVE FORCE, FAILED POSITION R

,;1. ' Low Pressur e' Letdown-a.

air, open Control Valve'(PCV-135) b.

aire as is c.-

airy closed 2.-Charging: Flow Control' d.

motorr open ValveL.(FCV-205) e.

- mot'r, as is.

o f.-

motore closed-3.LCharsingiLine Isolation Val've.(XCV-003) y l

- u.

'4. Charging Line Containment

Isolaion: Valve (XCV-005) 1

-l

. 5. Le.tdown. Orifice / Isolation-

~

i Valves'for;the 150 spmLand-100 spm. orifices: (CV-0012 and-

l CV-0013)

- GUESTION 3 04; (1.50)

-'a.

What'provides,the driving force for the RCP #3 seal injection" (0.5) j ib L To!where'do the leakoffs from the #2 and #3 seals drain?

(1.0) o.

i L

.l 4

1 h?-

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400ESTION 3

. 3.05.

(3 00) w fa.

.What:three (3) input. parameters / signals.ar.e used tosenerate control

. signals f or 'the : steam. donips?.

. ( 1. 0_).

q.

b.

All.. steam-dump' valves" shut when the. Low-Low;Tavsipermis ive! interlock

.P-12 isiresched.-

How. are ' thejtean, dumps made available. f oc continued -

j

~

tcooldown and which. valves are'available?

( 1 '. 0 ) :

E c -. ~

.What'causesIthe;followins interl'ocks'to. actuate? (Include any-

' applicable setpoints.). '

(1,0)'

. 1.'

' Coridenser Available Interlock C-9

~2 :

> Steam. Dump' Demand Interlock C-7

' QUESTION 3.06' (2.00);

s'..

What2. inputs /are compared to initiate control rod movement.whenl turbine load is changed?l(Specify the' source of the-input and what.it':.s.

' compar ed with'.-)

(1.0)'

lWhat,is"the.; purpose.of'the Rate Comparator circuit iri.: the Rod Control System?'

~

~

( 1 0 ):

0UESTION 3.07

.f(1.00)-

T.he reactor is operating at 100%'with al'. systems in a normal lineup-with Leontrol rods in manual.-

Which DNE of the followins events will cause the

.0TEdelta T setpoint-(Channel'II) to DECREASE?'

(1.0) s.;

'N42Lpower trnae lower detector fails low

v., lb.

'PT-456 pret.*urizer-pressure transmitter fails high c.:

Auctioneered high Tavs. fails high 1

.d.

' Power,is reduced to 50% with normal pressure and temperature l;

I L

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'(2.00)

F100ESTION a..

.In,additionitofdischarge.from;the pressurizerjPORV'scand safeties, p

what are.four (4.) other-so'urces of
discharge to'the1 Pressurizer Relief.

LTankt(PRT)?

(1 0).

??

r, LU:

'What'are'three:(3) alarms associated'with the Pressurizer Relief : Tank?-

(1,0)-

K l.

~

l L. QUESTION 3.09.

'(1.00)'

O.

, What.are two;(2)_ turbine. trip. signals provided by the'. turbine trip-system.

z to the' reactors. protection system? (Include applicable-coincidences)

(1.0).

1

[ ~tGUESTION.

"3.10!

'( 2. 00).

F

a..

'Listit'wo'-(2)Dcontrolsro'd blocks that. apply only..to automatic.

. trol

rod withdrawal.

- ( 1. 0 ).

1b.

L.ist[two1(2). control ' rod blocks that are accompanied by main turbine

[

trunbacks at--the same'setpoint.

(1.0) e

-GUESTION;

3.11 (2.00).

1What is~the purpose'of each of(the following La.

' Pressurizer backup heaters turn >n at +5% level deviation above progr aaimed level?

(0.5) b.'

Energizing the pressurizer backup heaters when diluting the Reactor Coolant System?

(0,5) t c.

Pressurizer PORV's see blocked when pressure is <2185 psig?

(0 5)

.c.

p

-f d.,

Pressurizer proportional heaters?

(0.5)

(

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h. 'GUESTIDN. - 3.12 (2.00) p

'.g La 4 Which ONE'of th'e"following';wi1~1-generate a Solid' State Pratection-

+

B JSystem-(SSPS) Urgent Failure alarm?:

(1 0)-

u

.'7

'~'4

11. -

Loss of either of twor48 volt:dc power, supplies..

E in 2.:

Loss of either of two 15' volt.dc. power supplies.-

b 3.

- SSPSLcabinet< door.open.--

h.

41 Reactor trip bypass breaker. closed.

b,:

'What is:the consequence of receiving an SSPS Urgent Failure. alarm'in-

.. bath Protection trains simultaneously?

(1.0) c l'

3'.13';

(2.50)'

GUESTION-JMatch the: conditions;(events) listed in the left hand column below with--ALL Jof.the reactor-tr.ips designed to provide protection.for that condition.

(The' reactor' trips listed-in the right-hand column may be used more;than-once')

.(2.5)

CONDITION' REACTOR. TRIP a.;

Rod Ejection 1.

Power. range hi flux (hi.stpt) 2.

Powet ~ r ange: hi' positive flux r ate-b.

,RCS Overpressure 3..

OT delta T

[^

~

4.-

OP delta T l c.;

' Loss of-Heat Sink 5.

Pressurizer low essure 6.

Pressurizer hi pressure ll

.d..

Reactor.0verpower 7.

Pressurizer hi level-8.

Loss of flow i

i from.

9.

Steam generator lo-lo level j

L

.e.

Departure i

Nucleate Boiling 10.

Turbine trip

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. GUESTION.

3.14-(1.00)'

e.f.

WhenJthefReLetor: Makeup system:is in' AUTOMATIC, how~does:it:k~nowJat what' rate : to' supply, bor :i c cacid?

(1.0)-

r.,;#L a. :

q The automatic' boric-acidiflow controller has.an-input from the pp

i boroi.ometer -

M b..

JThe rate 11'si determined byla; flow orif%e that:has been l'nstslied'p'rior

~

toisystem(startup.-

r

' The : baric / acid flow coritroller. uses the integrated chat'ging' header.

sc.~

g>

  • iflow signal.

p s

i l

fd..

.- The(boric acid' flow. controller uses the setting'on?the' potent'iometer.

c s

.c e

1 4

- f '(

3 15L

.-(2.50)

,10UESTION F'

a.

What ' three '(3): conditions must be' satisfied in' order to. reset the ESF load sequencer following actuation?

'(1.5) l b..

Once;theLESF; sequencer has actuated and:the-diesel' generators (EDG)

'have started, what two (2) manual. controls of the EDG'.s are blocked?

(1.0) a p

[

[00ESTION-3.16

. (2.00)-

t La.:

Wh'at! type-of. Power is available to the Class 1E'120 VAC inverters?-

~

(0.5)

[;

b.

-Describe how 120 VAC is obtained'froso the NORMAL power supply to the l:

. inverters?.

(0.5) c.:

In'the event of an inverter failure, what is the alternate power:

source to the 120 VAC vital bus?

-(0,5) 1 i

., d '.

Wh'at.. prevents the operator from paralleling AC sources through.the class >-1E 120 VAC bus?

(0.5)

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Page 25

i 4 ';BgSPONSIBILITIES'(10%)

y 49 f.

'3 1.[GOESTION::. ;3.' 17

' (3.00)-

. Wha't'are the'two1(2) sources of Makeupjto-the Auxiliary Feedwater g+<.ao.."[StorageT.ankf(AFWBT)?.

(1.0)-

a-

-b.-

At1what?locaticin inlthe" steam.systemcc.es the steam supply.-header,for the turbine driven:AFW pump. connect AND'what'is;theiexhaust; path for

the._ steam.usednin1the pump?'

(1.0):

.What; areitwo.(2)i sigrials -t'hatEwill automatically cause the turbine

.:c..

(1.0)-

driven AFW pump to start?.

,l'O ESTION.

3. '18 (1'.00)'

c.

E. What.are two?(2): functions that are bypassed when the Intermediate Range.

m

? Nuclear: Instrument C.evel Trip switcli is placed in the BYPASS position?.

'( 1. 0 )

a uGUESTION 3.19?

- -('2.00)2

a..

'What 'aren two '(2): conditions that will cause the Containment; Spray Additive' Tank. outlet;-(eductor suction).MOV valve to automatically sh'ut?-

(1.0)-

'b..

Whati.is the reasoncfor each of the'following?

-( 1 0 )-

' 1 '.
Limiting maximum containment spray pH-to 10.0 during the injection Phase.

2.

Maintaining equilibrium containment sump pH-praater than 7 5.

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Page 26

BESPQU@IglLIIIg@_11931 IGOESTION<

'3.20' (1.00) lWhich 0NELof the'following' statements list the input; signals.used to

controlL the:feedwaterEbypass flow control e Iv'e when in' automatic.-

( 1. 0 ) -

T

a.-

. Steam' header, pressure, fee'd. pump' discharge pressure, total ~ steam flow..

.b.-

Steam senerator. level, programmed' steam generator ' level,-.auctioneered-high>. nuclear. power.

Mc..

Steam generator level, programmed steam: generator' level, steam flow ~,-

ifeed flow.

d.'

Steam generator level, programmed steam; generator 19 vel, total steam flow.

-QUESTION, 3,21 (1.00)

What'is the;mi'nimum q~ qualification necessary to assume.the control' room:

command-function'if'the' Shift Supervisor is absent from the control ro~om

'when:thesonit is in Mode 5'or 6 (per the Tech Specs)?

(1.0)

~ QUES' TION' 3.22 (10'0 ENhatlare the four E(4) classes'of emergency declarations as stated in OErP01-ZA-0001,' EMERGENCY CLASSIFICATION?

List'in order from least severe Lto, mast; severe..

(1.0).

t p.'

l '

l l

f '..

l l

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iOUESTION -

-.3.23

('1.75)

I; Complete the folloking table dealins'with radiation' exposure limits.

. Individuals in A dinini s tr a tiv e 10CFR20 Radiologically Restr-icted Areas Limit Limit Unescorted Pet.sonnel-Whole Body (a)

(b)

Expectant Mothers

. (c)

' Escorted Visitors (d)

Emergency Response Personnel Equipment salvage (e)

Lifesaving situation (f) p l0UESTION.

3.24-

-(1.00)

According.to the~ CONFINED SPACE ENTRY PROGRAM, OPGP03-ZI-007, therr are two classifications'for confined spaces which must display danger placards.

.What'are thesettwo (2) classifications?

(1.0) b l

p

- GUESTION 3.25' (1.00)

According to OPGP03-ZR-044, CONTAMINATION CONTROL PROGRAM, what are'the three (3)' instances when personnel shall be considered contaminated?

(1.0)

GUESTION 3.26 (1.00)

What-three (3) types of Radiation Work Permits are used at STP?

(1.0)-

+

annnnn e n v re e n e v e enav vun nr a.a u urve ro a e r nnnnns

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2BESE9BSISILIIIES_1193F 0'UESTION-

-3.27

"( 1. 00 ).

~

Which DNE. set of the conditions listed below' requires double < valve protectional during the' performance of maintenance?

(140)

,, m b

fa.

-Upstream' pressure = 150 Psis Upstream. temperature = 100 degrees F i

i Maximum-potential opening size

=.25 inch diameter j

b ',

Upstream pressure.=.175.psis LUpstream' temperature'= 212 degrees F

'Haximum potential 1 opening _ size =.25 inch diameter Jc.

LUpstream pressure.= 125 psis, Upstream: temperature ='150l degrees F Maximum;-potential opening size = 0.5 inch diameter d.

Upstream pressure = 175 psig Upstream temperature ='150 degrees Maximum potential opening si=e =-. 75 inch diameter q

~

l LGUESTION

-3.28

'(1.00)

L 1 Throttle' valves.should:not normally be usedHas boundary valves for: system

isolation purposes on Equipment: Clearances because (choose ONE answer from J'

below)-

~

L It'is' difficult to accurately reposit' ion the valves to their proper a

. a..-

throttled position.

j b.,

They are susceptible to leakage.

l'

'c.-

They require independent verification when the Equipment Clearance is released.

"d.

.They are susceptible to damage when they are operated.

GUESTION 3.29 (1.25)

'a.

What is the purpose of the " SAFETY FUNCTION CHECKLIST"?

(.75) j b.

1When is a ' SAFETY FUNCTION CHECKLIST

  • required to be comp.leted? (0.5)

I

(***x.*

END OF CATEGORY 3

          • )

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

                    • )

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4 b.

-(1 0)-

( REFERENCE

l JLOT101".04srev 1,'p.o 8 192002K111'

...IKAfs)

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ANSWER; 1.02-(l'.00) b

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High. yield'(45)

2.-

Hish absorbtion cross.section (.5)

REFERENCE-1 LOT 101 10,rev 0yp.-4rEO~02 192006H102:

..(KA's) j

. ANSWER:

1.03 (l'00) c.)

(1.0),

. REFERENCE

-LOT 101.12,rev_.1,p 9,EO 08 19200 '4 K 113 --

192005K115

..(KA's) l

-ANSWER i.04 (1.50)

Fuel-Temperature (Doppler) Coefficient

-Moderator Temperature Coefficient oid' Coefficient V

(.4 for each correct answer,

.3 for correct orderr

.35 for each

~

m.' manipulation-to place in correct order)

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l

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l Westinghouse THERMAL-HYDRAULIC PRINCIPLES AND APPLICATIONS TO THE PWR II, p 10-44 1

191004K112 191004K107 191005K104

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lPurpose is to' prevent'any loakage of hydrogen-gas or steam through the-

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Accomplished by providing'a water. barrier between the safety valves and the steam; space..

. (.5)

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..(KA's)

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(1.0)

OR l Interlock : trips the breaker when inserting the racking tool. (1.0)

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.(3 actions' at :.4 each, 3=setpoints at.1.each)

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b.' J

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(.25 each)

, REFERENCE.

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4 REFERENCE, 1 POP 05-EO-FRS1,rev 2rpL4..

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e.-

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(.25'each) m

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~12 hours after1 event initiation

. 3.

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(.33 each) b...

-Flush plated boron from. upper resime of care

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(.5)

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b.

~

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, accept ~ 32Lspm (toiRCFV seals andq12 sem/ RCP ' seal mleallof f) g 93, '

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80 : spm; char giris Jinto RCSP(.25) 1

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. 4 2 P:-D R CD T. ' (. 5 ) ;

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, #3;- Containment Sump (may also list RCDT) (.5) d s.,

q-9:6 ' REFERENCE.

s 1

Ktf (0 dIC.HO.RCP.01,p..11,EO.06 r.

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/3r__ELBUI_HISIENS_13932_6HD_EL6BI: BIDE _GENEBIC' Page 45

-RESPONSIBILITIES (10%)

l ANSWER 3.05 (3.00)

J uctioneered high Tavs A

>2. ;

Turbine impulse pressure:

Main steam header pressure (3 at.33 each)

~

b.

. Cycle both' steam dump inter 1ock switches through the BYPASS interlock position (.5).. Thin allows bank No. 1 dump valves to continue dumping i

operations.(.5) c.'

1.'

One circulating water pump breaker must be shut (.25) and condenser vacuum must be greater than 20' Hg.(.25)

'2.

Turbine, load is reduced by greater than 10% step change (.25) or 5%~per minute ramp change.(.25)

$LSO ACCEPT

~

Turbine load reduction of 10% (.25) within a time interval of.120 seconds. (.25)

J

' REFERENCE, LOT 202.09 L,p 12, 22, 23;E0 02,04,08,09 041000G007 041020A402

..(KA's)

ANSWER'

~3.06 (2.'00) a.-

Auctioneered'high nuclear power (.25) is compared with' turbine impulse pressure (turbine load) (.25)

Turbine impulse pressure (Tref) (.25) is compared with auctioneered high loop Tavs (.25).

b.

Prevents the power mismatch circuit from responding to a steady state difference-between nuclear and turbine power. (1.0)

ALSO ACCEPT hit is an anticipatory circuit for fast response on load transients.

(1.0) k

v.

exa l

w

> 4 %"

l

/

4

m

-)

13.

-PLANT. SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 46

~

BESEONSI@ILIIIES;1 Loll h

JREFERENCE-

' LOT 201.'18,rev-0,p 20-22iE0 03,06 lA

-.001000K105 001010K507

..(KA's)

L

. ANSWER' 3.07 (1.00)'

'a.t (1.0)

REFERENCE I

1 0.LIC.HO.SSPS.01, p 7.

j 4

'012000K611' 012000A205

..(KA's) l ANSWER 3.08 (2.00)-

L a.:

- RHR pump discharge

-LSIS/HHSI discharge i

- ' SIS /LHSI discharge

- CVCS seal return

--CVCS letdown p

Reacter vessel head vent

- PASS (any 4 at.25 each) l b.

- High pressure alart

- Hi level alarm 1

- Lo. level alarm g

- High temp alarm (any 3 at.33 each) j TREFERENCE

'I 1

LOT 201.04,p 17,EO 10,13 l-007000A301 007000G008

..<KA's)

I L

l i

ANSWER 3.09 (1.00)

Low auto stop oil pressure (.25) on 2 of 3 pressure switches (.25).

Turbine throttle stop valves closed (.25) - 2 of 4 (.25) l l

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CATEGORY 3 CONTINUED ON NEXT PAGE *****)

l

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H 1

lj 3.

' PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 47 j

BESE9 Ngl @ILIIIgg_IIO31 TREFERENCE 1'

I LOT 201.20,p 24 045000K411

..(KA's)

ANSWER 3.10 (2.00) al.

Low power interlock - CL

(.5)

Control Dank D withdrawal limit - C11 (45)

.b.

OT delta T - C3

(.5)

OP delta T - C4

(.5)

I REFERENCE LOT 201.18, p 25 001000K407

..(KA's) t ANSWER 3.11-(2s00)

'a.

' Heat the insurge of cooler. wat er OR Limit pressure reduction.

(.5)

'b.

Equalize the pressurizer and RCS baron concentration (by creating additional spray flow.)

(.5)

.c.

Prevents an uncontrolled depressurization of the RCS (.5) (if one channel should fail high.)

d.

Compensate for continuous spray valve byposs flow (4 SPm) (.25) and heat losses to ambient.(.25)

. REFERENCE LOT 201.14, p 6,12,14;E0 14 LOT 201.04,E0 06,09,20 1 POP 03-ZG-0005,p 3 0 :.1000 K 603 010000K603 0100004203

..(KA's)

._ _ _ ___ ____ _ ____ b* * * *

  • E A T E G O R Y 3 CONTINUED ON NEXT PAGE
          • )

T

' 3 '. - PLANT SYSTEMS (38%) AND PLANT-WIDE GENFRIC-

.Page-48 cSESEQNgl@lLIIIgg_11931 ANSWER 3'.12 (2.00)-

s.

4.- (1.0) b.

The reactor will be1 tripped automatically.'(1 0)

REFERENCE 0.LIC.HO.SSPS.01,p 28 012000K402 012000G008

..(KA's)

ANSWER 3.13 (2 50) a.

2

(.25)

b.

6 and 7

(.5) c.

9 and'10

( 5) d.'

1 and~4

(.5) e.

3,5,and 0

(.75)

REFERENCE LOT 201.20,p 12-24 012000K402

..(KA's)

ANSWER 3 14 (1.00) l d.

(1.0)

REFERENCE CLT004.11, p 24 004020A401

..(KA's) l

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CATEGORY 3 CONTINUED ON NEXT PAGE

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.Page 49-BESE9BSIBILIIIES_11931 t

ANSWER' 3.15

-(2.50)

.a.-

SI reset UV cleared Loading sequence completed

(.5 each) b.

. Manual. shutdown Manual tri P of Senerator output breaker-EDG voltage adjustments EDG frequency adjustments- (any.2 at

.5 each)

REFERENCE CLT003.22,p 10 062000K302 064000K203

..(KA's)

ANSWER-

'3 14'

'(2.00) a.

125.VDC 480 VAC

(.25 each) b.

Normal 480 VAC is rectified to DC (.25).and then inverted to produce 120 VAC.(.25) c.

A voltage regulator (.25) supplied from a different~480 V MCC than the one supplying the inverter.(.25) 1d.

Mechanical interlock (.5)

REFERENCE LOT 201.38.L,p 5-7 062000K410

..(KA's) l L

l l

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CATEGORY 3 CONTINUED ON NEXT PAGE

          • )

y y

S_L EL6HI_SISIEUS_1SS31_609_EL6NI;SIDg_ggNEBI9' Page.50

,w BESEQUSIBILIIIES_IIO31 r,

' ANSWER 3.17.

(3.00)'

i ca,.

Demin-water Hotwells

(.5'each)

'b.-

' Steam source - Main steau, line 1D upstrean, of MSIV Exhaust' path

' Atmosphere:through roof vent

(.5 each)

_c-SI signal SG-Lo-Lo level AMSAC (any 2.at

.5 each)

REFERENCE I

LOT 202.28,p.6,9,10 1

061000K107 061'000K103 061000K402

..(KA's)

ANSWER

'3.18 (1.00).

IR hi flux reactor trip Rod withdrawal block (C-1)

('.5 each)

~

' REFERENCE

'L T201.16,p 22

?)5000K406

..(KA's) l

. ANSWER 3.19 (2.00)

H a.-

Additive tank l o - l 'o level (.5)

L RHST lo-lo level auto switchover (.5)

)

L I

l be' 1.

Prevent caustic attack on RCS and sump metals (.5) 2.

Ensure all entrapped Iodine remains in solution (.5)

REFERENCE LOT 201.11rp 6,11,12iE0 04 026020A101 026000K402

..(KA's) ll l

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13___fL6HIiSISIEdS_lSS32j$Np_EgedI;BIQE_GENESICr

-Pase 31

'BESEgNgl@ILIIIgg_11931

)

(ANSWER

3.20' (1.00).

T b".

<(1.0')

,v REFERENCE

. LOT 202.15',P.24-035010K402

..(KA's)

~

' ANSWER-3.21 (1.00)

RO licensed (1.0)

REFERENCE'

,Technica1 Specification 6.2.2 194001A103

..(KA's) p ANSWER 3.22 (1.00) l NOUE ALERT SAE GE

(.5 for correct classes,

.5 for correct. order) b REFERENCE p

'OEPP01-ZA-0001,rev 8, p4 1:

l'.

194001A116

..(KA's) l l,

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CATEGORY 3 CONTINUED ON NEXT PAGE

          • )

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L2___EL6BI_SYSIENH_1SS31_6N9_EL6dI: WIDE _GENEBIG Page.52

_R_ESPL_NSIB_ILI_ TIE _S__(10%_)

!~

1-

. ANSWER 3 '. 2 3.

(1.75) a._

(1.'O rem /qtr (.25) 4.01 rem /yr

(.25) t4 1.25 rem /qtr-(3.0 rem /qtr w/ complete exposure history on file) (,25) c."

500 mrem for the duration of the pregnancy'(.25)

ALSD ACCEPT 100 mrem /qtt (.25) d.'

.100. mrem (.25)

e..
25 rem for equipment / system salvage (.25) f.-
75. rem for lifesaving situations (.25)

REFERENCE OPGP03-ZR-0042, rev 1, p 19' 194001K103

.. (KA's)

,1 ANSWER-3.24 (1.00)-

Enclosed. Spaces (.5) and Permit Entry " spaces ( 5)

~

REFERENCE

'0PGP03-21-0007,rev 4,p 2 194001K113 194001K114

..(KA's)

ANSWER 3 25 (1.00) 1.

Beta gamma count rate on any portion of their body or clothing exceeds 100 cpm'above background C.33) 2.

When any alpha contamination is detected (.33) 3.

When a valid alarm is received on a Personnel Contamination Monitor (PCM)~

(.33)

(_r****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

f. -

E

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3.-

PLANT SYSTEMS-(38%)=AND PLANT-WIDE GENERIC

.Pase 53 a-BESPOUSl@lLIIIEg_11911 REFERENCE l0PGP03-ZR-0044,rev 0,p 5 L194001K103

..(KA's) l

' 1(;

?~ ANSWER 3.26

.(1.00) l Generale Specific, Emersency1(.33 each)

REFERENCE

.OPGP03-ZR-0002,rev'4,p 3 194001K104 194001K103 194001K105

..(KA's)

ANSWER 3.27 (1.00) d (1.0)

REFERENCE

'0PGP03-ZO-0001,rev Sep 8 19'4001K108 194001K109 194001K102

..(KA's)

ANSWER 3.28 (1.00) a.

(1.0)

REFERENCE OPGP03-ZO-0001,rev 8,p 24

'194001K102

..(KA's) l t

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

- = _ _ - -. :--. _ _ - _ _ -

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.h__EleNI_EXEIENS_13931_oN9_EL6NI: BIDE _9ENEBIG Pese 54.

1 BE@EQUSI@ILIIIES_11931 1

'h 1

ANSWEP:

13.29' (1.25) l a.

Used as a reference in determining the. minimum required equipment / instrumentation.'for any given plant mode. (.75) b.

..Each shift'(.25) and prior to a mode change (.25) (as required by 1 POP 03-ZO-0001)'.

REFERENCE

.0PCP03-ZA-0063,rev 6,pgs 4,12

~~194001A106 194001A113

..(KA's) i 1i..

l, l.

i l

l l

l-1 l-(*****

END OF CATEGORY 3

          • )

(********** END OF EXAMINATION *********x) 1__

_

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