Text

Exam Rept 50-361/OL-89-01 on 890512.Exam Results:Sole Candidate Failed Written Exam
	ML20246L721
Person / Time
Site:	San Onofre
Issue date:	06/20/1989
From:	Johnston G, Miller L; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	;
Shared Package
ML20246L697	List: ML20246L691; ML20246L721;
References
	50-361-OL-89-01, 50-361-OL-89-1, NUDOCS 8907180499
	Download: ML20246L721 (100)
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a:,3 %,;, ' Examination Report'No. 50-361/0L-89-01 c

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(FacilityLicensee: Southern' California ~ Edison Company..

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P. 0; Box 800 4

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'2244 Walnut Grove Avenue-4

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Facilf ty Docket Nos P < 50-361, 50-362.

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Facility Aicense Nost NPF-10; NPF-15

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,Examinationadminist$ red ~atSanOnofreNuclearGeneratingStation, i

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1, Chief E miner::

G6tf.W. JohnsKop', Opetator U

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Date Signed "

Licensing Exakiner~

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, _ Approved;by:

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.L7 F. Miller,(Jr J. Chief Date Signeds Operations Sectron Summary e

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. Examination on May.12, 1989 A written examination was2 administered to one' Reactor Operator. candidate.

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The-candidate failed the written' examination.

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REPORT DETAILS Examiner

- 1.

G..Johnston, RV

Denotes Chief Examiner 2.

Person attending the Exit Meeting R. Clement, SCE 3.-

Written Examination and Facility Review The written examination'was administered on May 12, 1989 at the training center. At the conclusion of the. examination, a copy of the Reactor Operator examination key was given to the facility staff for review and' comment.

The facility elected to not provide comments on the' examination as it was-

~iven..The facility staff did participate in a pre-examination review of g

the written examination. The examiner incorporated some suggested changes which were ' considered appropriate for the examination prior to ar' ministration to the candidate. Since the facility declined to submit written comments after the examination this report does not include a resolution of facility comments.

4.

Exit Meeting On May 12, 1989 an exit meeting was conducted with the licensee representative, as noted in Paragraph 2 of this report. The examiner discussed the examination progress and other topics related to operator licensing.

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L Grading Key Changes from Pre,-examination Review The.following will detail changes made to the examination from'the review conducted by Mr. R. Clement' and Mr. C. Elliot of the SONGS 2/3 staff. The facility staff declined to provide written comments following the examination.

.The following documents changes were made by the Chief Examiner to the l -

approved examination, as-a result of the pre-examination review.

Question 1,02:

Distractor d. was' changed to " Draining a steam generator when it is below 200 deg. F." vice " Draining a steam generator when it is greater than 212 deg. F.

l Question 1.03:

Distractor b. was changed to " Natural Circulation is indicated if delta T is between 25 and.100%.of normal full power Delta T" vice " Natural Circulation is indicated if delta T is between 25 and 80% of normal full power Delta T."

. Question 1.05:

4 The first sentence in the header was changed to read " Extensive voiding has occurred in the RCS, in the vicinity of the reactor vessel head during a natural circulation cooldown" vice " Voiding has occurred in the RCS, in the l

vicinity of the reactor vessel head during a natural circulation cooldown."

Question 1.06:

The sentence "The temperature of the steam exhausted to the atmosphere is 320 deg. F" was deleted.

Question 1.07:

The word identical was inserted between second and centrifugal.

Question 1.08:

1 The parenthetical information "(Assume negative ITC)" was added to the question.

Question 1.09:

The term negative 80 second period was replaced with negative 1/3 DPM.

b a

4 Question 1.13.

Item b. was rewritten as "The reactor and turbine power was raised to 100%"

vice "The rods were placed in automatic, and turbine power was raised to

-100%." Item c was rewritten-to " Reactor power was reduced rapidly and l

stabilized at a lower power level-(10%)" vice " Reactor power was reduced rapidly and stabilized at 10%."

- Question 1;16:

The header paragraph, "During power operations, ene 4.16 KV EXF bus has been deenergized because of a spurious feeder breaker trip. The Emergency Disel Generator failed.to start. The operator is' ready to reenergize the ESF bus by reclosing the feeder breaker using' the paralleling method of S023-6-2,

" Transferring of 4160 Volt bus ses." we.s deleted.

r The question was re-written from "If the operator attempted to close.the feeder breaker WITHOUT turning on the synchroscope, would the breeter close?"

to "If the operator attempted to close a 4160 volt bus supply (excluding Diesel Generator output) breaker WITHOUT turning on the synchroscope, would the breaker close?"

k Question.1.17:

The distractor a.,was changed to " cavitation" from " slip".

Question 1.18:-

Item a. was the actual correct answer, so the answer key was changed from c.

Question 1.21:

Item c., "125%" was changed to "175%" to make a more viable distractor.

Question 1.23:

The header was changed to include "in the field" for a manually shut valve.

Question 2.01 a.:

The question was changed to require three of four vice three answers. The answer "4. Stop All RCPs" was added to the key.

Question 2.02:

The term "4160 volt" was added before "ESF" in the header.

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Question 2.10:

The word COMPONENT was substituted for system.

Question 2.11 The phrase "with an inadvertent SIAS" was deleted.

Question 2.)3:

.The header paragraph, " SONGS 2 is in Mode 3 conducting a reactor startup when Source Range Neutron flux monitor "B" fails. The Train "A" flux monitor is out of service.

It is determined tha the normal power supply is faulty for Train "B"." was deleted.

The question was reworded to say "/hich of the following indicates a successful transfer of power for the Train "B" startup flux monitor to its alternate source for a shutdown from outside the control room?" vice "Which of the following indicates a successful transfer of power tor the Train "B" startup flux monitor to its alternate source?"

Question 2.14:

The first sentence in the header was changed to read " SONGS 3 is in Mode 5 with the RCS: partially drained to mid loop for installation of Steam Generator nozzle dams" from " SONGS 3 is in Mode 5 with the RCS partially drained to mid loop for maintenance on the RCS loop drain valves."

Question 2.19:

Answer b. was. changed to 740 GPM +/- 5 gpm vice 743 psia +/- 2 psia.

Question 2.21:

The first. header sentence was changed from "The Emergency Coordinator has tas b d you with determining the Event Classification'for an inadvertent radioactivity release. You have made the determination that the event code is A2-1" to read "The Emergency Coordinator has told you the Event Classification for an inadvertent radioactivity release determination is event code A2-1."

Question 3.07:

The answer was change tn "Duench Tank" from Containment Sump".

Question 3.10:

The answer "High Radiation" was changed to two answers "High Radiation RE-7865" and "High Radiation RE-7808". The answer was made to require two correct responses out of three possible.

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Question 3.14:

Item c. was changed to "High discharge pressure of the ogr. rating pump" from

- Low discharge pressure (15 psig) of the' operating pump

-Question 3.15:

The question was changed to "What TWO (2) conditions will cause an isolation

-of.the discharge to the Circulating Water Outfall?" from "What TWO (2) conditions, other than High Radiation on RE-7813, will cause an isolation of the discharge to t' e Circulating Water Outfall?" The answer was changed to add "High Radiation'on RE-7813" as an answer.

Question 3.17:

J The header was changed to read "The Diesel Generators.are'. running after starting from a SIAS signal" from 'he Start Mode Selector Switch at the Diesel' Generator Local Panel is in the LOCAL position and the diesel is running after starting from a SIAS signal."

Question 3.18:

' Answer c was changed to read "G003 Diesel Generator Control" from "L-160 is-the G003 Diesel Generator Control Panel."

Question 3.19:

Item c, was changed from "The indicated T-ave will fail to offscale high when the T-cold leac is shorted to the T-hot lead" to read "An open circuit in an RTD based system will cause a lowered resistance, thereby indicating a high temperature."

Question 3.21 a.:

The question was changed from "Why does the Pressurizer level level vary with changes that occur in RCS temperature?" to' read "Why does the Pressurizer level programmed level vary with changes that occur in RCS temperature?"

Question 3.22:

Item d., the power supply for backup heater B-3 was changed to B04 from B06.

Question 3.23:

In item b. " Hot Leg" was substituted for " Upper Guide Structure Support Plate".

In item d. 200 deg. was substituted for 90 deg.

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_ Question-3.24:-

. Item b'. was changed to read " Low level indication via LSHL-7740 is only"a lo_al' horn alarm in the Spent Fuel: Pool area." In item c. " annunciated c

replaced " monitored."'

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.. Question 3.26:

' Circ. Water replaced CWS.:

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. Question 3.28:~

Quotation marks were placed cn " block".

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pn ras-a Su e Vuc 5I U. S. NUCLEAR REGULAT)RY COMISSION j

REACTOR OPERATOR LICENSE EXAMINATION REGION 2 FACILITY:

san onofre Units 2/3 REACTOR TYPE:

combustion Engineering DATE ADMINISTERED:

May 12, 1989 j.

INSTRUCTIONS TO CANDIDATE:

Use 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 question.

The passing grade requires at 1 east 70% in each category and a final grade of at least 80%.

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

y

% OF l

CATEGORY % OF CANDIDATE'S CATEGORY

[

/VALUE TOTAL SCORE VALUE CATEGORY

't o

25.00 25.00 1.

REACTOR PRINCIPLES (7%)

THERMODYNAMICS (7%) AND COMPONENTS (11%)

(FUNDAMENTALS EXAM) i lf 27.00 27.00 2.

EMERGENCY AND ABNORMAL PLANT

'(

EVOLUTIONS (27%)

48.00 48.00 3.

PLAN 1 SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)

\\p e

i 100.00 TOTALS

.(

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

I have neither given nor i

. received aid.

i g.-

t Candidate's Signature

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ES-201 i

Rav 5 01/01/89 y

(

ATTACHMENT'2'(continued)

PROCEDURES FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS

)

i 1.

Check identification badges.

2.

Pass out examinations and r,11 handouts.

Repird applicants not to review 3-examination until instructed to do so.

READ THE FOLLOWING INSTRUCTIONS VERBATIM:

During the administration of this examination the following rules apply:

1.

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

p 2.

After the examination has been completed, you must sign the statement on j-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 f.

done af ter you complete the examination.

Y READ THE FOLLOWING INSTRUCTIONS 1.

Restroom trips are to be limited and only one applicant 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.

2.

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

3.

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

bl 4.

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

5.

You may write your answers on the examination question page or on a separate sheet of paper.

USE ONLY THE' PAPER PROVIDED AND DO NOT WRITE ON I

THE BACK SIDE OF THE PAGE.

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6.

If you write your answers on the examination question page and you need more space to answer a specific question, use a separate sheet of the l.

paper provided and insert it directly after the specific question.

DO NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.

L l

7.

Print your name in the upper right hand corner of the first page of each section of your answer sheets whether you use the examination question pages or separate sheets of paper.

Initial each page.

8.

Before you turn in your examination, consecutively number each answer li sheet, including any additional pages inserted when writing your answers on the examination que=H on page.

t

'ti Examiner Standards 14 of 18 I.

e i.

ES-201 Rev 5 01/01/89 ATTACHMENT 2 (Continued) (Continued) j 1

9.

If you are using separate sheets, number each answer as to category and number (i.e. 1.04, 6.10) and skip at least 3 lines between answers to allow space for grading.

10.

Write "End of Category

" at the end of your answers to a category.

11.

Start each category on a new page.

12.

Write "Last Page" on the last answer sheet.

13.

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

Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect answer. Write it out.

14.

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

question.

The amount of blank space on an examination question page is y

NOT an indication of the depth of answer required.

15.

Show all calculations, methods, or assumptions used to obtain an answer.

16.

Partial credit may be given. Therefore, ANSW74 ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

17.

Proportional grading will be applied.

Any additional wrong information that is provided may count against you.

For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth y

0.20 points.

If one of your five responses is incorrect, 0.20 will be

[

deducted and your total credit for that question will be 0.80 instead of j

1.00 even though you got the four correct answers.

i 18.

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

I 19.

When turning in your examination, assemble the completed extaina' ion with

[

examination questions, examination aids and answer sheets.

4a -ddition, turn in all scrap paper.

20.

To pass the examination, you must achieve an overall grade of 80% or greater and at least 70% in each category.

21.

There is a time limit of (6) hours for completion of the examination.

(or some other time if less than the full examination is taken.)

22.

When you are done and have turned in your examination, leave the examination area (DEFINE THE AREA).

If you are found in this area while the examination is still in progress, your license may be denied or revoked.

Examiner Standards 15 of 18

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EQUATION SHEET f = ma.

y.,fg.

Cycle efficiency = Net W rk (out) 2 U

-w = #8.

s = v t +. hat Energy (in) o 2

E = aC a = (v - v )/t g

g

'A = i,e~A" A = AN KE = hav vf. v, + at.

PE = agh a = g/t 1 ='in 2/tg = 0.693/tg

(*II) * (t, )(ts)

" "A#

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AE = 931Am (t '+ t )

f g

Q " M oT I=ze 4x p

-yx Q = UAAT 7,Ie i

f y,7 10 *!

Pwr = U In

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P = P,10 " IE)

TVL = 1.3/u

~P = P, e /T t

INL = 0.693/u SUR = 26.06/T-T = 1.44 DT SCR = S/(1 - K,gg) s fk*gg) o SUR = 26 CR = S/(1 - K,gf )

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x g_,.

CR (1 - Keff)3 =. CR (1 ~ Keff)'2 y

2 T = '(1,/p-)'+

[(6 'p)/A,gf ]

p y.t*/(p_j M = 1/(1 - K,gf) = CR /CR0 g

T = (3 - p)/ 1 p

egg M = (1 - K,ff)0 (I ~ eff)1 8*

eff eff = AK,ff/K

-1)I eff SDM = (l'- Keff)/Keff p[

[t*/TK,gg] + [H/(1 + A,gf )]

t* = 1 x 10 ' seconds

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t p=

-I b'

P = I(V/(3 x 1010)

A,gg = 0.1 seconds

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I = No Id =Id y3 22 WATER PARAMETERS Id =1d g

2 2

1 gal. = 8.345 lba R/hr = (0.5 CE)/d (meters)

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1 gal. - 3.78 liters R/hr = 6 CE/d (feet) 1 ft3 = 7.48 gal.

MISCELLANEOUS CONVERSIONS 3

10 k

Density = 62.4 lbm/ft 1 Curie = 3.7 x 10 dps Density = 1 gm/cm 1 kg = 2.21 lbm.

3 Heat of vaporization = 970 Etu/lbm I hp = 2.54 x 10 BTU /hr 6

i Heat of fusica = 144 Btu /lba 1 Hw = 3.41 x 10 Btu /hr

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1 Atm = 14.7 psi = 29.9 in. I'g.

1 Btu = 178 ft-lbf 5.54 cm 1 ft. H o = 0.4335 lbf/in 1 inch 2

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F = 9/$'C + 32

.n "C = 5/9 ( F - 32) 4-

Section 1 Reactor Principles, Thermodynamics, and Components GROUP 1-THERMODYNAMICS

QUESTION 1.01 (1.0)

MULTIPLE CHDICE (Select the correct answer.)

Which of the f ollowing i s correct concerning brittle fracture behavior of the reactor vessel?

a.

The stress due to the dif f erential temperature across the vessel wall is normally tensile in nature because of RCS I

pressure, and not compressive.

f b.

The presence of an inclusive flaw or crack and a low n

di f f erenti al temperature is required bef ore brittle f racture can occur due to stress.

c.

An increase in the integrated radiation exposure to the vessel due to gamma photons reduces ductility over the lif e of the vessel.

d.

Brittle f racture will only occur during conditions of low reactor coolant system pressure and low differential I

temperature across the vessel wall.

ANSWER

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a.

(1.0)

REFERENCE HTFF PG 260 - 263 LO 2MS212 OBJ 1.1.2

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QUESTION 1.02

. ( 1. 0 )

MULTIPLE CHOICE ( S'al ec t the correct answer.)

- D; Which of the f ollowing actions is most likely to cause water hammer 7 a.

Starting a centrifugal pump with the discharge valve shut.

b.-

Feeding a steam generator with water colder than saturation.

c.

Placing vacuum breakers on the high points of water systems.

d.

Draining a steam generator when it is below '200 deg.

F.

ANSWER b.

(1.0) i

REFERENCE l

HTFF 285 - 287 I

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GROUP ! I 1 - THERt10 DYNAMICS E

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QUESTION l'.03'

. (1.0)s Yfjf} q

. t.il MULTIPLE CHOICE (Select the correct: answer)-

g f m.l' Which of-the f ollowing describes the relationship of: core differential: temperature'(delta T) has with Natural Circulation:

conditions?

a.

With no flow, there will: be no change 'in delta. T, because

'T-hot and T-cold will:not change due to stagnation.

b.'

Natural Circulation 'is indi cated i f del ta T is betw'een ' 25 r

' and ' 100 L */. of ' normal full. power Delta T.

c.

Natural Circulation is indicated when-the delta T exceeds

.the. f ull' power normal delta T.

d.'

With no flow, there will'be a.dr.op in delta T, because T-hot y

and T-cold will not change dua to stagnation.

4

ANSWER-r

- b.

(1.0)

REFERENCE HTFF PG 356 - 357 LO 2HT204 OBJ 1.3.1 AND 1.3.2 r,.

' *KA 193OO8K121 L

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1* QUESTION'1.04.

( 1.. O )

MULTIPLE CHOICE-(Select the correct answer.)'

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Which of the f ollowing is correct concerning conductLof a secondary calorimetric?

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1 a.

The calorimetric equation does not tal.:e into account the heat input from the reactor coolant pumps or lost to the containment because these offset.

lb.

The calculated reactor power will be lower than actual because the change in enthalpy will be lower if feedwater

temperature is. read erroneously high.

L.

The mass flow rate of ' the: secondary system is determined by -

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totaling the average. steam flows f rom both of the Steam Generators.

l d.

The results of a primary calorimetric may be used as ' the u

basis for calibration of the power. range nuclear instrumentation but not the Safety Channels

ANSWER r

b.

(1.0)

REFERENCE HTFF PG 153 - 158 LO 2HT207 OBJ~1.1.5

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OUEST10N 1.05 (1.0)

MULTIPLE CHOICE (Sel ect the correct answer.)

n Extensive voiding has occurred in the RCS, in the vicinity of the reactor vessel head during a natural circulation cooldown.

Which of the following CORRECTLY characterizes the process of collapsing the void?

a.

The void will superheat if an attempt is made to collapse it too fast. The rate of collapse will be governed largely by ambient heat loss from the void.

b.

The void will collapse at a rate equivalent to the rate of HPSI flow; therefore, full HPSI should be run until the void is fully collapsed.

Iy c.

The void will be composed largely of hydrogen gas, and will therefore require degasifying of the RC3 in order to begin collapsing it.

d.

The void will collapse immedi.stely upon increasing the k

pressure above the local saturation pressure; the main a

concern is water hammer.

ANSWER a.

(1.0)

REFERENCE i

EQB GENERIC FUNDAMENTALS FOR CE PWR L

SECY 82-475 i

HTFF PG 355 - 358 LO 2HT221 OBJ 1.2.1 I,

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GROUP III THERMODYl;AMICS

QUESTION 1.06 (1.0) 1 MULTIPLE CHOICE (Select the correct answer. )

A ' reli ef valve on a pipe opens at 885 psig.

The fluid within the pipe is saturated steam. Using the steam tables provided, what is the approximate temperature of the steam within the pipe?

a.

530 ceg. F b.

400 deg. F c.

320 deg. F d.

212 deg. F f

ANSWER a.

(Saturated steam at 885 + 15 psia.)

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REFERENCE EDB GENERIC FUNDAMENTALS FOR CE PWR CE Steam Tables LD 2HT221 OBJ 1.2.7

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QUESTION 1.07 (1.0)

MULTIPLE CHO7CE (Select the correct answer.)

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- Initially, one centrifugal pump is in operation when a second identic.a1 centrif ugal pump (in parallel with the first pump) is also put into operation.

Which of the f ollowing statements correctly describes the ef f ect on system volumetric flow rate and system head loss?

a.

Same flow rate same head loss b.

Hic'?r flow rate, same head loss c.

Game flow rate, higher head loss

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d.

Higher flow rate, higher head loss k

ANSWER 1

s d.

(1.0)

REFERENCE HTFF 320 - 329 LO 2FD203 OBJ 3.2

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193OO6K115 193OO6K102 191004K109 191004K105 OO6050K501 n

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g-GROUP I REACTOR THEORY

OUESTION 1.08 (1.0) 51 Q"9 MULTIPLE CHOICE (Gelect the correct answer. )

t Which ONE of the following conditions will result 'in criticality occurring at a higher than estimated control rod position (Assume negative ITC)?

a.

Inadvertent dilution of RCS boron concentration during rod withdrawal.

b.

Misadjusting the steam dump controller such that steam pressure is maintained 50 psig higher than the required no-l oad setting.

c.

Delaying the time of startup from 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months to 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months f ollowing a trip f rom 100% power equilibrium conditions.

w d.

A malfunction resulting in control rod speed being f aster than normal speed.

ANSWER b.

(1.0)

REFERENCE RT PG 171 - 183 LO 2NT211.OBJ 1.3.1 -

1. 3. 3

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OUESTION 1.09 (1.0)

MULTIPLE CHOICE (Se'ect the correct answer.)

g, f ollowing a reactor trip the the' reactor power decays off.

Which of the following describes the nature.cf the post trip power response?

a.

The power drop initially is very f ast but af ter a stable SUR is estab)1shed will never be more than a negative 1/3 DPM.

b.

The power drop initially starts at a negative 1/3 DPM and eventually becomes O DPM.

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c.

The power drop is initially very f ast, then establishes a stable negative 1/3 DPM, and eventually becomes O DPM.

[

d.

The SUR is initially 0 DPM, then establishes a negative 1/3 L

DPM until a stable shutdown l evel is achieved.

ANSWER c.

(1.0)

+ REFERENCE RT PG 63 - 75 LO 2NT212 OBJ 1.2.6

KA 192OOSK123 s

b..

OUESTION 1.10

( 1. O)

MULTIPLE CHD1CE (Select the correct answer.)

During a reactor startup,- an ini ti al reactivity addition causes count rate to increase from 20 CPS to 40 CPS.

A second reactivity addition causes the count rate to increase 'f rom 40 CPS to 80 CPS.

Which of the following statements is correct?

a.

The first reactivity addition was smaller.

b.

The second reactivity addition was smaller.

c.

The first an.

second reactivity additions were equal.

d.

There is insufficient data given to determine relationship of reacti vity values.-

ANSWER-

+

b.

01.0)

REFERENCE RT PG 109 - 110 AND 131

.139 L.O 2NT212 OBJ 1.4.6

KA 192OOGK103 l.

I E

t U

/

t a

T A

i i

4 f

t

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L____________.___

i

W ~m.._ ;g '.

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=

pp"[ '

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+

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E

OUESTION[1.11'

( 1. 0) '

-,e_

.NULTIPLE' CHOICE (Selectcthe c6rrect answer.)

. -a.

n w--

g4g., '

Which of Lthe f allowing. resporyses below will correctly; complete

'the statement?

c. E During'a; reactor ~startup, just PRIOR to " reaching criticality, the-SUR indication ~will respond-to the same~given amount.of rod wi thdr..awal by - '

'a.

ri sing : sl owly then (alling' sl owl y. to..zero.

b..

rising rapidly then f alling slowly to ero.

c.

rising: slowly then falling rapidly to'zero, t.

%; j s

(,

d.

rising rapidly then' falling rapidly to zero.

p F-

ANSWER g.

{,

.b.

( 1. 0) -

t P-

REFERENCE-RT PG 131'.133 LO 2NT212.OBJ 1.4.6

KA' 192OOOK194 192OOBK105 192OOOK103 015000K506 o

f, -

t.

d

.O

4. ! s,

4 4.

[, [

f.

F; -'

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l GROUP'IIcREAC10R THEORY

DUESTION 1.'12

( 1. O )

s '.

MULTIPLE CHOICE (Select the correct answer.)

When a reactor trips from various power levels the Xenon.135 concentration will rise to a peak.

Which of the f ollowing a s true about this peak Xenon 135 concentration?

a.

The peak occurs earlier after a trip from 100% of reactor power versus 25% of reactoi pmer, b.

The peak is lower in value and occurs later for a power

[-

level of 25% power versus 100% power.

P i.

c.

The peak is higher in value and occurs later for a' power l

1evel of 25% power versus 100% power.

l d.

The peak i s l ower in value and occurs earlier for a power level of 25% power versus 100% power.

ANSWER d.

(1,0)

+ REFERENCE RT PG 218 - 222 LO 2NT204 0B.1 2.3 y>

KA' 192OO6K111 h

k V

~

i t

i h

h

{:

i i

C _ _ _ _ __ -.___-- -- _ _

m,---

DUESTION 1.13

'(1.0)

MULTIPLE CHOICE (Select the correct answer.)

Using the f ollosing Xenon worth curve, Figure 1.1, answer the f ollowing question.

What happened at. time = T2 7 a.

The reactor tripped..

b.

The reactor and turbine power was raised to 100%.

c.

Reactor power was reduced rapidly and stabilized at a lower power (10%).

d.

Turbine power remained constant, rods in manual and inserted 50 inches and a turbine bypass valve failed open (7% of rated power).

ANSWER c.

(1.0)

REFERENCE RT PG 218 - 226 LO 2NT204 OBJ 2.5

KA 192OO6K105 192OO6K106 k

-o k

e\\}; a h

&* ' 'l

~___.__&_mm_.-

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-mm

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P GROUP III REACTOR THEORY

OUESTION 1.14 (1.0)

MULTIPLE CHOICE (Select the correct answer.)

Which of the f ollowing statements concerning the Shutdown Margin (SDM) is correct?

a.

It is based on a rod ejection accident at end of-core life.

b.

It is based on a steam'line break accident at end of core life.

c.

It is based on having a positive moderator temperature coef+icient at beginning of core life.

d.

It is based on a rod withdrawal accident while in the source range at beginning of core life.

ANSWER b.

(1.0)

REFERENCE T.S.

BASES 3/4.1.1 LO 2NT213 OBJ 1.1.2

KA 192OO2K114 s

3'.

I 7

.Y 9

/

lj :

L '}l,-

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L GROUP 1 COMPONENTS

OUESTION 1.15 (1.0)

+.

_3 ~.

MULTIPLE CHOICE (Sel ect the correct answer )

The Boric Acid Makeup controller is set to AUTO for makeup to the VCT.

f a

Which of the following indicates when the makeup to the VCT will start and stop?

a.

Start < or = 37% --- Stop > or = 51% level in VCT.

b.

Start > or = 37% --- Stop < or = 51% level in VCT.

{-

c.

Start > or = 51% --- Stop < or = 88% level in VCT.

I,)

d.

Start > or = 37% --- Stop < or = 88% l evel in VCT.

Y

),a

. j.

+ ANSWER

.g.

a.

(1.0)

REFERENCE SD-SO23-390 LO 2IC201 OBJ 1.1.2

KA' 191003K101 k

l

[

f

I:

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'f f,

k

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DUEST YON 1.16 (1.0)

MULTIPLE CHOICE (Select the correct answer)

If the operator attempted to close a 4160 volt bus supply (excluding Diesel Generator output) breaker WITHOUT turning on the synchroscope, would the breaker close?

a.

Yes, but the synchroscope circuit will delay actual breaker closure until both lines are in phase.

b.

Yes, because closure interlocks are bypassed when the oncoming bus is deenergized, c.

No, because the two lines may be out of phase and breaker closure could damage the breaker.

d.

No, because the synchroscope is interlocked with the breaker t'

closure circuitry.

I f

I L

ANSWER d.

(1.0)

REFERENCE SO23-6-2 PG 4 3

LO 2ES201 LO 1.1.7 j.

KA 191008K107 i

k

(.

i e

y,.

[.

i I

l

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l L,

f L

OUESTION 1.17 (1.O)

MULTIPLE CHDICE (Select the correct answer) spr

{

\\

<.r.

A CVCS Positive Displacement Pump is operating-with the discharge valve closed and the relief valve is. i noperati ve.

Which one of the f ollowing is likely to occur?

a.

Cavi ti t ati on.

b.

Decreased pump speed.

c.

Viscosity loss.

' d.

Vapor binding.

Yr, P.

ANSWER f'.

b.

(1.0)

REFERENCE HTFF PG 319-329 LO 2FD203'OBJ 3.2

KA 191004K121 i

h Le e

,L

.y n y;3

h, p

DUESTION 1.18 (1.0)'

MULTIPLE CHOICE (Select the correct answer)

Prior to closing any alternating current circuit breaker, the two power sources must be in phase to prevent component: damage.

How is this requirement assured when closing the Diesel Generator 2 GOO 2 output breaker?

a.

The output breaker i s interlocked with the synchroscope to prevent closing unless both lines are in phase.

b.

The output breakers are always closed onto a deenergized bus so that paralleling is not necessary.

c.

The operator must properl y parallel across the breaker, no electrical interlocks are provided.

(

d.

All 4.16 KV breakers are the break-bef ore-make design which allows f or any breaker closing sequence.

ANSWER a.

(1.0)

REFERENCE 5023-2-13 PG 67 LO 2ES202 DBJ 1.1.2

KA 191008K107 E

k

- i -

~

r

+

~

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4 U

_ac._.-

O e

e

-w ep y

e-

.y e.

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,e

OUESTION 1.19 (1.0) t1ULTIPLE CHOICE (Select the correct answer)

What type (s) of radi ation i s/are measured by a Pocket Ionization 1

Chamber Dosimeter?

a.

Gamma only, b.

Gamma and Beta.

c.

Gamma and Neutron.

d.

Gamma. Beta, and Neutron.

ANSWER a.

(1.0)

REFERENCE i

SO123-VII-4.8 PG 5 LD 2HP205 1.4.2.2

(

KA 191002K119 I

s r

e s

Y

.i

F p

1 i.

r 1

DUESTION 1.20 (1.0)

NULTIPLE CHOICE (Select the correct answer)

.m What type of detector is used for the Source Range nuclear instrumentation?

a.

Compensated lon Chamber, b.

Fission Chamber.

c.

Proporti onal Counter.

d.

Geiger-Mueller Counter.

At45WER

{E b.

(1.0) e

'.y.

}

REFERENCE j-SD-SO23-470 PG 5

{!

LO 2HP205 OBJ 1.2

KA 191002K118 sf.

ki; t.

t

.e f

4 3 '.

e v'

i

?

f.i

r v

1 I

QUESTION 1.21 (1.0) t.

MUL TIPLE CHOICE (Select the correct answer)

Procedure 50123-O-23.1, " Valve Operations" speci f i es 'h'ow val ve operation and position verifications are to be done.

Which of the f ollowing will verif y that a Motor Operated Throttle

~

Valve is in the fully closed position?

a.

The operator can depress or rotate the handswitch fcr at least 5 seconds after f ully closed indication is achieved.

b.

The operator can depress or rotate the handrwitch f or approxi mately 133% of stroke time.

I i

c.

The operator can depress or rotate the handswitch f or

)

approximately 175% of stroke time.

f d.

The operator can depress or rotate the handswitch for at L

least 10 seconds after f ully closed indication is achieved.

i fL i

+ ANSWER d.

(1.0)

REFERENCE 50123-0-23.1 LO NOT IDENTIFIED c

KA 191001K108 t

E' i

e tI l

r i

S' i

t r

I

f

QUESTION 1.22 (1.0)

MULTIPLE CHCICE (Select the correct answer)

Indicate which of the f ollowing DECREASES the available NPSH of a centrifugal pumps a.

The pump - discharge val ve is throttled shut, b.

The temperature of the pump suction fluid decreases, c.

The nitrogen blanket pressure on the suction side supply tank increases.

d.

The pump discharge valve is throttled open.

ANSWER ll d.

(1.0)

REFERENCE HTFF PG 319 - 329 LO 2FD203 OBJ 1.6

KA 191004K106 l

1 b

F

-t i

6'

(_ _ _ _ _ _ _

j

.!j r.

j'

OUESTION 1.23-(1.O)

MULTIPLE CHDICE (Select the correct answer)

A motor operated safety related valve was manual.ly shut in the field f or surveillance testing and is being returned to service per SO123-0-23.1, " Valve Operations".

What action' must be taken bef ore the valve is declered f ully operable?

It must be. manually returned to it's original posi ti on.

g..

a.

b.

It must be Denger Tagged until administrative approval is signed by the Shif t Supervisor.

L

,(

It must be electrically' cycled and any applicable ISI or IST c.

periormed.

s

[

d.

The operatin0 M'Chanism must be lubricated with an alcohol

[

and graphite solation.

i

$,1.

ANSWER 1

c.

(1.0)

REFERENCE S0123-0-23.1 PG 7 1

LO NOT 1DENTIFIED

KA 191001K106 e

1 F

i:

.];!

s Ik g

e

- _ = _ _. _ _ _ _

._____m._.__..._m__

e GROUP 2 COMPONENTS

QUESTION 1.24 (1.0)-

. fy

' ~ '

MULTIPLE CHOICE (Sel ect the correct answer)

The number of starts over a given time period is limi ed for the Reactor Coolant Pumps.

Why is' this limit required?

a.

The motor stert capacitors are air cooled and require significant (30 minutes) cool down time.

b.

High motor starting currents can overheat and damage motor windings if adequate cooling time is not allowed.

c.

High heat loads on the motor lube oil system from excessive cold motor starts can cause motor binding.

d.

The split phase induction design motors require high starting currents that may overload supply breakers if a rapid restart i s perf ormed.

ANSWER b.

(1.0)

REFERENCE SO23-3-1.7 PG 4 LO 2XA202 OBJ 5.4.2

KA 191005K106 n.

e f

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

t l'

E

DUESTION 1.25 (1.0) i MULTIPLE CHOICE -(Select the correct answer) g Compare the indications that would be observed if a SDC Pump were started and operated with its discharge flow path isolated, as compared to with its discharge flow path open_(assume runout flow conditions).

What are the i ndicati ons f or the i sol atdd di scharge" case?

a.

Higher starting current and lower running amperage.

b.

Lower starting current and lower running amperage.

c.

Higher starting current and higher running emperage.

E d.

Lower starting current and higher running amperage.

i

ANSWER b.

(1.0)

REFERENCE HTFF PG 319 - 332 LO 2FD203 OBJ 1.2

KA 191005K104 i

i i

a e

'l e s,

4.j L____.__.z__

i Section 2 Emergency and Abnormal Plant Evolutions GROUP 1 EMERGENCY PLANT EVOLUTIONS

OUEST10N 2.01 (2.5)

A fire burning out of control in the Cable Spreading Room has been confirmed by plant operators.

The cable Spreading Room fire suppressi on system cannot be initiated.

a.

What.are the three (3) of four immediate operator action steps that are required by 5023-13-2 " Shutdown f rom Outside the Control Room"?

(1.5)

L L

b.

What are two (2) of the four conditions (not all are necessarily related to Fire) in 5023-13-2 that may require abandonment of the Control Room?

(1.0) w (l[

ANSWER r

?

a.

3@ (0. 5) each 1.

Manually trip Reactor.

2.

Manually initiate MSIS.

3.

Stop all Charging Pumps.

4.

Stop all RCPs.

y r[

b.

Any two @ (0.5) each

[L 0

1.

Dense smoke or uncontrolled fire.

l~

2.

Massive damage to 18cC cabl es.

3.

High Radiation inside Control Room area.

p :

4.

Toxic gas inside CREACUS envelope.

C

REFERENCE SO23-13-2 PG 2 LO 2A0702 - No specific Objective provided.

)

KA OOOO67K304 OOOO68G010 OOOO68G011 t

l 4!

4 I

1 t

l m

- =

a

n

QUEST 1ON 2.02 (1.O)

MULTIPLE CHOICE. (Select the correct answer) v.

j t-A loss of all offsite power has occurred due to a severe 1

electrical storm. Both Diesel Generators are running after manual starts. The operators are attempting to manually place 4160 volt ESF loads on the busses.

Which of. the f ollowing loads must be placed in service first?

1%

Class 1E Pressurizer Heaters b.

Saltwater Cooling Pump l

c.

CCW Pump

l 4

d.

Charging Pump g

ANSWER i.

c.

(1.0)

[

REFERENCE SO23-31-1 PG S LO 2A0701 OBJ 1.3

KA OOOO55A203 OOOO55K302

+

II g.

i 1.

u lt l}

4 lE-s

4 g

1 is u

LL

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-.*OUESTION 2.03

('1. 0 )'

MULTIPLE CHOICE (Select the correct answer)

~

f f:

"n

- A' di agnosis of. an event has led..the operators to procedure s.

5023-12-5,." Steam Line Break".

A' Break Identification Chart is.

used for verifying that the break is a secondary side break and not a~ primary side ~ break.

Which of.the following will determine that the break'is a steam.

m l i n e ?.-

a.

? Containment pressure increasing.

b'.

Activity in thre steam:p1 ant.

f.

.c.

Pressurizer pressure lowering.

c d.

Steam Generator pressure-abnormally low.-

y.

U SANSWER

,y

'd.-

-(1.0)

REFERENCE

-U-S023-12-5.- PG 3 Question f rom f aci1ity Exam 1683 04.9.

LO 2EO705 OBJ 1.1

KA' OOOO40K304 OOOO40A201 f.

'..>p-e i

m r

b n

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{:.

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___1_:._a__._______.___._____.__-___.___..z__..a_

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

s k

OUESTION 2.04

( 1. 0 )

i ML'LT IPLE CHOICE (Select the correct answer) r

~

When re-energizing a dead Vital AC bus f rom i ts al ternate source, 5023-6-17, " Class 1E 120 VAC Vital Bus Power Supply System Operation" requires that all of the 27 distribution breakers must be opened on that bus.

Which of the f ollowing describes the reason for thi s requirement?

The distribution breakers must be open to allow an interlock a.

for the 175 ampere supply breaker to be opened.

b.

The loads f rom each distribution breaker must be sequenced E

on after the bus is reenergized because of possible overload p

of the inverter.

g.

c,.

The loads f rom each distribution breaker must be open to

{,

prevent feedback into the alternate source regulating and step down transformers, e

d.

~

The distribution breakers are not able to accommodate the surge current from the reenergization.

ANSWER i

i

[

c.

(1.0) k

R EFERENCE 5023-6-17 PG 14 LO 2XE210 OBJ 5.1.d

KA OOOO57A101 b

l ).

l5

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fk b

h

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.Y l -[

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OUESTTON 2.05' (1.0)

MULTIPLE' CHOICE (Select the correct answer.)

' &, Ok :._

SONGS 2/3 Technical" Specifications require ALL : moveable' Control Assembli es' to - be OPERABLE and posi tioned within-a speci'fied.

distance;of their.1groupfdemand position. Currently o'ne CEA is

.m'saligned by 18 inches on Unit'3, and the reactor'is at'50%

i

. power. -:

Operation may l continue 'in Mode 1, provided, which of'the following is satisfied?

a..

The-CEA i s realigned within 19 inches Lof the group and the SHUTDOWN MARGIN is verified every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

.b..

.The'.CEA is realigned within 7 inches of the group and,the 3

SHUTDOWN MARGIN is verified every 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.'

The CEA' is realigned within.19 inches of the group and the SHUTDOWN MARGIN is verified every 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ..

d.

The CEA is realigned within 7 inches of-the. group and the SHUTDOWN MARGIN is verified every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ANSWER d.

(1.0) h,

REFERENCE

[

Technica11 Specification 3/4.1.3

_LO 2NT213 OBJ 1.1

KA OOOO5K303 pg.

n

', d. f

v

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4

'y ^0

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l

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-* QUESTION 2.06

( 1. O)

[

Following a Steam Line Break accident, step 9.c of SO23-12-5

- i

" Steam Line Break" has the operators override and stoplAFW pumps associated with the affected Steam Generator.

What concern will arise when MSIS is eventually reset?

(1.0)

ANSWER AFW flow will resume to the affected S/G, and possibly cause a SGTR.

(1.0)

REFERENCE S023-12-5 PG 9-LO 2EO705 OBJ 1.2 L

KA OOOO40K107 p,

i Ip..

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DUESTION 2.07 (1.5)

.The success paths f or recovery of the Heat Removal f unction f

(5023-12-12, " Heat Removal - Priority 5") include the' Steam Generators for three of the four paths. Each path her, one other method or system associated with the f unctional recovery.

What are three (3) of the f our methods or systems that can be utilized for recovery of the Heat Remosal function?

(1.5)

ANSWER 1.

Forced ~ Circulation (RCPs) any 3 @ (0.5) 2.

Natural Circulation 3.

ECCS 4.

SDC

?

y,

REFERENCE y.

S023-12-12 PG 2

^

LO 2EO708 OBJ 2

KA OOOO74K103

.[

w e

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' QUESTIDNi2.08'--

( 1. O)

Y 1

E f Pr ocedure, SO23-12-13 l"Contai nment, Isol ati on -' Pri crity, 6" has.

,l f been entered and a ' manual :. isolation-~ of the containment'.'of SONGS 2 l f

isl being conducted. A ' step - requi res that - i f ; contai nment '.' pressure j

'is greater than instrument' air _-pressure then instrument. air to i

- the containment must be ~ isolated.

i.

h,nat functions will the isolaEion of instrument air disable?

(1.O)

ANSWER r

( 1. O)

~

Letdown *and. normal PZR. spray wi11 be di sabl ed. -

i

REFERENCE' L[

SO23-12-13 PG 11 1.

LO 2XQ207 OBJ 5.8-C

KA

OOOO6 9K301 --

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1

OUESTION 2.09

( 1. O ')

During an E.mergency Boration perf orm' a according to' procedure 5023-12-9, "Reacti vity - Priori ty 1",

the charging pumps are being aligned 'to take a gravity f eed f rom the BAMU tank.

Why must the VCT outlet valve be closed?

(1.0)

ANSWER.

The overpressure from the VCT will prevent the charging pumps from providing borated water from the BAMU tank.

(1.0)

REFERENCE 5023-12-9 PG 3 LO 2A0711 OBJ 1.3 (lesson plan for 401) i LO 2EO"/08 OBJ 2 p

KA OOOC24K302 OOOO24A105

)

it 1

A

+

e

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, k.;..

DUESTION 2.10 (1.0)

The Noncritical' Loop of SONGS 3 CCW has been isolated because of-an apparent rupture. _This removes the capability to monitor for radiation f or a system served by the Noncritical Loop.

What COI1PONENT would be af f ected f or radiation monitoring if the Noncritical Loop is lost?

(1 0)

ANSWER

l Letdown Heat Exchanger (CVCS).

(1.0) s

REFERENCE 5023-13-7 PG 6 LO 2XB201 OBJ 5.7 h

KA OOOO26A107

+

h' c

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.. GROUP II EMERGENCY AND ABNORMAL PLANT-EVOLUTIONS U

..x

-*OUESTION 2.11' (1.0):

3 j, p;n:d.O! ~

.MUL.TIPLE CHOICET(Select"the correct answer.)

fi k SONGSS21has experienced a reactor trip. The plant operators are-performing'SO23-12-1 " Standard Post Trip Actions" Step'3 verifying Reactivity Control Criteria.

'Which'of the, fallowing.will require action per Response not

- Obtained instructions f or Step 3 requiring Emergency.' Boration?

h a.

- All CEAs inserted, reactor power lowering, and turbine tripped.

(

-6.

All CEAs inserted, reactor' power lowering, and startup rate

- negative.

c.

Oric-CEA not inserted, reactor power lowering, and startup

/

. ate negative.

d..

Orie CEA not inserted, reactor power increasing, and startup rate positive.

ANSWER d.

(1.0)

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T MULTIPLE ^' CHOICE 1(Select the. correct answer) y

.m 3.

?W.iv. m.

.m 7

SONGb;2 has experienced a; reactor trip and an inadvertent Safety-Injection.- - The; plant-operators are performing SO23-12-2'"ReactorD oTrip Recovery".

-What:im'one of the conditions-that must'be met prior to-terminating and'iesetting SIAS?

q -.

3 a..

- RCSisubcooling less..than 25 deg.:F.

F ibi Steam Generator level greater than 5%..

as A-

,X.

c.

RCS plenutn level greater than 75%.

1

.., d.,

Pressurizerilevel greater than 30%.

p L

'* ANSWER i

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4 h

d.

.41.0)

l c

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OUESTION 2.13 (1.0)

MULTIPLE CHOICE (Select the correct answer)

Which of the f ollowing indicates a successful transfer of power for the ' Train "B"

startup flux monitor to its alternate source f

for a shutdown from outside the control room?

a.

Power supply transfer switch XS539B has a captive key and the white light is off.

b.

Alternate power supply isolation switch XS539A has a captive key and the white light is off.

c.

Power supply transfer switch XS539B has no key inserted and the white light is on.

d.

Alternate power supply isolation switch XS539A has a captive i

key and the white light is on.

1,-

j

ANSWER e

.{L b.

(1.0)

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QUESTION 2.14 (1.0) l 1

1 MUL11PLE CHOICE (Select the correct answer)

I SONGS 3 is in Mode 5 with the RCS partially drained 'to mid-loop for installation of the. Steam Generator norrie dams..Both SDC pumps (shutdown cooling) pumps are operable with one pump running. Indication shows a loss of all flow has just' occurred.

1 Which one of the following actions should the operator take?

a.

Initiate filling and venting of the system.

b.

Attempt to restart the SDC pump that tripped.

h c.

Start the other SDC pump immediately.

p f

d.

Investigate the cause of the SDC pump trip.

.f -

k

ANSWER 5-[

a.

(1.0)

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QUESTION 2.15 (1.0)

MULTIPLE CHOICE (Select the correct answer)

Indication of a RCS leak is provided by annunciator 57C43

" REACTOR COULANT PRESS BNDRY/ UNIDENTIFIED LEAKAGE ABNORM HI".

Which of the f ollowing chemistry sample from the containment sump results would indicate the leakage is actually coming f rom the Component Cooling Water system?

a.

Nitrates and Boric Acid.

b.

Hydrazine and Boric Acid.

c.

Hydrazine and Ammonia.

d.

Ammonia and Boric Acid.

I

(

ANSWER a.

(1.0)

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OUESTION'2.16-(1.O)

MULTIPLE' CHOICE-(Select the correct answer.)_

.. 2=ue;- = i

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Procedure SO23-12-12, Heat Removal

. Priority.5" has been entered to reestablish the heat removal f unction f ollowing a small LDCA.

Two Reactor Coolant Pumps are running-and-Auxi1~iary Feedwater is about to be' established to one Steam Generator.

Which of the following is an indication.of potential RCP performance that would mandate tripping the RCPs?

a.

RCP thrust bearing' temperature is'198 deg.

F.

b.

One RCP seal has f ailed on both pumps.

c.

RCP. average motor amperage f or both pumps is - 220 amps.

~

'd.

RCP motor. amperage for one pump.is fluctuating by 420 amps.

ANSWER

+

\\

d.

. ( 1. 0) g,

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DUESTION. 2.17

( 1. O )

Annunciator window 63C55."125V-DC D3. BUS' TROUBLE".has,.,

, illuminated. The(Annunciatoriresponse procedure references procedure S023-6 f or action to ' troubleshooting the buis, indications.are that an-undervoltage exists.

.ca

.: q:

.,h k i

What acts on can be taken usi ng ' the charger to~ increase ; voltage; on.

the: bus?.

'(1.0)

ANSWER-i 4

The charger can.' be set. to equalize to;, rai se - the' voltage' -(if appropriate)..

( 1.' O ) -

REFERENCE SO23-5-2.3 PG 58 AND SO23-6-15 PG 7.

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DUESTION 2.18 (1.0) i Control power was lost for a short period of time to Makeup Water to VCT valve FV-9253.

t' What one action must be taken to recover FV-9253 after control power has been restored?

(1.0)

ANSWER The operator must depress both the CLOSE and AUTO pushbuttons for FV-9253.

(1.0)

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DUESTION 2.19 (2.0) 1

! to S023-12-3 " Loss of Cool ant Accident" providet for simultaneous hot / cold leg injection. The attachment describes the method of balancing flows when the RCS pressure is lower than 500 psi a f oll owing a l arge break LOCA.

a.

How much time after the break occurs must simultaneous hot / cold leg injection be initiated?

(1.0) b.

Using Figure HLIF (f oll owing page) what i s the total flow for a RCS oressure of 215 psia?

(1.0)

ANSWER a.

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

(1.0) b.

Appro>:. 740 gpm +/- 5 gpm (1.0)

REFERENCE i

5023-12-3 PG 55 - 63 LO 2EO713 Ne specific Obj provided.

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NUCLEAR GENERATION SITE EMERGENCYOPERATINGI$TRUCTION 5023-12-3 UNITS 2 AND 3 REVISION 1 PAGE 63 0F 65 SIMULTANEOUS HOT / COLD LEG INJECTION FIGURE HLIF soo N\\

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500 309 275 359 475 314 250 364 L

450 320 225 369 V

425 326 200 375 400 3 31 175 3801 375 336 150 385 350 342 125 391 ;

325 347 110 395 300 353

<.110 395 BOTH the HPSI Hot Leg injection Flow AND the Total of the HPSI Cold Leg injection Flows must each be greater then or equal i

to the above values for the indicated I

PCS oress ve te iower o' s 0 03 or P-O*C5 q

0091G ATTACHMENT 5 PAGE 9 0F 4 1

C________________________________-__

t

DUESTION 2.20 (1.0) 1 MULTIPLE CHOICE (Gelect the correct answer) 9.

l' 5023-12-4, " Steam Generator Tube Rupture",.provides actions to T

terminate leakage of reactor coolant into the secondary system following a rLeam generator tube rupttare.

Which method does 5023-12-4 use to identify the most affected SG?

a.

High containment radiat2 an f rom local Area Radiation Monitors.

b.

Any RCS loop. flow greater than 100%, or a 1% difference between loops.

c.

Any SG pressure decreasing in an uncontrolled manner.

I d.

Steam Line and Blowdown radiation monitors.

ANSWER d.

(1.0)

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OUESTION 2.21 (1.0)

MULTIPLE CHOICE (Select the correct answer)

The Emergency Coordinator has told you the Event C15ssi fi c ati on for an inadvertent radioactivity release determination is event code A2-1.

(The Event Codes Tabl e f ollows this page. )

Which of the following describes the event that has occurred?

a.

The event i s an Uncontrolled Release of Radioactivity, the Emergency Classification is an Alert, with a whole body dose at the Exclusion Area boundary of more than 2.0 mrem, b.

The occurrence is a Miscellaneous event, the Emergency Classification is an Alert, with a whole body dose at the Exclusion Area boundary of more than 2.0 mrem.

I c.

The event is an Uncontrolled Release of Radioactivity, the 3

Emergency Classification is an Unusual Event, with a whole body dose at the Exclusion Area boundary of more than 2.0 mrem.

]

I d.

The occurrence is a Miscellaneous event, the Emergency Classification is an unusual Event, with a whole body dose at the Exclusion Area boundary of more than 2.0 mrem.

+ ANSWER j

a.

(1.0)

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NUCLEAR GENERATION SITE E IP 5023-VIII-1 UNITS 2 AND 3 REVISION 5 PAGE 5 0F 58 W&lS~/

RECOGNITION Als CLASSIFICATION OF' EMERGENCIES.

~

ATTACHMENT 1 EVENT CODES TABLE NOTE: Event Codes comprise three charteters which designate the Event Category, the Emergency Class, and the Emergency Action Level:

A:. -L Emergency Action Level k.

l Emergency Class Ii Event Category

[

f-1.

DETERMINE the Event Category designator from the list below:

DESIGNATOR EVENT CATEGORY A

Uncontrolled Release of Radioactivity 8'

Loss of RCS Inventory C

Core Degradation or overheating D

Loss of Safety Equipment i -

E Disaster l[.

F Security Contingency G

Miscellaneous 2.

DETERMINE the Emergency Action Level (EAL) designator as follows:

p a.-

Match plant conditions with the EALs listed in the selected Event Category tabs;

.p b.

Find the highest-level applicable EAL by reviewing the notes following the selected EALs and Event Categories; 3.

OETERMINE the Emergency Class designator from the page title for the selected EAL:

j f

DESIGNATOR EMERGENCY class 1

Unusual Event 2

Alert i

3 Site Area Emergency l

4 General Emergency I

f 1(23). AVI ATTACHMENT.1 PAGE 1 0F "

I t-1

+ QUESTION 2.22 (1.O)

Window 61A20 " AREA RADI ATION MONITOR FAILURE" has ' illuminated due to a failure of the Artificial Background for a scintillation detector.

1 How would an operator determine which ARM has experienced this l

failure?

(1.0)

I

ANSWER The (amber) channel f ailure light will be illuminated on the module et L-099.

(1.0)

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l GROUP III EMERGENCY PLANT EVOLUTIONS 1

+0UESTION 2.23 MULT IPLE CHOICE (Select the correct answer)

In the SONGS 2 control room a reactor trip has occurred, and the operations personnel are performing procedure 5023-12-1 " Standard Post Trip Actions".

Due to adverse plant conditions, all Reactor Coolant Pumps have tripped and CANNDT be started.

Which condition supports or indicates natural circulation tlow?

a.

RCS subcooling iess than 25 deg.

F.

[

b.

RCS Hot Leg temperr.tures stable or decreasing.

E c.

RCS Cold Leg temperatures increasing, d.

RCS delta T greater than 58 deg.

F.

g

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ANSWER b.

(1.0)

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+DUESTION 2.24 (1.0)

SONGS 2 has been in Mode 6 f or three weeks and refueling ope *ations are in progress.

HIGH radiation alarms were just received in the Spent Fuel Pool area.

If the radiation level in these areas was 250 mR/ hour, what is the maxi mum stay time f or a worker with no previous exposure (documented on NRC Form 4) without exceeding 10CFR2O limits?

SHOW YOUR WORK!

(0.25 for answer)

(0.25 f or method)

(0.5 f or limit)

ANSWER 4

1::

10CFR2O quarterly limit is 3,000 mR 1

(this may be inf erred by the problem solution, 0.5) 3000 mR / 250 mR/hr = 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (0.25 for answer, 0.25 for method)

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Section 3 Plant Systems, and Plant-Wide Generic Responsibilities GROUP 1 PLANT SYSTEMS

DUESTION 3,01 (1.0)

The EFAS 1 initiation logic requires at least low level in Steam Generator No.

1, and at least one of two other signals must be present.

)f What are the TWO (2) other signals, either of which, would allow t

the initiation of Emergency Feedwater to the No. 1 Steam Generator?

( 1. O )

i

ANSWER t

I Steam Generator No. 1 pressure not low (>729 psia).

(0,5) or Steam Generator No. 1 pressure greater than Steem Generator No. 2

(>50 psid).

(0.5)

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^* QUESTION 5.02

( 1. 5 ) '

Regarding"the Engineered Safety Features:

Y a.

. WHAT are the actuation setpoints f or the f ollowing Engineered-Safety Features assuming the plant is operating at f ull power?-

1.

Saf ety Injection Actuation Signal (RCS pressure only)

(0.25)

2..

Containment Spray Actuation Signal (0.25) 3.

(1ain Steam 1 solation Signal (0.25).

4.

Recirculation ActJation Signal (0.25) h.

Which of the above,ESF signals-have setpoints.that varv r

under conditions other than full power?

(0.5) p1 r

fD SWER '

g-9 L

v a.

1..

1806 psia RCS (0.25) 2.

16.14 psi'g Contaf.nment (0.25) 3.

.729 psia (Variable)

(0.25) 4.

18.5% RWST level (0.25) b:

h b.

SIAS and MSIS

' ( 0. 5) fl-

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+0UESTION 3.03 (1.5) l 0

I i

Area Radiation Monitors RE-7856 and RE-7857 are located in the j

Containment.

1

'e a.

What automatic actuation signal is initiated by these two units?

( 0. 5 )-

U b.

What elevation are these two monitors located at in the containment?

(0.5)

!)

c.

In what building are the readout / alarm / control modules

j located for these monitors?

(0.5) i

ANSWER L

a.

CPIS (Containment Purge Isolation Signal)

(0.5) i b.

63 feet (refueling deck).

(0.5) c.

Penetrati on buil ding.

(0.5)

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QUESTION 3.04 (2.0)

- The Control Room Isolation' System can be initiated manually or by-a SIAS. signal from'ekther unit..

6+jii; e

a.

.What two-(2).other signals will generate an actuation of'the CRIS?'(No setpoints required.)

(1.0) b.

Why will the bypass swa tch not prevent an actuation f rom i

occurring from either manual,or SIAS signals?

(1.0)

ANSWER.

a.

1.

Gaseous activity high.

( 0. 5 's 2.

Particu1 Ate and Iodine High.

.(0.5)

If b.

The bypass. switch only blocks actuation from the PERMS RE-7024-1'and RE-7825-2.

(1.0) t' I

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QUESTIDN 3.05:

( 1. O).

1 MULTIPLE-CHOICE.(Select;the'correst answer.-)-

4 041 r The Qualified Saf ety' Parameter. Di sp1 ay System (OSPDS) providen an

' indication of'Subcooled Margin and utilizes several? inputs for temperature 2nd. pressurizer pressure.

' ;> l

-,Which of. the following;are representative of.the regions that' OSPDS determines ' Bubcooled ' Mar giri?

a.

The RCS Hot' Legs;' Upper;; Head of~the.VesselgiCore Exit-

_(

'b.-

The RCS-(all)p Upper Head of the Vessel; and the RCS Hot'

. Leys.

c.

The ' maximum. of the RCS c,e the Upper Head, ' and.- the. Core Exit.

^

.d.

The Upper Head of.the Vest.el and the Core Exit.

ANSWER s

c.-

11.0)

.v

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+ QUESTION 3.06 (1.0)

MULTIPLE CHOICE (Select the correct answer.)

The Auxiliary Feedwater piping to the Steam Generators contain check valves.

Which of the f ollowing describes the ef f ec.f-the backl eakage f r om the Steam Generators would have on the Auxiliary Feedwater pumps?

a.

The backleakage may cause e>:cessive discharge pressures when the pumps are called on to start.

b.

The backleakage could cause mechanical binding of the pumps when they are called on to start.

f' c.

The backleakage could cause the pumps to become steam bound I

when called on to start.

d.

The backleakage could cause the pumps to overheat the pump packing.

t i

+ ANSWER c.

(1.0)

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QUESTIDfJ 3.07 (1.0)

Reactor Conl ant Pump Seal bleedoff flow is normally routed to the VCl.

'".s Where would the flow be routed if a Containment Isolation Signal (CIAS) is present?

( 1. 0 ) -

3

ANSWER Through a (150 psi) re12ef val vre into the quench tank.

(1.0) t

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QUESTION 3.08 (1.0) e Answer the f ollowing questions concerning the Chemical and Vol ume Control System (CVCS).

a.

What is the f unction of the backpressure control valven located downstream of the let-down flow control. valves?

(0.5)

\\

1 b.

What heat load within the CVCS is cooled by the CCW system?

(0.5)

ANSWER a.

They prevent f l ashi rtg in the let-down heat exchanger.

(0,5) hm b.

The letdown heat exchanger.

(0,5)

REFERENCE

(-

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QUESTION 3.09 (1.0) j l

MULTIPLE CHGICE (Select the correct answer. )

Which'of the following will cauee a Main Feedwater Pump to trip?

a.

Feedwater Header pressure is 1400 psig.

b.

MFW' Pump suction pressure is 245 psig c.

MFW Pump speed is 5780 RPM.

d.

MFW Turbine lube oil pressure is 6 psig.

ANSWER i

c.

(1.0)

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,*DUESTION.3.10-

'(1.0)

.,n.

'I.')

1

..,_2 s

Ddring a release?of, Gaseous Radwaste the automatic'isolatica dvalve1 in3:the:decayLtank: discharge header can be iso 1%tedhon the:

A i

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receipt'of either;of'two: isolation signals.

( -,

~

s

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What;ar'e those TWO'-:(2)? isolation signals?

. s[ ' .'

(1.0).

M m

_.* ANSWER

,m 4

- AnyL2/S,O'.5',,

. r.

LHighERadi ati on RE-7865.

g

'High Radiation RE '7808.

b.Y

. Loss:of all fans in the. exhaust plenum, p

P

. 7* REFERENCE

>SD-SO23-660' PG-33 AND 5 1.0 2XR206 OBJ 3.5

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QUESTION 3 11 (1.0)

MULTIPLE CHOICE (Select the correct ans wer. )

Which one of the following control rod interlocks is bypassed, when operating the CEDMCS in the Manual Individual mode?

a.

Upper. Electrical Limit (UEL) b.

Lower Electrical Limit (LEL)'

c.

Control Element Withdrawal Prohibit (CWP) d.

Upper Group Stop (UGS)

ANSWER 4

[

d.

(1.0)

REFERENCE SD-SO23-510 PG 45, 37, AND 38 LO 2X1203 OBJ.5.2

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., _ '.V e:

I f.

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m.____m_. _. _ _ _...

b

QUESTION 3.12 (1.0)

MULTIPLE CHOICE'(Select the correct answer.)

.m-,

The Source Range Count Rate indication will shut off during a startup automatically when it is no longer needed.

Which of the f ollowing is the point at which the Source Range Count Rate indication will shut off?

a.

2X 10'

% power b.

1 X 40~

counts per second c.

1 X 10~

% power d.

1 X 10~

% power

-* ANSWER c.

(1.0)

?

REFERENCE SD-SD23-470 LD 2XC208 OBJ 4.0 (No specific objective)

KA 015000K404 I

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QUESTION 3.13-:

( 1. O) -

1

' SONGS : 2 'Li s 'i n '.Mocte 4, due 'to continuing : drain valve l eakage-- a '-

Saf ety InjectionHTank has ' to" have lits level ' increased [

. Why:must RCS pressure be greater than.1600 psig.praor to Jinitiating the filling:of.the SIT'with the HPSI system?

(1.0)

ANSWER-

To: ensure no flow enters the RCS through the-SI check valves from.

'.the HPSI. system'(discharge. pressure is 1500 psig).

(1.0)

REFERENCE SO23-3-2.7.1 PG B LO 2XA207 OBJ 5.3.1

}

. *KA OO6020K601 1

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p 1

s v

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'*DUESTYDN 3.14 (1.0)

HULTIPLE CHOICE (Select the correct answer.)

a Normally one Chilled Water Pump is operating and one unit is in stendby.-

If the control for the standby pump is in AUTO, what condition

would cause the pump to start?

a.

Low discharge pressure (35 psig) of the operating pump.

.L b.

High temperature in the discharge (110 deg. F) of the operating pump.

c.

High discharge pressure of the operating pump.-

F d.

High temperature in the discharge-(45 deg. F.) of the h-operating pump.

l-

f4NSWER a.

(1.0)

REFERENCE SD-SO23-770 PG 15 LO 2XB203 OBJ 3.3.1

+KA 022OOOK104 c

. 1 D

p l-C_________

I A

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,!.?

OUESTION 3.15 (1.0)

A discharge of Coolant Radwaste is in progress to the. Circulating j

Water Outfall.

r What'TWO (2) conditions will cause an isolation of the discharge to'the Circulating Water Outfall?

(1.0)

ANSWER Any 2 G O.5 each

~

Hi gh Radi ati on on' RE-7813.

Channel failure of RE-7813 (i solates HV-7642 and HV-7641 ).

j-Stoppage of all Circulating Water Pumps for Unit involved (isolates either 2HV-7644 or 3HV-7644).

REFERENCE I

SD-SO23-505 GP 11, AND 13 I

LO 2XR205 OBJ 4.3.c f;

KA 069000A302 0680004404 fy

-i p

7 1 1 1

i

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GROUP II PLANT SYSTEMS

DUESTION 3.16 (2.0) 1-- ;

Regarding the Containment Recirculation Filtration Units a.

When is the Containment Recirculation Filtration unit utilized for reducing airborne concentrations of radioactive i

particulate?

(1.0) b.

' The Contai nment Recirculation Filtration unit uses a pre-filter and what two (2) other types of filter media?

(1.0)

ANSWER a.

The unit is operated prior to a purge operation and prior to personnel entry.

(1.0) b.

HEPA and Charcoal.

(1.0) k

REFERENCE SD-SO23-770 PG 34 LO 2XA209 OBJ 2.0 (No specific objective) l

KA 029000K105 029000K401 029000 GOO 4 k-L.

I a

r I

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DUESTION 3.17:

- ( 2. 5 ) -

The Diesel Genrators are running after starting:from.a.SIAS.-

signal..

%;o e m:

a..

What three ' (3) trips are not def eated < when 'a SI AS signal i s-present?

4 (1.5) b.

What two.(2). operator methods,.in the~ Control Rootn, woul d s

stop the Diesel. Generators when a SEAS signal-is present?

(1.0)

.* ANSWER a.

.Overspeed

( 0. 5) '

F Low Gil Pressure (0. 5) ~

U Generator Di f f erential (0,5) i

'b.

Depressing both:SIAS ovtrride stop buttons..

(0.5)

Placing. the Maintenance switch in ' Maintenance.

(0.5)

REFERENCE

SD-SO23-750 PG 28,.29 LO:2XEA06 OBJ 5.4 AND 3.8

KA 064000A406 -064000K402 064000K401 062OOOK102 062OOOK401 p

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1, nJ-.

QUESTION 3.18 (2.O)

For. each :'of thel f all owing. Vi tal. DC. Ioads, what is,t'he particular T

. component that is affected-if power is lost to that_ load?L w..

a.-

Dus D3 -' Turbine Driven Auxiliary'Feedwater PumpiPanel.

L-299.

. (0.5) 1

.b.

Bus-D4 - Inverter for HV-9378.

(0. 5) L c.

IBus D2 - Control' Panel L-160.

. (0.5) d..

' Bus D3 - Breaker Cabinet-L-33.

.(0. 5):

ANSWER I

a.

AFWP Steam Inlet: Valve HV-4716 (P-140)..

-: (0.5) b.

'HV-9378'~is Suction Isolation Valve for SDC.

(0.5) f f[

c.

GOO 3 Diesel Generator Control.

(0.5)

~

d..

Reactor Trip Circuit Breaker (Reactor Protection).-

(0. 5).

REFERENCE SD-SO23-139, AND 140 LO 2XE210 OBJ 5.3 (Objective Non-Specific)

KA

'063OOOK201 063OOOK302

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f. ' -

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_____._____E_______________._

l

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QUESTION 3.19 (1.0) l MULTIPLE CHOICE (Choose the correct answer.)

S-1 i

Which of the f ollowing is true about the T-ave indication?

a.

A closed circuit in an RTD based system will cause an infinite resistance, thereby indicating a high temperature.

b.

An open circuit in an RTD based system will cause an infinite resi stance, thereby indicating a high temperature.

c.

An open circuit in an RTD based system will cause a lowered r esi st ance, thereby indicating a high temperature.

d.

An open circuit in an RTD based system will cause an k

infinite resistance, thereby indicating a low temperature, ir

ANSWER I

b.

(1.0) t

REFERENCE SD-SO23-710 LO 2XA202 OBJ 4.0 (No specific objective)

KA 012OOOA205 191002K114 I

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DUESTION 3.20 (1.0)

MULTIPLE CHOICE (Select the correct answer.)

Why will Pressurizer l evel indication INCREASE when there is an increase of 20 deg.

F.

in the reference leg?

a.

The density of the fluid in the reference leg increases.

b.

The increase in temperature biases the calibrated output of I

the transmitter upward.

c.

The density of the fluid in the reference leg decreases.

d.

The increase in temperature biases the calibrated output of f

the transmitter for the reference leg.

5

ANSWER v

l c.

(1.0) h

REFERENCE

[

HTFF PG 273 - 285 LO 2IC201 OBJ 1.1

+KA 011000K402 011000A101

)

4 L

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QUESTIONe3.21 (1.5)

'i

. The :1evel setpoint' f or the. Pressurizer Level: Contr ol '.sy stem

-varies with the RCS average temperature (T-ave)..

Why does the' Pressurizer.' level programmed 1evel vary with'

~

a.

changes that occur-in.RCS temperature?

(1.0)

),

b.

'What system:provides.the! program signal to'the-Pressurizer t.evel. Control system for level?

(0.5)

ANSWER

.a._

To minimize RCS ' mass changes f rom changes of density due to

~

' temperature. changes.

( 1.. C )

b.

.The Reactor Regulating-System.

- ( 0. 5) '

f

.* REFERENCE

'SD-SO23-360 PG 57~

l'

'LO 2XI202 OBJ 1.3 AND 3.0

KA.

OO2OOOK508 OO2OOOK109.OO2OOOK407 l$

b i.

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. i-* QUESTION 3.22.

( 1. 0 )4 L

~

MULTIPLE CHOICE ' (Select ' the : correct answer. )

lb r

3 q,g v-p t

(2;

'.f ).

'2

~

Which.of. the f ollowing power _ ' suppl y arrangements f or.t'>he

' G PressurizercHeaters are correct?;

$. g,y

. a.f Backup-Heaters Power Supply (Bus) s.

. B-l '

'B02-

'B-2 i

B02' B-3:

. B02 : -

p;-

f B-4 BOB B-5 BOB B-6 BOB b.

Backup Heaters

. Power Supply (Bus)-

B-1 '

B02 I~

B-2 B02 B-3 BO2 L

B -

B06 E-B-5 B06 t

B-6' BO6 c.

Backup Heaters.

Power. Supply (Bus)

-B-1 BO6 B-2 B06 B-3 B06 B-4 BOB k

B-5 BOB'

{: --

B-6 BOB r

LJif i, d.-

' Backup Heaters Power Supply (Bus) a y.I.-

B -

B02

(

h B-2

'BO2-B-3 BO4

.B-4 B06 B-5 BO'8 B-6 BOB

ANSWER s

3

- d.

( 1. 0) -

J.;

REFERENCE N ;..

t jM*h,.g.

SD-SO23-360 P.'

144 LO 2XA202 DBJ 2.0 (No specific objective) w-

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i* QUESTION 3.23 (1.O) i

{

i

,HULTIPLE CHOICE-(Select'the correct answer..)

...k%

i r-

~*

r 4

An! event ' has. Just : occurred where the possi bili ty ofi voiding '

occurring in the.' upper head of the Reactor.. Vessel mayfte indicated.

l n

Which of the f ollowing-is true about the OSPDS indication for.

l level in.the RCS. Vessel Head?

-m.

The indication' system utilizes 5 Heated Junction

. i j

y

. Thermocouple (HJTC)," detectors for level in the Head.

I b.-

The indi' cation system wi11 ' indicate when level in the Head '

reaches 50%=of:the distance'between the Head'itself and the l

Hot Leg.

.c..

.The indication system will indicate when level in the Head i'

reaches 80% of the distance between the Head itself and'the I

Upper Guide Structure Support Plate.

I,'

"d.

The indication system-utilizes a di f f erential of 200 deg.

F' in the circuitry to provide indication that voiding has occurred at a locati'on of HJTC pairs.

ANSWER s

d.

(1.0)

- l

\\

I

'

REFERENCE l

SD-SO23-820 PG.52 AND-77

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{

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?

MULTIPLE CHOICE (Select the correct answer.)

f Which of.the following is true about the monitoring of Spent fuel Pool /Ref ueling Canal water level during Ref ueling Operations?

a.

A High level of the Spent Fuel Pool and Refueling Canal cannot be monitored in the Control Room, b.

Low l evel indication via LHSL-7740 is only a local horn alarm in the Spent Fuel Pool area.

c.

Low l evel indication vi a LHSL-7740 is annuciated in the Control Room.at panel CR-61C.

t d.

The High level alarm occurs at elevation 65 f eet in the

~~

Control Room at panel CR-61C.

k

ANSWER p-c.

(1.0)

.c

REFERENCE i

SD-SO23-430 PG 90 LO 2XB204 OBJ 4.1.b

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QUEST 10N 3.25 (1.O)

MULTIPLE CHOICE (Select the correct answer.)

The Technical Specifications' require that the Emergency Diesel Generators have an operable fuel oil system.

.1hi ch. of the following would meet the MINIMUM requirements for operability as described in the Technical Specifications for the fuel oil system for ONE Diesel Generator for Mode 1?

a.

A day tank with 325 gallons, a fuel storage tank with 55,000 gallons, and an operable fuel oil transfer pump.

b.

A day tank with 275 gallons, a fuel storage tank with 47,000 gal l ons, and an operable f uel oil transfer pump.

I J

c.

A day tank with 325 gallons, a fuel storage tank with 55,000 gallons, and two operable fuel oil transfer pumps.

d.

A day tank with 325 gallons, a fuel storage tank with 47,000 gallons, and an operable fuel oil transfer pump.

+ ANSWER d.

(1.0)

REFERENCE T.S.

3.8.1.1 SD-SO23-750 PG 65 - 70 LO 2XEA06 OBJ 2.6

+KA 064000K608 5

t I

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?

QUESTION 3.26 (1.0)

MULTIPLE CHOICE (Sel ect the correct answer.)

c The' Circ Water system is operating in a degraded condition due to seaweed building up on the screens.

a.

This is an indication of excessive flow through the Circulating Water System, b.

The condition can be verified by observation of the Circ Water pumps motor current.

c.

Degraded performance of the Circ Water is limited by a temperature difference of 30 deg.F.

u d.

The problem can be alleviated by opening Gatr 5 and allowing f.

some recirculation.

F

ANSWER b.

(1.0)

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KA 075000A201 k

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GROUP III PLANT SYSTEMS-

DUESTION 3.27 (1.0)

. g g:*

What component wilI prevent the instrument air system from continuing to discharge into the containment if the. instrument a i.- line ruptures in the containment?

G (1.0)

ANSWER There is an excess flow check velve in the line that isolates if the flow rate is excessive (200 sfem).

(1.0)

REFERENCE SO23-1-1 PG 10 AND SD-SO23-570 PG 5

(

LO SXO207 OBJ 2.1.7

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KA 078000K302 011000K406 011000K207 i

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)

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QUESTION 3.28 (1.O)

The Steam Bypass Control System normally actuates when a load rejection occurs.

What event will cause a quick opening " block" of the SBCS valves?

(1.0)

ANSWER Reactor tri pped. wi th T-ave l ow.

(1.0)

REFERENCE SD-SD23-175 PG 30, AND 41 LO 2XI205 OBJ 3.2

KA 04102OK417 s

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u.--2.-. - _ _ _ _ - _ - _ _ - _ _ _ _ _ _ - _ _. _ _ _ _ _ - _

m-.m

4

DUESTION 3.29 (2.0)

The Low Temperature Over Pressure (L-TOP) r el i ef valve provides t protective feature for the Shutdown Cooling System when it i s aligned to the RCS. The relief capacity of the valve is based on two events, one of which is an inadvertent SI AS while the RCS is solid.

a.

What other possible event is used to base the capacity of the relief valve?

(1.0) b.

Where, in the suction line, i s the L-TOP valve l ocated?

(1.0)

ANSWER L

a.

Starting a RCP with a S/G 100 deg.

F.

higher than the RCS.

).

(1.0) 6.

Between the inside and outside containment isolation valves.

h (1.0) f

REFERENCE ED-SO23-740 PG 3B LO 2XA203 OBJ 2.1

KA GO5000K401 OO5000K407 tr' Ik N

f J

u

o

QUESTIOld 3. 30 (1.O)

Regarding the Component Cooling Water System a.

What is the normal supply of makeup water for the CCW System?

(1.0) b.

What is the emergency source of makeup water for the CCW System?

(1.0)

ANSWER a.

Nuclear Service Water.

(1.0) b.

Firemain (through a connection at the NSW connection). (1.0)

REFERENCE-SD-SO23-400 PG 24, AND 6.

a LO ?XD201 OBJ 1.3.10

KA OO8010K101 1

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v' 4

.u.--.

1

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4 1.

OUESTION 3.31 (1.0)

The Saltwater Cooling System is can 'ae aligned such that one train draws suction on the opposite unit's intake structure, and the other train f rom it 's own unit 's intake structure.'

a.

What is the purpose of this alignment?

(0.5) b.

What system normally supplies the bearing and seal water to l

the Saltwater Cooling Pumps?

(0.5)

ANSWER a.

To ensure that a single f ailure of a units' intake structure does not render both Saltwater Cooling trains inoperable.

(0.5)

h-b.

Service Water System.

(0.5) f

+ REFERENCE j

SD-SO23-410 PG 5 f-LO 2XB202 DBJ 1.3 AND 5.1

'(

+KA 076000K406 t

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.p

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e PL ANT WIDE GENERICS

QUESTION 3.32 (2.0)

What are the minimum administrative lioits f or each of the following postings?

a.

Cauti on Radi ati on Area" (0.5) b.

" Caution High Radiation Area" (Not locked exclusion area.)

(0.5) c.

" Caution Contaminated Area" (Beta / Gamma only)

(0.5) d..

" Caution Airborne Radioactivity Area" (0.5) j

ANSWER

[$;.

a.

2.5 mrem /hr (at 18 inches)

(0.5) r

[.

6.

100 mrcm/hr (at 18 inches)

(0,5)

P c.

1000 dpm/100cm (0.5)

P d.

in excess of 25% of MPC (0.5)

REFERENCE SO123-VII-7.4 PG 5 - 6 LO 2HP204 OBJ 1.8

KA 194001K103

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f-

QUESTION 3.33 (2.O)

Procedure 50123 O-27,

" Key Control" goveras the issue of facility keys to personnet.

e.

Which two staff positions may issue keys f or Vital Area locks?

(1,0) b.

How long may a Non-security key normally be issued to an individual?

(0.5) c.

Who may approve the issuance of a Non-security key for longer than the normal i nterval?

(0.5)

ANSWER a.

The NOA or the SRO Operations Supervisor.

( 1. O) b.

No more than one shift.

(0,5) c.

The SRO Operations Supervi sor.

(0,5)

E'

REFERENCE S0123-0-27 PG 3 - 5 NO OBJECTIVE IDENTIFIED

KA 194001K105

's l

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- n n.,n n e_ on

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n s -

DUESTION 3.34 (3.0)

Procedure 5023-0-17, " Locking of Saf ety Related Critical Valves and Breakers" describes the controls placed on locked safety related valves and breakers.

a.

What are Red-Label TVD containment pentration valves?

(1.0) 6.

What color are the tapes applied to the handwheels of each of the f ollowing?

1.

Train A valves.

(0.5) 2.

Train B valves.

(0.5) 3.

Train AB valves.

(0.5)

I 4.

Containment Isolation valves.

(0.5)

?

ANSWER

?

l a.

Valves requiring independent verification of posi ti on following repositioning.

(1.0) b.

1.

Red (O.S) 2.

Yellow (0.5) 3.

Red and Yellow (0.5) 4.

Orange (0.5)

REFERENCE SO23-0-17 PG 4 - 5 NG OBJECTIVE IDENTIFIED

KA 194001K101 3.

4 e

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DUESTION 3.35 (2.0)

Occasi onall y " alternate means" of independent verification must be done.

yy a.

What alternate. method may be used to verif y valve, position?

(1.0) 6.

What alternate method may be used to verify breaker posi ti on?

(1.0)

ANSWER a.

When the valve is cycled remotely by observing i ndication of Eflow or pressure changes 3.

(1.0) b.

When a motor for a pump is cycled on and off by observing Camperage, voltage, or equipment rotation].

(1.0)

(One item in brackets required. )

L

REFERENCE SO23-0-23 PG 11 NO OBJECTIVE IDENTIFIED

KA 194001K101 i

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I L

l h

L__ _

QUESTION 3.36 (1.0)-

MULTIPLE CHOICE (Select the correct answer.)

1.

< 3 y, Procedure S0123-0-11, " Station Logs" governs the keepihg of all of the station logs.

How are i ncorrect log entries corrected?

, a.

By drawing a single 'line through the incorrect entry and initialing the entry.

b.

By highlighting the incorrect entry and then initialing the entry in the lef t hand margin.

c.

By drawing a single line through the incorrect entry and informing the SRO Operations Supervisor.

)

L d.

By using a " Red Arrow" next to the entry and then initialing the entry in the left hand margin.

+ ANSWER a.

(1.0)

REFERENCE.

SO123-0-11 PG 9 NO OBJECTIVE IDENTIFIED

KA 194001A106 r

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y 9

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I

+0UEST1DN 3.XX j

A Trip Channel Bypass can be performed on the Plant Protection i

System on only one channel of any one trio at a time and only at the PPS bistable control panel. However, one PPS trip can be bypassed on all four channels at one time at the remote operator j

module in the control room, a.

Which PPS trip f unction can be bypassed simultaneously in the control-room?

b.

At 10 E -5 % of full power a bistable turns of f what THREE (3) features of the Excore Nuclear Instrumentation?

ANSWER f

a.

High Log Power.

j f

i b.

1.

Source Range Countrate i

2.

Audible Countrate 3.

Baron Dilution Monitor f

+ REFERENCE SD-SO23-470 PG 18 AND 11

KA 015000K604 015000K407 015000K405 015000K101

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