ML20006A826

Exam Rept 50-395/OL-89-02 on 891205-07.Exam Results:All Five Reactor Operators Passed Written Exams & Operating Tests

ML20006A826
Person / Time
Site:	Summer
Issue date:	01/12/1990
From:	Ernstes M, Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20006A825	List: ML20006A824 ML20006A826
References
50-395-OL-89-02, 50-395-OL-89-2, NUDOCS 9001300292
Download: ML20006A826 (63)

Text

[9'"!?u UNITO STC. TIS i

o NUCLEAR RECULATORY COMMISslON

["

REGION 41 f

,[

101 M ARIETT A ST RE ET. N.W.

f ATL ANT A, C EORGI A 30323 n

%...../

ENCLOSURE 1 EXAMINATION REPORT 50-395/0L-89-02 j

i Facility Licensee:

South Carolina Electric and Gas Company P.O. Box 88 j

Jenkinsville SC 29065

)

l Facility Nane:

V. C. Sumer Nuclear Station Facility Docket No.:

50-395 l

Facility License No.:

NPF-12 Examinations wire' administered at V. C. Summer Nuclear Station near Jenkinsville, l

South Carolina.

Chief Examiner: //Ntrl

[-( M

/!/3[M titchael E. Ernstes Date Signed i

Approved By*

/ /2/7c

- John F. Mdnro. Chief Date Signed Operator Licensing Section 1 Division of Reactor Safety-i

SUMMARY

i l

Examinations were administered on December 5-7, 1989.

Written examinations and operating tests were administered to five R0 s

applicants, five of whom passed.

l l

l t

i

• EER"a2%gt, v

I i

I REPORT DETAILS l

1.

Facility Employees Contacted:

• K. Woodward. Manager, Nuclear Operations Education and Training

• G. Taylor, Manager, Operations

• S. Furstenberg, Associate Manager, Operations

• V. Kelly, Supervisor, Nuclear Operator Training

• W. R. Quick, Senior Instructor

• G. Lippard, Lead Instructor, Reactor Operator Training

• Attended Exit Meeting 2.

Examiners:

• M. Ernstes, NRC, Region II R. Vinther, PNL i

A. Lopez, PNL

• Chief Examiner 3.

Exit Meeting:

At the conclusion of the site visit, the examiners met with representa-tives of the plant staff to discuss the results of the examinations.

There were no facility comments submitted for the written exam.

The cooperation given to the examiners and the effort to. ensure an atmosphere in the control room conducive to oral examinations was also i

noted and appreciated.

t The licensee did not identify as proprietary any material provided to or reviewed by the examiners.

I i

v

DRAFT COPY I

U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 2 FACILITY:

V. C. Summer 1 REACTOR TYPE:

PWR-WEC3 DATE ADMINSTERED: 89/12/04 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

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

The passing grade recuires at least 80% correct overall.

Examination

+

papers will be pickec up four and one half (41/2) hours after the examin: tion starts.

CATEGORY % OF NUMBER VALUE TOTAL CORRECT CATEGORY 29.50 36.88 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (36%)

50.50 63.13 PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%)

80.00 OVERALL

% CORRECT OVERALL All work done on this examination is my own.

I have neither given nor received aid.

1 Candidate's Signature

)

DPAFT COPY

[

,]

l MERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 2 (36%)

QUESTION: 01 (1.00)

WHICH ONE (1) of the following describes the response of the component cooling water pump A" to a loss of offsite power in conjunction with a SI signal */ ASSUME the pump is operating.

(1.0) a.

Pump continues operation without interruption, b.

Pump stops and is restarted by ESF loading sequencer.

c.

Pump stops and will not restart until offsite power is restored.

d.

Pump continues operation until standby. pump is started by ESF loading sequencer, then shuts down.

l ANSWER:

01 (1.00) b.

[+1.0)

REFERENCE:

1.

VCS: Component Cooling Water, p. 26. Enabling Objective #1,

[

4 and 8.

2.

KA 000026A202 (2.9).

000026A202

..(KA's)

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

~ E'MERGENCY AND ABNORMAL PLANT FVOLUTIONS Page 3 (36%)

QUESTION: 02 (1.00)

WHICH ONE (1) of the following items would NOT be a consequence of a continuous control rod withdrawal per A0P-403.3 " Continuous Control Rod Withdrawal"t (1,0) a.

RCS Tavg Tref Deviation, b.

Rod Control Urgent Failure.

c.

Reactor Power-Turbine Power Mismatch d.

Overpower Delta T Rod Stop ANSWER:

02 (1.00) b.

[+1.0)

REFERENCE:

1.

VCS: A0P 403.3, " Continuous Control Rod Withdrawal," p.1.

2.

KA 000001A205 (4.4) 000005G005 (3.1).

000005G005 000001A205 (KA's)

QUESTION: 03 (1.00)

WHICH ONE (1) of the following symptoms would be an indication of a loss of condenser vacuum ac:ording to A0P-206.1, " Loss of Condenser Vacuum"?

(1.0) a.

Increasing pressure in the steam sealing header.

b.

Decreasing electrical load with constant steam flow, c.

Decreasing circulating water inlet temperature.

d.

Decreasing condenser hotwell level.

(*****

CATEGOR) 2 CONTINUED ON NEXT PAGE *****)

u---

. ----. - -- ---a

~

n w

EhERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 4 (36%)

i i

t ANSWER:

03 (1.00) b.

[+1.0) i

REFERENCE:

1.

VCS: A0P-206.1, " Loss of Condenser Vacuum," p. 1.

2.

KA 000051G001 (2.7) 000051G011

..(KA's)

QUESTION: 04 (1.00)

WHILH ONE (1) of the following actions is used to ct,11 apse a void according to E0P-18.2,

• Response to Voids in Reacto-Vessel"?

ASSUME a void, exists in the reattor vessel with al', RCPs stopped.

(1.0) a.

Decrease temperature while maintaining system pressure.

b.

Increase system pressure using pressurizer heaters while maintaining pressurizer level.

7 c.

Start a $1 pump to increase system pressure while keeping temperature constant.

d.

Fill pressurizer solid and vent the reactor vessel head.

ANSWER:

04 (1.00) b.

[+1.0) e

REFERENCE:

1.

VCS:

E0P-18.2, " Response to Voids in Reactor Vessel," p. 5.

l 2.

LA 000074K311 (4.0).

]

000074K311

..(KA's)

)

I

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

tt a w EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 5 (36%)

QUESTION: 05 (1.00)

WHICH ONE (1) of the following is an immediate operator action for E0P-6.0,- " Loss of All ESF AC Power"?

(1.0)

{

a.

Place CCW pump switches in pull to lock or 0FF position.

b.

Check if Letdown Isolation Valves are closed, c.

R a tore AC pt;..u to at least one (1) ESF bus, d.

Check main steamline isolation and bypass valves are closed.

a ANSWER:

05 (1.00) i b.

[+1.0)

REFERENCE:

3 VCS:

E0P-6.0, " Loss of All ESF AC Power."

E.

KA 000055G010 (4.1).

000055G010

..(KA's)

QUESTION: 06 (1.00)

WHICH ONE (1) of the following actions must be performed FIRST following Pressurizer Pressure Channel PT-444 failing HIGH, according to A0P-401.5, Pressurizer Pressure Control Channel failure?"

(1.0) a.

Close PORV block valve MVG-8000B.

b.

Close pressurizer PORV 4448.

c.

Defeat pressurizer channel PT-444, i

d.

Place pressurizer pressure control in manual.

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

5MERGENCYANDABNORMALPLANTEVOLUTIONS Page 6 (36%)

ANSWER:

06 (1.00)

I b.

[+1,0]

j

REFERENCE:

j l.

VCS: A0P-401.5, " Pressurizer Pressure Control Channel Failure."

2.

KA 000027A215 (3.7) 000027G0ll (3.7) 000027A215 000027G011

..(KA's)

QUESTION: 07 (1.00)

WHICH ONE (1) of the following, in addition to T/Cs NOT less than 1200 deg F, also represents a solid line path for core cooling assuming subcooling cor.dition is less than zero?

(1,0)

At least.One RVLIS RCP Running Core Exit Temperature Vessel Level a.

no greater than 700 deg F greater than 40%

b.

yes less than 700 deg F greater than 40%

c.

no greater than 700 deg F less than 40%

d.

yes less than 700 deg F less than 40%

1 ANSWER:

07 (1.00) c.

[+1.0]

~

l l.

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

L l

0 EMERGENCY AND' ABNORMAL PLANT EVOLUTIONS Page 7 l

(36%)

REFERENCE:

1.

VCS:

E0P-14.0, " Response to Inadequate Core Cooling."

2.

VCS:

E0P-12.0, " Monitoring of Critical System Functions,".

3.

KA 000074G0ll (4.5).

000074G0ll

..(KA's)

QUESTION: 08 (1.00)

WHICH ONE (1) of the following Critical Safety Function conditions should have first priority? ASSUME a steam line break has occurred and SI has actuated.

(1.0) a.

S/G narrow range level is less than 30% with feedwater flow at 300 gpm.

b.

Containment pressure is at 24 psig.

c.

A 128 deg F cooldown occurred in eight-(8) minutes resulting in RCS cold leg temperature at 220 deg F.

d.

PZR level is being maintained at 6%.

l ANSWER:

08 (1.00) a.

[+1.0]

REFERENCE:

1.

VCS:

E0P-12.0, " Monitoring of Critical Safety Functions."

2.

KA 000040G012 (3.8).

000040G012

..(KA's)

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 8-(36%)

-l QUESTION: 09 (1.00)

WHICH ONE (1) of the following items will determine the amount of RCS subcooling required during a natural circulation cooldown in accordance with E0P-1.3, " Natural Circulation Cooldown"?

'(1,0) a.

RCS pressure j

i b.

RCS vessel level.

c.

number of CRDM fans running i

d.

amount of EFW flow to S/Gs J

t ANSWER:

09 (1.00) c.

(+1.0]

REFERENCE:

1.

VCS: E0P-1,3, " Natural Circulation Cooldown," p. 4.

2.

KA 000015A121 (4.4).

000015A121

..(KA's)

QUESTION: 10 (1.00)

WHICH ONE (1) of the following correctly discriminates between a steamline rupture inside containment and a small break LOCA?

(1.0)-

t a.

RCS temperature b.

RCS pressure c.

containment temperature d.

containment pressure

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

C EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 9 (36%)

t ANSWER:

10 (1.00) a.

(+1.0]

REFERENCE:

1.

VCS:

E0P 1.0, " Reactor Trip / Safety Injection Actuation,"

step 15, p. 6 and step 28, p. 11.

2.

KA 000040A203 (4.6) 000011A213 (3.7)..

000040A203 000011A213

..(KA's)

QUESTION: 11 (1.00)

WHICH ONE '(1) of the following statements correctly completes the' sentence?

During an ATWS (Anticipated Transient Without Scram) with a loss of feedwater, the operator should.....

(1.0) a.

.. leave the main turbine on line to provide a heat sink for the RCS."'

b.

. trip the main turbine to initiate a reactor trip."'

c.

. leave the main turbine on line.to reduce RCS pressure."

i d.

. trip the main turbine to prevent steam generator dryout. "

ANSWER:

11 (1.00) d.

(+1.0]

)

i 4

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

l u*

e gw

4 iMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 10 (36%)

REFERENCE:

1.

VCS:

E0P-13.0, " Response to Abnormal Power Generation," p. 2.

2.

VCS:

FR-S.1, Bases, pp. 75-77, " Westinghouse Background Information."

i 3.

KA 000029K306 (4.2) 000029K312 (4.4).

000029K306 000029K312

..(KA's)

QUESTION: 12 (1.00)

WHICH ONE (1) of the following correctly states one of the bases for the reactor coolant pump tripping criteria in E0P-2.0, " Loss of Reactor or Secondary Coolant."

(1,0) a.

Minimizes two phase flow in a large break LOCA.

b.

Conserves coolant inventory in a small break LOCA.

c.

Reduces overall plant loads, d.

Prevents accident consequence from exceeding 10CFR100 criteria (site boundary dose limits).

ANSWER:

12 (1.00) b.

(+1.0)

REFERENCE:

1.

VCS:

E0P E-0, " Westinghouse Background Information."

2.

KA 000009K321 (4.2) 000009K323 (4.2) 000009K321 000009K323

..(KA's) i i

J

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

EAERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 11 (36%)

QUESTION: 13 (1.00)

WHICH ONE (1) of the following states the basis for the immediate operator action " Ensure Turbine Trip," according to E0P-1,0, " Reactor Trip / Safety Injection Actuation?"

(1. 0) -

a.

Prevent damage to the. turbine, b.

Prevent uncontrolled cooldown of the RCS.

c.

Conserve and provide decay-heat for turbine driven auxiliary equipment.

d.

Prevent fluctuations in electrical power to the grid as turbine coasts down.

ANSWER:

13 (1.00) 1

.l b.

[+1.0)

]

i

REFERENCE:

i i

I 1,

VCS:

E0P-1.0, " Reactor Trip / Safety Injection Actuation", p.4.

2.

KA 000007K103 (3.7).

000007K103

..(KA's)

Ej QUESTION: 14 (1.00).

i WHICH ONE (1) of the following is NOT a Critical Safety Function monitored by E0P-12.0, " Status Trees?"

(1,0)

I a

Containment b.

Heat Sink c.

Suberiticality d.

Subcooling 1

i l

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

l

a ENERGENCY AND ABNORMAL PLANT EVOLUTIONS Page-12'

[

(36%)

ANSWER:

14 (1.00)

.d.

[+1.0) r

REFERENCE:

1.

VCS: E0P-12.0, " Monitoring of Criticality Safety Functions", p.1 2.

KA 000007G011 (4.1).

000007G011

..(KA's)

QUESTION: 15 (1.00)

WHICH ONE (1).of the following is NOT an immediate action that must be taken according to A0P-404.1, " Audio Count' Rate Malfunction,"

if the audio count rate signal is lost?,

(1.0) a.

Discontinue refueling operations.

b.

Place fuel in a safe condition, c.

Stop all positive reactivity additions.

d.

Immediately initiate emergency boration.

ANSWER:

15 (1.00).

d.

(+1.0)

REFERENCE:

1.

VCS: A0P-404.1, " Audio Count Rate Malfunction."

2.

KA 000032G0ll (3.1) 000032G005- (2.8).

000032G011 000032G005

..(KA's) i

(***** CATEGORY 2 CONTINUED ON_NEXT PAGE *****)

1 4

e

=

m N

M

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page'13 (36%)

QUESTION: 16 (1.00)

WHICH ONE (1) of the following is an indication that natural t

. circulation flow exists per E0P-1.3, " Natural Circulation Cooldown"?

(1.0) a.

RCS delta-T decreasing

-b.

S/G pressure decreasing with RCS T-cold constant.

r c.

RCS or core exit temperature increasing d.

S/G level increasing with constant feedflow b

ANSWER:

16 (1.00) a.

[+1.0]

REFERENCE:

1.

VCS:

E0P-1,3, " Natural Circulation Cooldown."

2.

KA 0000llA209 (4.2) 000015A121 (4.4) 0000llA209 000015A121

..(KA's) i l

l l

i l

l l

i

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

i

' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 14.

(36%)

i QUESTION: 17-(1.00) l WHICH ONE (1) of the following is the reason all reactor coolant pumps are tripped according to E0P-15.0, " Response to Loss of

-Heat Sink"?

(1.0) a.

To get increased safety injection flow by decreasing RCS cold leg pressure.

b.

To conserve reactor coolant -inventory by reducing seal leak off.

c.

To conserve steam generator secondary inventory by reducing heat input to the RCS.

d.

To minimize the possibility of a tube rupture.as EFW is restored to the S/G.

ANSWER:

17 (1.00) c.

[+1.0]

REFERENCE:

l l

1.

Westinghouse E0P Basis FR-H.'1, p. 8.

2.

KA 000054K304 (4.4).

000054K304

..(KA's) i i

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

i c-y.

.-y.g

' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 15 (36%)

l QUESTION: 18 (1.00)

WHICH ONE (1) of the following is an immediate action that must be taken according to E0P-2.4, Loss of Residual Heat Removal System While Refueling" (Condition B), if low-flow is indicated on loop A and B?

(1.0) a.

Verify reactor vessel level at half-pipe or greater, b.

Maintain Refueling Reactor Building integrity.

c.

Stop any core alterations in progress.

d.

Reduce demand on HCV-603A(B)-(A.B RHR Hx outlet).

1 I

ANSWER:

18 (1.00) i c.

[+1.0)

_j

REFERENCE:

1.

VCS: E0P-2,4, Condition B, " Loss of Residu'al Heat Removal System While Refueling," pp. 7 and 8.

2.

KA 000025G010 (3.9).

1 000025G010

..(KA's) l 1

l l

I 1

l q

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

4 ENERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 16 (36%)

QUESTION: 19 (1.00) 1 2

WHICH ONE (1) of the following is an automatic action that will occur on a loss of normal letdown according to A0P-102.1, " Loss of All Letdown Capability't" (1.0):

a.

FCV-122 (Charging flow) will modulate closed.

b.

PCV-145 (Pressure Control). will modulate open.

c.

TCV-144 (Temperature Control) will modulate open.

l d.

LCV-Il5A (Divert valve) will start to divert.

ANSWER:

19 (1.00) a.

[+1.0) i

REFERENCE:

1.

VCS: A0P-102.1, " Loss of All Letdown Capability," pp.1.

and 2.

2.

KA 000028G011 (3.6) 000028G010

..(KA's) l QUESTION: 20 (0.50) e FILL IN THE BLANKS.

Procedure A0P-206.1, " Loss of Condenser eM'b Vacuum", has just been entered. At (a) inches Hg v.aettum; operation of all condenser steam dump valves will be blocked.

Turbine Trip will occur at (b) inches Hg. net!Iliii.

(0.5) c49e,\\a~t&

(***** CATEGORY 2 CONTINVED ON NEXT PAGE *****)

4 4

• +e*---,w-.,,

= - -

• e -

EAERGENCYANDABNORMALPLANTEVOLUTIONS Page 17:

(36%)

i ANSWER:

20 (0.50)

(a) 5.0" Hg' [+0.25)

(b) 8.0" Hg.[+0.25)

REFERENCE:

1.

VCS: A0P-206.1, " Loss of Condenser Vacuum," p.-l.

2.

-VCS:

IC-1, " Steam Dump System," p. 32.

)

3.

KA 000051A202 (3.9),

f 000051A202

..(KA's)

QUESTION: 21 (1.00)

FILL IN THE BLANKS. The listed automatic actions that must be verified per A0P-220.1, " Loss of Instrument Air", include that the reactor may trip on (a) due to the (b) valve (s) failing closed on loss of air.

(1.0).

1 ANSWER:

21 (1.00) l (a) low steam generator level

[+0.5)

(b) feedwater regulating [+0.5) l

REFERENCE:

l 1.

VCS: A0P-220.I, " Loss of Instrument Air," p.1.

2.

KA 000065G012 (3.1).

l l

000065G012

..(KA's) 1 1

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

i J

r, 9

>m a

'-a----

e EfiERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 18 l

(36t.')

~

QUESTION: 22 (0.50)

FILL IN THE BLANK.

Per E0P 1.1, " Reactor Trip Recovery", the operator must ensure Si actuation and go to E0P-l'.0 " Reactor Trip / Safety injection Actuation" if Pressurizer pressure DECREASES BELOW psig.

(0.5)

ANSWER:

22 (0.50)-

1850 (psig)

[+0.5]

REFERENCE:

1.

VCS:

E0P-1.1, " Reactor Trip Recovery", p.5.

2.

KA 000007G011 (4.1).

000007G011

..(KA's)

QUESTION: 23 (1.00)

FILL IN THE BLANKS.

Per Technical Specification 3.4.6.2, ' action must be taken by the operators if Steam Generator tube--leakage exceeds (a)

GPM primary-to-secondary leakage through all Steam Generators and (b) gallons per day through any one Steam Generator not isolated from the Reactor. Coolant System.

(1,0)

ANSWER:

23 (1.00)

(a) 1

[+0.5]

(b) 500 [+0.5]

s

(***** CATEGORY 2 CONTINVED ON NEXT PAGE'*****)

' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 19 (36%)

REFERENCE:

1 1.

VCS: Technical Specification 3.4.6.2, p. 3/4 4-19 2.

KA 000037A210 (3.7),

000037A210

..(KA's)

QUESTION: 24 (1.50)

LIST the THREE (3) valves that the AB Operator ensures are closed as an immediate action per E0P-8.0, " Control Room Evacuation".

(1.5)

ANSWER:

24 (1.50) 1.

Boric acid blender inlet isolation valve (XVD-8430-CS) 2.

Chemical mixer tank header isolation valve (XVD-8454-CS) 3.

.RMW charging pump suction isolation valve (XVD-8441-CS)

[+0.5] each for a total of [+1.5] points.

REFERENCE:

1.

VCS:

E0P-8.0, " Control Room Evacuation" p.2.

I 2.

KA 000068K318 (4.2).

000068K318

..(KA's)

QUESTION: 25 (1.50)

STATE the THREE (3) symptoms / plant conditions requiring emergency boration in accordance with E0P-11.0, " Emergency Boration".

(1.5) t 4

l

(***** CATEGORY 2 CONTINVED ON NEXT PAGE *****)

1 ENERGENCYANDABNORNALPLANTEVOLUTIONS Page 20 (36%)

. ANSWER:

25 (1.50)

1. - ' Failure of the reactor makeup control system (such that

. bypass is necessary to accomplish boration.).

2.

Uncontrolled cooldown NOT requiring SI.

3.

Any questionable shutdown margin.

[+0.5]each

REFERENCE:

1.

VCS:

E0P-II.0, " Emergency Boration," p. 1.

2.

KA 000024G010 (4.0) 000024K301 (4.1).

000024G010 000024K301

..(KA's) 4 QUESTION: 26 (2.50)

WHAT are the FOUR (4) contingency action steps the operator may take from the control board if the turbine stop valves do NOT shut according to E0P-13.0, " Response to Abnormal Nuclear Power Generation"? ASSUME conduct of each contingency action is ineffectual.

(2.5) l ANSWER:

26 (2.50) 1.

Manually trip turbine

[+0.5]

1. 6 u elt ~b r Stop EHC pump A and B [+0.5] and pull-to-lock [+0.5],,qn,,e f ati 2.

_g3. gg 3.

Runback the turbine [+0.5]

Close all main steam isolation fnd bypass valves [+0.5]

4.

hi, % A di c,ed, j bu qT m 1,b e

i I

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

i

EkERGENCY AND ABNORMAL PLANT EVOLUTIONS-Page 21 (36%).

REFERENCE:

1.

VCS:

E0P-13,0, " Response to Abnormal Nuclear Power Generation," p. 2.

2.

KA 000007A107 (4.3) 000029All3 (4.1).

000007A107 000029All3

..(KA's)

QUESTION: 27 (2.00)

STATE the FOUR (4) immediate actions that must be taken according to A0P-403.6, " Dropped Control Rod", if during Mode 1 operation ONE (1) rod has fallen into the core and its rod bottom light is lit?

(2.0)-

ANSWER:

27 (2.00) 1.

Verify reactor did not trip.

[+0.5]

2.

If reactor tripped, implement E0P-1.0, Reactor Trip /

Safety injection Actuation.

[+0.5) 3.

Decrease Turbine load to ensure Tavg within 5 deg F of Tref.

[+0.5) 4.

Rotate R0D CNTRL BANK SEL switch to MANUAL, '[+0.5]

l

REFERENCE:

1.

VCS: A0P-403.6, " Dropped Control Rod," p. 1.

2.

KA 000003G010 (3.9) 000003G0ll (3.6).

000003G010 000003G0ll

..(KA's)

(***** END OF CATEGORY 2 *****)

l

' PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 22 RESPONSIBILITIES (13%)

4 QUESTION: 01 (1.00)

WHICH ONE (1) of the following is a prerequisite for starting 1

a reactor coolant pump?

(1.0) a.

Oil lift pump has been operated for 1 (one) minute.

b.

Reactor Coolant System pressure is above 315 psig.

c.

1. 1 seal leakoff flow is above 0.2 gpm.

d.

Delta pressure across #1 seal is greater than 150 psid.

ANSWER:

01 (1.00) c.

[+1.0)

REFERENCE:

1.

VCS: AB-4, Reactor Coolant pumps, p.24.

Enabling Objective #6.

2.

KA 003000K614 (2.6).

003000K614

..(KA's)

QUESTION: 02 (1.00)

WHICH ONE (1) of the following Pressurizer water levels is the setpoint at which the CVCS letdown isolation valves (LCV-459 and LCV-460) will automatically close?

(1.0) a.

27%

b.

22%

c.

17%

d.

12%

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

-PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 23 RESPONSIBILITIES (13%)

ANSWER:

02 (1.00)-

i c.

[+1.0]

1

REFERENCE:

1.

VCS: AB-3, Chemical and Volume Control System, p.6.

Enabling Objective #5.

2.

KA 004000A302 (3.6).

004000A302

..(KA's)

QUESTION: 03 (1.00)

WHICH ONE (1) of the following will occur if VCT level channel LT-ll5 has failed HIGH7 ASSUME no operator action'is taken.

(1.0) a.

Actual VCT level decrease with potential charging pump damage.

b.

Charging pump saction will shift to RWST at 5% actual level.

t c.

Letdown will not go to recycle holdup tanks.

d.

VCT level remains unchanged.

l ANSWER:

03 (1.00) a.

[+1.0]

l.

l

REFERENCE:

l.

VCS: AB-3, Chemical and Volume Control, p.16.

Enabling Objectives 5 and 7.

2.

KA 004010A211 (3.1).

004010A211

..(KA's)

L l

l L

L

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

Pl. ANT SYSTEMS (51%) AND PLANT-WIDE GENERIC-Page 24 RESPONSIBILITIES (13%)

l QUESTION: 04 (1.00)

The' following data concerning power range nuclear instrumentation exists.

(STP-108.001," Quadrant Power Tilt Ratio", Attachment 1 is attached for use~if needed)

N41 N42 N43 N44 lower current reading 237 mA 236 mA W mA 241 mA lower reference current 474 mA 472 mA 489 mA 481 mA upper current reading 222 mA 214 mA 245 mA 257 mA upper reference current

'444 mA 426 mA 474 mA 486 mA i

WHICH ONE (1) of the following is closest to the Quadrant Power Tilt Ratio (QPTR) given the conditions shown above?

(1.0) a.

1.00 b.

1.01-c.

1.02 d.

1.03 ANSWER:

04 (1.00)

.i l -

d.

[+1.0]

REFERENCE:

1.

VCS: Station Curve Book: Fig V-3A.

2.

VCS: Surveillance Test Procedure STP-108.001.

3.

VCS: IC-8, Nuclear Instrumentation, p.1, Enabling objective #9.

4.

KA 015000A104 (3.5).

015000A104

..(KA's) l j

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

=.

PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 25 RESPONSIBILITIES (13%)

i QUESTION: 05 (1.00)

WHICH ONE (1) of the following serves as the alternate water

_(1,0) supply suction for the Emergency Feedwater pumps?

a.

Condensate Storage Tank b.

Water Treatment Building c.

Demineralized Water Tank d.

Service Water System T

ANSWER:

05 (1.00) d.

[+1.0]

REFERENCE:

1.

VCS: 18-3, Emergency Feedwater System, p. 5.

Enabling Objective

1. 3.

2.

KA 061000K401 (3.9).

(

061000K401

..(KA's)

QUESTION: 06 (1.00)

WHICH ONE (1) of the following supplies steam to drive the three (3) main feedwater' pump turbines? ASSUME normal 100 percent plant load with three feedwater pumps running.

(1.0) a.

Hot reheat steam from Moisture Separator Reheater A.

1 b.

Main steam supplementing hot-reheat steam, i

I c.

Hot reheat steam from Moisture Separator Reheater B.

d.

Main steam supplementing cold reheat steam.

l L

(***** CATEGORY 3 CONTINVED ON NEXT PAGE *****)

6 PLANT SYSTEMS (51%)'AND PLANT-WIDE GENERIC Page 26 RESPONSIBILITIES (13%).

ANSWER:

06 (1.00) a.

[+1.0)

REFERENCE:

l.

VCS: TB-7, Feedwater System, p. 9, Enabling Objectives #3 and #4.

2.

KA' 039000A403 (2.8).

039000A403

..(KA's)

QUESTION: 07 (1.00)

At WHICH ONE (1) of the following RCS pressures does the ECCS-accumulator tank contents begin injecting into the RCS?

~ (1.0).

a.

1350 psig b.

650 psig c.

350 psig d.

150 psig 1

l ANSWER:

07 (1.00) b.

[+1.0)

REFERENCE:

1.

VCS: AB-10, Emergency Core Cooling Systems, p.'37.

Enabling Objective-#5.

2.

KA 006020K603 (3.0) 006000K602 (3.4)- 006000A301 (4.0) 006020K603 006000K602 006000A301

..(KA's)

(***** CATEGORY 3 CONTINUED ON NEki PAGE *****).

PLANT SYSTEMS (51%) AND PLANT WIDE GENERIC Page 27 RESPONSIBILITIES (13%)

i QUESTION: 08 (1.00)

WHICH ONE (1) of the following conditions is the proper valve status for the Residual Heat Removal System in the normal standby ECCS mode?

. (1.0).

a.

Residual Heat Exchanger Bypass Valves (FCV-605A/B) open, b.

Recirculation Sump Isolation Valves (MVG-8811A/B) open.

c.

Cold Leg Injection Isolation Valves (MVG-8888A/B) open.

d.

Hot Leg Injection Isolation Valve (MVG-8889) open.

i ANSWER:

08 (1.00) c.

[+1.0]

REFERENCE:

1.

VCS: AB-10, Emergency Core Cooling Systems, p. 35, Enabling Objective #3 and #4.

2.

KA 006020A302 (3.9),

l 006020A302

..(KA's) l QUESTION: 09 (1.00)

WHICH ONE (1) of the fo'llowing occurs when Hot. Leg Recirculation Phase is initiated?

(1.0).

a.

Reverse flow through the core is stopped, b.

A steam bubble is formed in vessel head.

c.

Water flow through the core is reduced.

4 d.

Boron washes back into solution.

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

i PLANT SYSTEMS (51%) AND PLANToWIDE GENERIC Page-28 RESPONSIBILITIES (13%)

i ANSWER:

09 (1.00) d.

[+1.0)

REFERENCE:

1.

VCS: AB-10, Emergency Cooling System, p. 40.

Enabling Objective

1. 1 and 3.

2.

KA 006000G004 (3.5) 006030K403 (3.4).

i 006000G004 006030K403

..(KA's)

QUESTION: 10 (1.00)

WHICH ONE (1) of the following specifies the LIMIT that inserted rods shall be positioned at within their group step counter.

demand position according to Technical Specification 3.1.3,

" Moveable Control Assemb1'les"?

(1.0).

a.

+/- 12 steps b.

+/- 14 steps c.

+/- 16 steps d.

+/- 18 steps ANSWER:

10 (1.00) a.

[+1.0)

REFERENCE:

1.

VCS: Tech. Spec. 3.1.3.1

-l 2.

VCS: 10-5 Rod Control System, Enabling Objective #9.

3.

KA 014000A204 (3.4).

i 014000A204

..(KA's) l

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

i L

l PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC-Page 29 RESPONSIBILITIES (13%)

k QUESTION: 11 (1.00)

WHICH ONE (1) of the following conditions or events will result in a DECREASE in the OP-delta T setpoint?

(1.0) a.

Pressurizer spray valve sticks open for 15 seconds (assume no reactor trip).

b.

A reactor boration is initiated at 50% power.

c.

A power ascension from 75% to 100% power.

d.

Feed flow to a steam generator is. increased.

ANSWER:

11 (1.00) c.

[+1.0]

REFERENCE:

1.

VCS: IC-9, Reactor Protection and Safeguards System, p. 29.

Enabling Objective #7.

2.

KA 012000K611 (2.9).

012000K611

..(KA's) l l

(***** CATEGORY 3 CONTINVED ON NEXT PAGE *****)

~

PLANT SYSTEMS (51%) AND PLANT WIDE GENERIC Page 30 RESPONSIBILITIES (13%)'

QUESTION: 12 (1.00)

WHICH ONE (1) of the following canditions will cause the actuation of the steam dump system? ASSUME steam dumps in Tavg mode unless otherwise indicated and no operator action is taken.

(1.0) a.

Failure of impulse pressure PT-447 LOW at a fast rate with a coincident Tavg-Tref error signal of 6 deg F.

b.

Failure of BOTH impulse pressure PT-446 and PT-447 HIGH, coincident with a hot leg RTD failed HIGH.

t c.

Failure of impulse pressure PT-446 LOW with the stea'n dump controller in " Steam Pressure" and setpoint at no-load value.

d.

Failure of impulse pressure PT-446 LOW coincident with a hot leg RTD failed LOW.

ANSWER:

12 (1.00) a.

[+1.0)

REFERENCE:

1.

VCS: IC-1, Steam Dump System, Enabling Objective #6.

and figure 10.11.

2.

KA 041020K411 (2.8) 041020K414 (2.5).

041020K411 041020K414

..(KA's) l 1

i i

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

l

Pi. ANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 31 RESPONSIBIL1 TIES (13%)-

-l l

QUESTION: 13 (1.00)

WHICH ONE (1) of the following Refueling Water Storage Tank i

(RWST) conditions meets the operability requirements for the-RWST as specified in Technical Specification 3.5.4?

(1.0) a.

450,000 gallon volume, boron concentration of 2250 ppm, and a water temperature of 41 degrees F.

b.

455,000 gallon volume, boron concentration of 2450 ppm, and a water temperature of 38 degrees F.

c.

460,000 gallon volume, boron concentration of 2550 ppm, and a water temperature of 40 degrees F.

d.

465,000 gallon volume, boron concentration of 2350 ppm, and a water temperature of 42 degrees F.

t ANSWER:

13 (1.00) d.

(+1.0)

REFERENCE:

1.

VCS: AB-10. "ECCS", Enabling Objective #9, 2.

Technical Specification 3.5.4, page 3/4 5-9.

3.

KA 006020A109 (3.3) 006020A109

..(KA's) l l

l

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

~..

l PLANT-SYSTEMS (51%) AND PLANT WIDE GENERIC Page 32 l

RESPONSIBILITIES (13%):

y L

QUESTION: 14 (1.00) i 1

i WHICH ONE (1) of the following reactor building instrument air discharge header pressures is the setpoint at which the Backup Instrument Air Valve (PVA-2659) will automatically open to provide backup instrument air?

-(1.0) a.

105 psig b.

90 psig c.

75 psig d.

60 psig i

ANSWJR:

14 (1.00) b.

[+1.0)

REFERENCE:

1.

VCS: AB-14, Reactor Building Instrument Air, p. 6.

Enabling l

Objective #5.

2.

KA078000K402(3.2).

078000K402

..(KA's)

QUESTION: 15 (1.00)

WHICH ONE (1) of the following loads. is supplied by the Component Cooling Water System?

(1.0) a.

Diesel generator coolers I

b.

HVAC mechanical chillers c.

Reactor building cooling units d.

Reactor Coolant Drain Tank Heat Exchanger

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

PLANT SYSTEMS (Sl%) AND PLANT WIDE GENERIC Page 33 RESPONSIBILITIES (13%)

ANSWER:

15 (1.00) d.

[+1.0)

REFERENCE:

1.

VCS: IB-2. Component Cooling System, p.18.

Enabling Objectives

1. 1,4.

2.

VCS: IB 1, Service Water, p. 10.

Enabling Objective, #1,4.

3.

KA 00B000K102(3.3).

008000K102

..(KA's)

-QUESTION: 16 (1.00)

WHICH ONE (1) of the following arrangements during NORMAL full power operations satisfies the component cooling heat removal requirements?

(1.0) e.

One il) CCW pump operating in SLOW speed, b.

Two (2) CCW pumps operating in SLOW speed.

c.

Two (2) CCW pumps operating: One in SLOW speed and one in FAST speed, d.

Two (2) CCW pumps operating in FAST speed.

ANSWER:

16 (1.00) e.

[+1.0)

REFERENCE:

1.

VCS: IB-2 Component Cooling, p. 25.

Enabling Objective #6, 2.

KA 008000A101 (2.8) 008030A302 (2.5) 008010A303 (2.9) 008000A101 008030A302 008010A303

..(KA's)

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PLANT SYSTEMS (51%) AND PLANT. WIDE GENERIC Page 34 RESPONSIBILITIES (13%)

QUESTION: 17 (1.00)

WHICH ONE (1) of the following statements is allowable concerning i

the requirements for the Nuclear Instrumentation Recorder NR 45, in order to perform a reactor startup?

(1,0) a.

BOTH source range channels are selected, b.

The LOWEST indicating source range channel and the HIGHEST indicating intermediate range channel are selected, c.

The HIGHEST indicating source range channel and the LOWEST indicating intermediate range channel are selected.

d.

BOTH intermediate range channels are selected.

ANSWER:

17 (1.00) c.

[+1.0)

REFERENCE:

1.

VCS: 10 8, Nuclear Instrumentation System, p. 40.

Enabling l

Objective # 4,5.

~

2.

KA 015000A402 (3.9) 015000A401 (3.6).

015000A402-015000A401

..(KA's)

QUESTION: 18 (1.00)

WHICH ONE (1) of the following will cause a main feedwater pump l

trip? ASSUME the plant is operating at 50% power.

(1,0)

.i a.

Low deaerator storage tank level, b.

Low feedwater pump discharge pressure.

c.

Excessive feedwater pump vibration.

d.

Loss of a feedwater booster pump.

(***** CATEGORY 3 CONTINVE0 ON NEXT PAGE *****)

2

PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 33 RESPONSIBILITIES (13%)

5 ANSWER:

15 (1.00) d.

[+1.0)

I

REFERENCE:

1.

VCS: IB 2, Component Cooling System, p.18.

Enabling Objectives

1. 1,4.

2.

VCS: IB 1, Service Water, p. 10.

Enabling Objective, #1,4.

3.

KA 008000K102 (3.3).

l 008000K102

..(KA's)

I QUESTION: 16 (1.00) l WHICH ONE (1) of the following arrangements during NORMAL l

full power operations satisfies the component cooling heat removal requirements?

(1.0) a.

One (1) CCW pump operating in SLOW speed.

s i

b.

Two (2) CCW pumps operating in SLOW speed.

c.

Two (2) CCW pumps operating: One in SLOW speed and one in FAST speed.

d.

Two (2) CCW pumps operating in FAST speed, i

\\

ANSWER:

16 (1.00)

I a.

[+1.0)

REFERENCE:

i 1

1.

VCS: IB 2 Component Cooling, p. 25.

Enabling Objective #6.

I 2.

KA 008000A101 (2.8) 008030A302 (2.5) 008010A303 (2.9) 008000A101 008030A302 008010A303

..(KA's)

)

l l

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

PLANT SYSTEMS (51%) AND PLANToWIDE GENERIC Page 34 RESPONSIBILITIES (13%)

P QUESTION: 17 (1.00)

)

WHICH ONE (1) of the following statements is allowable concerning the requirements for the Nuclear Instrumentation Recorder NR-45, in order to perform a reactor startup?

(1.0) a.

BOTH source range channels are selected.

b.

The LOWEST indicating source range channel and the HIGHEST indicating intermediate range channel are selected.

c.

The HIGHEST indicating source range channel and the LOWEST indicating intermediate range channel are selected.

i d.

BOTH intermediate range channels are selected.

ANSWER:

17 (1.00) c.

(+1.0)

REFERENCE:

1.

VCS: IC-8, Nuclear Instrumentation System, p. 40.

Enabling Objective # 4,5.

2.

KA 015000A402 (3.9) 015000A401 (3.6).

015000A402-015000A401

..(KA.'s) i QUESTION: 18 (1.00)

WHICH ONE (1) of the following will cause a main feedwater pump i

trip? ASSUME the plant is operating at 50% power.

(1.0)

{

a.

Low deaerator storage tank level.

b.

Low feedwater pump discharge pressure, c.

Excessive feedwater pump vibration.

d.

Loss of a feedwater booster pump.

l i

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

w

l PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 35 RESPONSIBILITIES (13%)

l ANSWER:

18 (1.00) a.

[+1.0)

REFERENCE:

1.

VCS: TB-7, Feedwater System, p. 12-13.

Enabling Objective #5.

2.

KA 059000K416 (3.1).

l 059000K416

..(KA's)

QUESTION: 19 (1.00)

WHICH ONE (1) of the following radiation monitors can be used to detect primary to secondary leakage?

(1.0)

I a.

Main Plant Vent (RM-A13) b.

Particulate and Gaseous activity (RM-A2) c.

MainSteamLine(RM-Gl9A,B.C) j d.

Reactor Building Purge Supply & Exhaust System (RM-A14) i

~

ANSWER:

19 (1.00) c.

[+1.0)

-l

REFERENCE:

1.

VCS: Technical Specifications 3.3.3.1. Radiation Monitoring Instrumentation, p. 3.4-41.

2.

VCS: AB-2 Reactor Coolant System, p. 47.

Enabling Objective #9.

3.

KA 002000A301 (3.7) 073000G0ll (2.8) 073000G007 (2.9).

002000A301 073000G011 073000G007

..(KA's) i t

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

t FLANT SYSTEMS (51%) AND PLANT WIDE GENERIC Page 36 RESPONSIBILITIES (13%)

QUESTION: 20 (1.00)

WHICH ONE (1) of the following components receives its input from Pressurizer pressure transmitter PT-4457 (1.0) a.

"PZR PRESS LO" annunciator b.

Both Pressurizer Spray controllers c.

Proportional heater controller d.

P-ll interlock I

ANSWER:

20 (1.00) a.

[+1.0)

REFERENCE:

1.

VCS: 10-3, Pressurizer Pressure and Level Control, p.11-21.

Enabling Objective #2,3, and 4.

2.

KA 010000G007 (3.4) 010000K601 (2.7) 010000A302 (3.6).

010000A302 010000G007 010000K601

..(KA's) 1

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

PLANT SYSTEMS (51%) AND PLANT WIDE GENERIC Page 37 RESPONSIBILITIES (13%)

OVESTION: 21 (1.00)

WHICH ONE (1) of the following describes the plant response to a pressurizer level channel failure? ASSUME LT-459 control channel failed LOW, the system is in automatic, no operator action is taken, and the reactor is at 100% power.

(1,0) a.

Charging flow decreases, actual level decreases, letdown isolates, and the level stabilizes at setpoint.

b.

Charging flow remains the same, letdown flow temperatures increase, backup heaters turn on if actual level increases greater than 5% above program.

c.

Letdown isolates, charging flow increases, actual level increases, and the reactor trips on high pressurizer level.

d.

Letdown isolates, heaters turn off, pressurizer pressure i

decreases, and the reactor eventually trips on low pressurizer pressure.

ANSWER:

21 (1.00) c.

[+1.0)

REFERENCE:

l 1.

VCS: IC 2, Pressurizer Pressure and Level Control, p. 24 30 and Enabling Objective # 2,4, and 5.

2.

KA 011000A211 (3.4).

011000A211

..(KA's)

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

t

PLANT SYSTEMS (51%) AND PLANT WIDE GENERIC Page 38 RESPONSIBILITIES (13%)

QUESTION: 22 (1.00) l WHICH ONE (1) of the following valves is used to THROTTLE Pressurizer auxiliary spray flow?

(1.0) 4.

PVT-8145 (Auxiliary Spray Valve) b.

TCV-122 (Charging Flow Control Valve) c.

PCV-444C (Spray Valve for Loop C) d.

PCV-4440 (Spray Valve for Loop A)

[

ANSWER:

22 (1.00) i b.

(+1.0)

REFERENCE:

1.

VCS: AB 2, Reactor Coolant System, p. 29 30.

Enabling Objective

1. 4.

2.

VCS: AB 3, CVCS, p. 23-24 3.

KA 010000A202 (3.9) 010000A401 (3.7) 010000A202 010000A401

..(KA's) l i

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P'LANT SYSTEMS (51%) AND PLANT WIDE GENERIC Page 39 RESPONSIBILITIES (13%)

i l

i QUESTION: 23 (1.00)

WHICH ONE (1) of the following actions will occur if the operator

)

were to push the

• SCAN" pushbutton on the Incore Instrumentation System panel? ASSUME Incore Instrumentation System is setup for automatic operation.

(1.0) j a.

Inserts detectors (s) at LOW speed to the top of-core limit.

i b.

Inserts detector (s) at HIGH speed to the top of core limit.

c.

Inserts detector (s) at LOW speed to the bottom of-core limit.

i d.

Inserts detector (s) at HIGH speed to the bottom-of core limit.

ANSWER:

23 (1.00) a.

(+1.0)

REFERENCE:

l.

VCS: 10 7, Incore Instrumentation, p. 19.

Enabling Objective #4.

2.

KA 015000A303 (3.9) 015000A303

..(KA's) t t

t

(***** CATEGORY 3 CONTINVED ON NEXT PAGE *****)

. PLANT SYSTEMS (51%) AND PLANT-WIDE GD1ERIC Page 40 RESPONSIBILITIES (13%)

l QUESTION: 24 (1.50)

MATCH the correct seal leakage flows from Column B with the correct reactor coolant pump seal in Column A.

(Items in Column B may be used more than once). ASSUME normal full-power conditions.

(1.5)

COLUMN A COLUMN B f

a.

1. 1 Seal l.

50 cc/hr b.

1. 2 Seal 2.

100cc/hr

{

c.

1. 3 Seal 3.

3 gph 4.

3 gpm 5.

5 gpm 6.

8 gpm i

i ANSWER:

24 (1.50) a.

4

[+0.5) b.

3

[+0.5) c.

2

[+0.5) i

REFERENCE:

I 1

1.

VCS: AB 4, Reactor Coolant Pumps, Enabling Objective #2.

2.

KA 003000K602 (2.7) 003000A30)

(3.3).

003000K602 003000A301

..(KA's) l

(***** CATEGORY 3 CONTINVED ON NEXT PAGE *****)

F

i

'LANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 41 P

RESPONSIBILITIES (13%)

QUESTION: 25 (2.00)

MATCH the correct detection instrument from Column B with the correct range in Column A.

(Items in Column B may be used more than once)

(2.0)

COLUMN A COLUMN B a.

Source Range detectors 1.

BF3 proportional detector N31 and N32 2.

U 235 Fission Chamber b.

Source Range detector N33 3.

Uncompensated Ion Chamber j

c.

Intermediate Range 4.

Compensated Ion Chamber detectors N 35 and N 36 d.

Power Range detectors N41, N42, N43, N44 i

ANSWER:

25 (2.00) a.

2

[+0.5) b.

1

[+0.5) c.

2

[+0.5) d.

3

[+0.5)

REFERENCE:

1.

VCS: 10 8, Nuclear Instrumentation, p. 4-10.

Enabling Objective i

1. 3.

2.

KA 015000K601 (2.9).

015000K60)

..(KA's)

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

PLANT SYSTEMS (51%) AND PLANT-WIDF. GENERIC Page 42 RESPONSIBILITIES (13%)

QUESTION: 26 (1.00)

MATCH the setpoint values from Column B with the correct Rod Stop interlock in Column A.

(Items in Column B may be used more than once).

(1.0)

COLUMN A COLUMN B a.

C 1, Intermediate Range 1.

1%

Rod Stop, % power 2.

2%

b.

C-2, Power Range over-power Rod Stop, 3.

3%

% power c.

C-3, OT delta T Rod Stop, % from trip 5.

12%

-setpoint 6,

20%

d.

C 4, OP delta T Rod Stop, % from trip 7.

30%

setpoint 8.

103%

9.

109%

b ANSWER:

26 (1.00) a.

6

[+0.25) b.

8

[+0.25]

c.

3

[+0.25) d.

3

[+0.25)

P

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

)

t

. PLANT SYSTEMS (51%) AND PLANToWIDE GENERIC Page 43 RESPONSIBILITIES (13%)

i

REFERENCE:

1.

VCS: 10-8, Nuclear Instrumentation, p. 50.

Enabling Objective

1. 5.

2.

KA 015000K402 (3.7) 001000K407 (3.7) 015000K402 001000K407

,.(KA's)

I QUESTION: 27 (1.00)

MATCH the correct ower supply from Column B with the correct i

Emergency Core Coo ing System pump in Column A.

(Items in column B may be used more than once).

(1,0)

COLUMN A COLUMN B a.

RHR Pump A 1.

IDA b.

RHR Pump B 2.

IDAl c.

Charging Pump A 3.

IDB d.

Charging Pump B 4.

IDB1 J

5.

lA3 6.

IDA or IDB i

ANSWER:

27 (1.00) a.

2 b.

4 c.

I d.

3

[+0.25] pts each 1

t

(***** CATEGORY 3 CONTINUED 01 NEXT PAGE *****)

s PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 44 RESPONSIBILITIES (13%)

REFERENCE:

i 1

1.

VCS: AB 3, CVCS p. 20.

Enabling Objective #4.

J 2.

VCS: AB 10 ECCS, p. 28,61.

Enabling Objective #4.

3.

KA 005000K201 (3.0) 006000K201 (3.6).

j 006000K201 005000K201

..(KA's)

QUESTION: 28

.(2.50)

MATCH the RCS loop segments from Column B with the RCS penetrations in Column A.

(Items in Column B may be used more than once).

(2.5)

COLUMN A COLUMN.C a.

CVCS Normal Charging 1.

Loop A cold leg b.

Pressurizer Surge Line 2.

Loop A hot leg c.

Pressurizer Spray Line 3.

Loop A intermediate leg l

(two items) d.

Normal Letdown 5.

Loop B hot leg 6.

Loop B intermediate leg 7.

Loop C cold leg

+

8.

Loop C hot leg 9.

Loop C intermediate leg e

i t

(***** CATEGORY 3 CONTINVED ON NEXT PAGE *****)

i PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 45 RESPONSIBILITIES (13%)

I i

ANSWER:

28 (2.50) a.

4

[+0.5) b.

2

[40.5) i c.

I and 7

[+0.5) each d.

3

[+0.5) i

REFERENCE:

1.

VCS: AB-2, Reactor Coolant System, Fig AB2.3, Learning Objective

1. 3, 4, 2.

KA 002000K109 (4.1)- 002000K106 (3.7) 002000K106 002000K109

..(KA's) t QUESTION: 29 (1.00)

MATCH the correct rod speeds in Column B with the appropriate rod bank and mode of operation in Column A.

(Items in Column B may be used more than once)

(1.0)

COLUMN A COLUMN B a.

WITHDRAWING control bank *B" in 1.

O spm control bank "B" position 2.

8 spm b.

Automatic INSERTION with TAVG greater than TREF by 1 degree 3.

40 spm

]

c.

Automatic INSERTION with TAVG 4.

4B spm greater than TREF by 2 degrees 5.

68 spm d.

Automatic INSERTION with TAVG greater than TREF by 5 degrees 6.

72 spm i

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

l t

PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 46 RESPONSIBILITIES (13%)

i I

ANSWER:

29 (1.00) a.

4 [+0.25) b.

1

[+0.25) c.

2 [+0.25) d.

6 [+0.25)

REFERENCE:

i 1.

VCS: 10 5 Rod Control, p. 31.

Enabling Objective # 4 and 5.-

2.

KA 001010K404 (2.6) 001010K403 (3.4) 001000G007 (3.2) r 001010K404 001010K403 001000G007

...(KA's)

QUESTION: 30 (0.50)

FILL IN THE BLANK. The Reactor Building spray system is designed to remove fission products from the reactor building atmosphere.

The fission product of particular concern is (0,5)

I ANSWER:

30 (0.50) lodine

[+0.5)

REFERENCE:

1.

VCS: AB 8, Reactor Building Spray System, p. 12.

Enabling Objective #1.

2.

KA 026020K401 (2.8) 02600G004 (3.6).

026020K401 026000G004

..(KA's) l

(***** CATEGORY 3 CONTINVED ON NEXT PAGE *****)

PLANT SYSTEMS (51%) AND PLANT WIDE GENERIC Page 47

{

RESPONSIBILITIES (13%)

I QUESTION: 31 (0.50)

FILL IN THE BLANKS. The C 5 interlock prevents outward rod motion in the automatic mode if turbine power is less than (a).

percent. The C.11 interlock prevents outward automatic rod motion when control bank D is at (b) steps as indicated by the Rod Positiun Indication System.

(0,5) f ANSWER:

31 (0.50)

(a) 15%

[+0.25)

=

(b) 220

[+0.25]

I

REFERENCE:

1.

VCS: 10 5, Rod Control, p. 33. Enabling Objective #5.

2.

KA 001000K407 (3.7).

001000K407

..(KA's)

I QUESTION: 32 (2.00)

STATE the FOUR (4) automatic start signals for the Motor Driven Emergency Feedwater Pumps.

(2.0)

ANSWER:

32 (2.00) a.

(2/3) Low Low Steam Generator level (from any one Steam J

Generator)

[+0.5)

)

b.

All 3 Main Feedwater Pumps have tripped.

[+0.5) c.

Undervoltage on either ESF Bus (IDA,lDB)

[+0.5) d.

Safety Injection

[+0.5)

Sy;,hm a d a ?.d u q 4 Orb

, li,

e 1

Ll [ g (**{ w c 49, y,sa aag.eky

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

.i

PLANT SYSTEMS (51%) AND PLANToWIDE GENERIC Page 48 RESPONSIBILITIES (13%)

i

REFERENCE:

1.

VCS: 50P-211 Emergency Feedwater, p. 14 of 21.

2.

VCS: IB 3. Enabling Objective #5, p.1.

3.

KA 061000K402 (4.5).

061000K402

..(KA's)

QUESTION: 33 (2.00)

I STATE FOUR (4) signals that determine the main feedwater regulating valve position.

(2.0)

ANSWER:

33 (2.00) 1.

S/G 1evel j

if ~ cp-' Iu c i )

2.

power level (N 44) ("c I

y 3<

e s. n,1%s bv+i 3.

steam flow 4.

steam pressure (to compensate steam flow)

'slex,r r lev > / F(:d Flb J m t $ r n',d r)

O 1 (U%tdUU 07W'

[+0.5each,k1 maximum 2.0 points) o s

REFERENCE:

1.

'VCS: 10 2 Steam Generator Level Control, p. 19-21.

Enabling Objectives #3,4, and 5, 2.

KA 035010K401 (3.6).

035010K401

..(KA's) j

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

P(ANTSYSTEMS(51%)ANDPLANTWIDEGENERIC Page 49 RESPONSIBILITIES (13%)

OVESTION: 34 (1.50)

STATE the THREE (3) signals, other than manual, that will automatically close the main steam isolation valves.

Logic and setpoints NOT required.

(1.5)

AN'SWER:

34 (1.50) 1.

(2/3) High 2 Reactor building pressure (6.35 psig)

[+0.5) l 2.

(2/3) Low steam pressure (675 psig)

[+0.5) 3.

HighSteamFlow(Powerdependentsetpoint)

[+0.25) coincident with (2/3) low low Tavg (553 deg F)

[+0.25)

REFERENCE:

1.

VCS: TB 2, Main Steam System, p. 17.

Enabling Objective #5.

2.

KA 039000K405 (3.7).

039000K405

..(KA's) i QUESTION: 35 (1.00)

STATE TWO (2) inputs that may trip.the Waste Gas Discharge Control Valve HCV-014 during a controlled release of waste gas.

(1.0)

ANSWER:

35 (1.00)

(High Radiation on) RM A10

[+0.5] or (High Radiation on) RM A3

[+0.5) l l

l

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

4 PLANT SYSTEMS (51%) AND PLANT. WIDE GENERIC Page 50 RESPONSIBILITIES (13%)

REFERENCE:

j 1.

VCS: AB 12, Waste Gas System, p. 20.

Enabling Objective #5.

2.

KA 071000K404 (2.9).

071000K404

..(KA's)

QUESTION: 36 (1.00)

WHICH ONE (1) of the following is NOT a correct action performed i

by an operator qualified as " Danger Tagger" when clearing a tagout?

(1.0) a.

Forward white copies of the tagout paper work to the Associate Manager, Operations.

b.

Initial tag removal on the white copy of the component 109 i

c.

Realign non tagged components after removal of danger tag.

d.

Verify component restored to required operable position, i

ANSWER:

36 (1.00) c.

[+1.0)

REFERENCE:

1.

VCS:

SAP-201 " Dan er Tagging," p. 11.

2.

KA 19400lK102 (3.7.

19400lK102

..(KA's)

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

r 1

PLANTSYSTEMS(51%)ANDPLANTWIDEGENERIC Page 51 RESPONSIBILITIES (13%)

QUESTION: 37 (1.00)

WHICH ONE (1) of the following items correctly describes one requirement at VC Summer for station log entries?

(1.0) a.

Corrected entries must be explained, b.

Midnight entry shall always start a new pagc.

c.

Missed entries must have entries in remarks.

d.

Entries must be made within one (1) hour of the designated time.

ANSWER:

37 (1.00) b.

(+1.0)

REFERENCE:

1.

VCS: SAP 204, " Operating Logs and Records" p. 3 & 4, 2.

KA 194001A106 (3.4).

194001A106

..(KA's)

QUESTION: 38 (1.00)

WHICH ONE (1) of the following is NOT required to be reviewed by the oncoming operator at the controls (OATC) upon shift relief?

(1.0) a.

Tag Out Log b.

Station tog c.

Special Instruction Log i

d.

Surveillance Requirements

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

l l

\\

PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 52 RESPONSIBILITIES (13%)

)

i ANSWER:

38 (1.00) c.

[+1.0)

REFERENCE:

1.

VCS:

SAP 200, " Conduct of Operations", p.5 and attachments 11 and 111, 2.

KA 194001A106 (3.4).

i 194001A106

..(KA's)

I QUESTION: 39 (1.00)

WHICH ONE (1 Main Control) Status board as required?of the following is responsible for updating the (1.0) a.

Nuclear Reactor Operator (NROATC) b.

Control Building Operator c.

Control Room Supervisor d.

Shift Supervisor ANSWER:

39 (1.00) b.

[+1.0) t

REFERENCE:

1.

VCS: Special Instruction S1-89-05, p.2 of 5.

2.

KA 194001A106 (3.4).

194001A106

..(KA's)

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

PLANT SYSTEMS (51%) AND PLANT WIDE GENERIC Pcge 53 RESPONSIBILITIES (13%)

QUESTION: 40 (1.00)

WHICH ONE (1) of the following items is information listed on a CAUTION TAG but NOT listed on a DANGER TAG?

(1.0) a.

Tag number.

b.

Reason for tag.

i c.

Designated system.

d.

Location I

ANSWER:

40 (1.00) b.

[+1.0)

REFERENCE:

1.

VCS: SAP 202,"CautionTagging",p.4.

2.

VCS:

SAP-201, " Danger Tagging, p.7.

3.

KA 19400lK102 (3.7).

19400lK102

..(KA's)

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

PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 54 RESPONSIBILITIES (13%)

QUESTION: 41 (2.00)

MATCH the appropriate description in Column B with the HPP 153, " Administrative Exposure Limits" allowable dose in Column A.

(Items in Column B may be used more than once)

(2.0)

COLUMN A COLUMN B a.

500 mrem 1.

Maximum lifetime dose to save a

life, b.

2500 mrem 2.

Maximum quarterly dose to c.

5000 mrem extremities.

d.

12000 mrem 3.

Maximum quarterly dose to whole body.

4.

Maximum quarterly dose to skin.

5.

Maximum quarterly whole body dose to a fertile female.

6.

Maximum annual dose to whole body.

ANSWER:

41 (2.00) a.

5

[+0.5) b.

3

[+0.5) c.

6

(+0.5) d.

2

(+0.5)

REFERENCE:

1.

VCS: HPP 153, " Administrative Exposure Limits," page 3, 2.

KA 19400lK103 (2.8) 194001K103

..(KA's) 1

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

l

r s

PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Page 55 RESPONSIBILITIES (13%)

QUESTION: 42 (1.50)

FILL IN THE BLANKS. All locked valves using a chain / seal tab combination will have their chains color coded as follows:

Valves locked in the CLOSED position will have (a) color (0.5) coded chains.

Valves locked in the OPEN position will have (b) color (0,5) coded chains.

Valves locked in a THROTTLED position will have (c) color (0,5) coded chains.

ANSWER:

42 (1.50)

(a)

Green

[+0.5]

(b)

Red

[+0.5]

(c)

Yellow

[+0.5]

REFERENCE:

1.

VCS: SI 89 04. Locked Valve Control 2.

KA 19400lK101 (3.6) 19400lK102 (3.7) 19400lK101 19400lK102

..(KA's)

QUESTION: 43 (1.00)

FILL IN THE BLANKS. To maintain the required chemistry control of the secondary systems, the chemical feed system is used to inject (a) for oxygen scavenging and (b) to elevate the pH.

(1,0)

(***** CATEGORY 3 CONTINVED ON NEXT PAGE *****)

L

O FlANT SYSTEMS (51%) AND PLANT-WlDE GENERIC Page 56

)

RESPONSIBILITIES (13%)

j 1

ANSWER:

43 (1.00)

]

(a) hydrazine (+0.5) l (b) ammonia

(+0.5) l

REFERENCE:

1.

VCS: IB-4 Secondary Chemistry and Chemistry Control, p.18.

Enabling Objective #3.

3 2.

KA 194001All4 (2.5),

j 194001All4

..(KA's) i QUESTION: 44 (1.50) r LIST the THREE (3) conditions that must be met to allow a non-licensed person to manipulate controls that may affect the reactivity or power level of the reactor?

(1.5) l ANSWER:

44 (1.50) 1.

Under the direct supervision of a licensed operator (+0.5) l 2.

Part of his/her training to qualify for an operator license (+0.5)

(under10CFR55) 3.

Has been trained on the evolution he/she is about to perform (+0.5)

REFERENCE:

l 1.

VCS: SAP 200, "Coi1 duct of Operations,' Section 6.6.2, p.

l 13.

2.

KA 194001A103 (2.5),

i 194001A103

..(KA's)

'l t

(***** END OF CATEGORY 3 *****)

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

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E ENCLOSURE 3 SIMULATOR FIDELITY REPORT Facility Licensee:

South Carolina Electric and Gas Company Facility Docket No.:

50-395

=-

Operating Tests Administered'on:

December 6-7,.1989

=

During the conduct of the simulator portion of the operating tests, the following item was observed :

I ITEM DESCRIPTION E

CCW Surge.

With the "C" Component Cooling Water pump in service, a leak in-Tank the letdown heat exchanger was simulated. CCW surge tank level went to zero vice increasing as would be-expected.

This resu'.ted in a misdiagnosis of the problem by; the-Reactor Operator., Actions taken to produce the expected indications -

detracted from the realism of the_ scenario._

E E

E

_...