Text

June Exam 50-269/2003-301 Draft Ro/Sro Written Exam & Outline
	ML032471483
Person / Time
Site:	Oconee
Issue date:	08/11/2003
From:	Ernstes M; Operator Licensing and Human Performance Branch
To:	Rosalyn Jones; Duke Energy Corp
Shared Package
ML032521014	List: IR 05000269/2003301; ML032020259; ML032471475; ML032471483; ML032471531; ML032480791; ML032480796; ML032480798; ML032480800;
References
	50-269/03-301, 50-270/03-301, 50-287/03-301, ES-401, ES-401-2 50-269/03-301, 50-270/03-301, 50-287/03-301
	Download: ML032471483 (129)
	v • d • e

Draft Submittal

OCONEE JUNE 2003 EXAM

50 -2

69/2

0 0 3 -3 0 I

JUNE 16 - 27,2003

/

1.

Reactor Operator Operator Written Exam

s&&/o&.

Rg&c7O L ULd77e4 E x * -

+ Q

~

Y

L

~

E

ES-401

PWR Examination Outline

Form ES-401-2

9

2.

3.

4.

5.

6.*

7.

h.

I.

, , .

Facility:

Oconee

Date of Exam: 2003

3. Generic Knowledge and

Abilities Categories

Note: 1.

Ensure that at least two topics from every WA category are sampled within each tier

of the RO outline (Le., the Tier Totals in each WA category shall not be less than

two). Refer to Section D.l .c for additional guidance regarding SRO sampling.

The point total for each group and tier in the proposed outline must match that

specified in the table. The final point total for each group and tier may deviate by *I

from that specified in the table based on NRC revisions. The final RO exam must

total 75 points and the SRO-only exam must total 25 points.

Select topics from many systems and evolutions; avoid selecting more than two WA

topics from a given system or evolution unless they relate to plant-specific priorities.

Systems/evolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the categoryher.

The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA

Catalog, but the topics must be relevant to the applicable evolution or system. The

SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

On the following pages, enter the WA numbers, a brief description of each topic, the

topics importance ratings (IR) for the applicable license level, and the point totals for

each system and category. Enter the group and tier totals for each category in the

table above; summarize all the SRO-only knowledge and nonA2 ability categories in

the columns labeled K and A, Use duplicate pages for RO and SRO-only exams.

For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals

on Form ES-401-3.

Refer to ES-401, Attachment 2, for guidance regarding the elimination of

inamrotxiate WA statements.

,

~

000009 Small Break LOCA / 3

00001 1 Large Break LOCA / 3

000015/17 RCP Malfunctions / 4

000022 Loss of Rx Coolant Makeup

/ 2

03

I

000025 Loss of RHR System / 4

000026 Loss of Component Cooling

Water / 8

I

000027 Pressurzer Pressure

Contro System MalfJnction / 3

I

000029 ATWS / 1

I

000038 Steam Gen Tube Rupture13

ES-401

PWR Examination 1

Emergenc) nd Abnormal Plant Evolutior

2.7.8

WA Category Totals:

1 2

'

1 2 1 4 y ~ I

212

3

d

1 of 34

000040 (BW/E05; CE1EOS: W/E12)

Steam Line Ru Lie. Excessive

Heat Transfer ?4

I

000054 (CE/EO6) Loss of Main

Feedwater / 4

000055 Station Blackout / 6

000057 Loss of Vital AC Inst. BUS I

000062 Loss of Nuclear Svc Water /

000065 Loss of Instrument Air / 8

I

I z

BW/EW; W/E05 Inadequate Heat

Transfer - LOSS of Secondary Heat

Sink / 4

Form ES-401

itline

.Tier l/Group 1 (ROISRO)

I

WA Topic@)

I

IR

I

Knowledge of interrelationshi between

42142

1

1 1 0

I

vital system status and FaciIi&'s heat

removal system

Ability to determine and interpret the loss

of cool ng water as it appl es to RCP

ma functions

3 713 7

1

I

Loss of RC effects on PZR level

I 3.013.4 I 1

Knowledge of the reaspns for shift to

I 3.V3.4 I /

glteAnate flow path as it applies to Loss of

GEN 2.4.24 Knowledge of loss of Cooling

3.313.7

1

water procedures

I

Definition of saturated as it applies to PZR

3.113.4

1

malfunction.

$50 ONLY Gen 2.1.U Ability to apply I 2.914.0 I 7

Actions contained in EOPs for ATWS

$7;;Reeg TrijVtrubine trip as 1

1 1

MFWas it applies to SGTR

Selection of procedures associated with

Excessive heat transfer

KA moved from K2 because of importance

3.814.2

1

factors

SRO ONLY Existing valve position on

3.m.7

7

loss of instrument air associated with

SOB

Proper operation of EDG load sequencer

3.813.9

1

I

Manual control of components

35135

1

SR0,ONLY Coordinate Activities

3.8136

1

outside the CR

I

SRO ONLY DC Loads lost

Flow rates to components furnished by

Heat removals stems associated with

4.214.2

2

inadequate hea! transfer

Manipulation of controls associated with

inadequate heat transfer

4.213.8

Group Point Total:

18u-

NUREG-1021, Draft Revision 9

11 ES-401

PWR-Exam

Emergency and Abnormal Plant E

-

UAPE # I Name I Safety Function

K1

KZ

K3

A I

000001 Continuous Rod Withdrawal I1

000003 Dropped Control Rod I 1

000060 Accidental Gaseous Radwaste Rel. I 9

000061 ARM System Alarms 17

01

000067 Plant Fire On-site 148

04

000028 Pressurizer Level Malfunction 12

Termination of radioactive release

ARM detector limitations

Actions mntained in EOPs for

lant fires

howledge of fire in the plant

procedures

35/33

1

2.512.9

1

3.314.1

1

3.0i3s

1

\\

'

I

L

000068 (BW/AOG) Control Room Evac. I 8

000074 (WlE06&E07) had. Core Cooling 1 4

000076 High Reactor Coolant Activity I 9

BWlAOl Plant Runback I 1

ll

I"

BWIAM Turbine Trip I 4

BWIE13BE14 EOP Rules and Enclosures

I1

WA Category Point Totals:

7

'

/

2

1

A21G

3=

2.4.9 +

2.4.27 f

I

+

J- t

t

+

2.4.18

Form ES-401

oup 2 (ROISRO)

KIA Topic(s)

IR

4.314.6

1

/...

2' 1

3.4/3.6

1

PZR

SRO ONLY PZR Level

Indications

LcmvfEFmpensating vo

MAh+L?*

0 rating behavior,charaqeristics

3.Z3.5

o the facility associated with P

Runback

Adherence to a propriate

1

procedures anxoperational limits I

I

Knowledge of EOP Basis

2.713.6

1

EOP Rules:

facilify condgions

3.44.0

9

and selection of appropnate

procedure

Group Point Total:

915

u

I

L

NUREG-I 021, Draft Revision 9

2 of 34

ES-401

I

System # / Name

KI

I

-/Reactor

Coolant Pump

004 Chemical and Volume Control

005 Residual Heat Removal

006 Emergency Core Cooling

007 Pressurizer RelieWQuench Tank I 03

I

008 Component Cooling Water

010 Pressurizer Pressure Control

I

012 Reactor Protection

I

022 Containment Cooling

ca Condenser

039 Main and Reheat Steam

056 Condensate

059 Main Feedwater

061 AuxiliaryIErnergency Feedwater

062 AC Electrical Distribution

063 DC Electrical Distribution

064 Emergency Diesel Generator

076 Service Water

078 Instrument Air

04

vi4 Category Point Totals:

Form ES-401-

RCP Shutdown effect on

3.213.5

2.612.5

Sewndav Parameter

RCP Motor current

MUP power suppb

2.913.1

of abnormal condifkm

ECCS Flowpath

3.913.8

SRO ONLY- ECCS -

Abliiiyto evaluate plant

performance

wnnection to RCS

3.013.2

3.7M.4

PZR Heaters

I 3.013.4

3.313.8

Bypass Block Circuits

3.313.6 .

Containment

4.314.7

BWST Level

3.613.9

ccs malfunction

3.914.1

System Purpose

2.812.9

ADV

3.313.3

Water Hammer

2.9n.i

I

malfundion of EFW

2.512.8

4.214.2

wntmller

AFW start-up

Circuit Breakers

2.512.7

2.612.8

loss Of sws

Cooling water to

Group Point Total:

3 of 34

NUREG-1021, Draft Revision 9

ii

NUREG-1021, Draft Revision 9

4 of 34

-~

~

3-401

Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3

>ategory

KIA#

Topic

RO

SRO-Only

I

Initial

Submittal

to

ONS

1. 000003 GEN 2.4.1 001/1/2/DROP ROD/M 4.314.6lBANK 2003/OC03301/S/LSM/RFA

Unit 1 plant conditions:

Reactor power = 50%

ICs is in AUTOMATIC

Which one of the following events will require the operating crew to enter the EOP?

A. Steam Generator Tube Leak of 13 gpm.

B. Inadvertent ES Channels 1, 3 and 5 actuation.

C. "A" SG level is 43% and "B" SG level is 37%. Both are stable in the operating range

D.' Control Rods 1 and 5 in Group 3 drop into the core, actuating the in-limit for both

rods.

-

BANK Answer 161

A. Incorrect - SGTL EOP entry is 25 gpm.

B. Incorrect - Inadvertent ES action is not an EOP entry.

C. Incorrect - SG level that causes EOP entry is < 15 inches on the SU Level.

D. Correct - 2 CR drop into the core requires a manual reactor trip and entry into the

EOP.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D B A C B A A D B B

Scramble Range: A - D

Tier:

1

Group:

2

Keyword

DROP ROD

Cog level:

M 4.314.6

Source:

BANK 2003

Exam:

OC03301

Test:

S

AuthodReviewer: LSM/RFA

Wednesday, May07,2003 01:3918 PM

1

2. 00000SAA2.22 001/1/1/STEAM SPACEICIA 3.814.2IBANK 1992/01/25/0C03301ISILSMIRFA

From a 100% FP condition, which one of the following describes the expected response of

pressurizer level to a Small Break in the STEAM SPACE of the pressurizer (PZR)? (Assume

no operator actions are taken and HPI stabilizes RCS pressure slightly higher than secondary

system pressure.)

PZR level initially:

A. increases rapidly, then slowly increases until the PZR is completely filled by HPI.

B. decreases and drops off scale low during depressurization until HPI initiates, then level

returns on scale during repressurization.

c. decreases slowly, then decreases more rapidly when a reactor trip occurs, then returns on

scale during repressurization with HPI.

D.' increases, then decreases when a reactor trip occurs, then completely fills after the RCS

hot leg flashes.

1992/01/25

REFERENCE

OP-OC-TA-AT, Section E.5, pg 14, EO 1 .b.5 & SRO Objective 1 .b.5

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D A D C D A B C D D

Scramb1eRange:A - D

Tier:

1

Group:

1

Keyword

STEAM SPACE

Cog level:

CIA 3.814.2

Source:

BANK 1992101I25

Exam:

OC03301

Test:

S

AuthorIReviewer: LSMlRFA

Wednesday, May 07,2003 01:39:19 PM

2

3. 000009 GEN 2.1.31 001lIJllSBLOCAJCIA 4.213.9lBANK 200310C03301IRILSMIRFA

I

A Small Break LOCA has occurred inside containment. Which one of the following describes

the status of the SG XSUR level indication?

The indicated level will be:

A. LOWER than actual, a correction factor based on REACTOR BUILDING temperature must

be applied.

6.' HIGHER than actual, a correction factor based on REACTOR BUILDING temperature must

be applied.

C. LOWER than actual, a correction factor based on REACTOR COOLANT SYSTEM

temperature must be applied.

D. HIGHER than actual, a correction factor based on REACTOR COOLANT SYSTEM

temperature must be applied.

REFERENCE

OP-OC-EAP-E25, Revision 05, page 11; LRO 7, LSO 7

Oconee bank EAP-74 (fully modified)

(3.8/4.0)

I

16

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B C A B A B A C D C

Scramble Range: A - D

Tier:

1

Group:

1

Keyword:

SBLOCA

Cog level:

CIA 4.213.9

Source:

BANK 2003

Exam:

OC03301

Test:

R

AuthorJReviewer: LSMIRFA

Wednesday, May 07,2003 01:3919 PM

3

4. 000009EA2.15 OOI/I/l/SBLOCA/C/A

3.3/3.4/M/OC03301/S/LSM/RFA

Unit 1 plant conditions:

SB LOCA has occurred due to a Seismic event

Inspections reveal some minor damage to HPI components and piping

EOP Enclosure 5.1, ES Actuation has been performed

EOP Enclosure 5.12, ECCS Suction Swap to RBES is in progress

EOP Enclosure 5.37, Isolation of the HPI Pump Recirc has been completed

ILP-19 and ILP-20 (IA & 16 RX BLDG SUCTION) are OPEN

ILP-21 and ILP-22 (IA & 16 LPI BWST SUCTION) are CLOSED

RCS pressure is 1700 psig as read on ICCM indication

IHP-410 (IHP-26 BYPASS) was inadvertently opened and remains open

IHP-120 (RC VOLUME CONTROL) is closed

ILP-16 (18 LPI TO HPI & RBS) FAILED CLOSED

Which one of the following sets of flowrates meets acceptable HPI flow for the above

conditions? (Assume zero seal injection flow)

A. " A HPI HDR Flow

270 gpm

"B" HPI HDR Flow

165 gpm

" A Crossover Flow

200 gpm

" B Crossover Flow

0

gpm

RCS Makeup Flow

0

gPm

B. " A HPI HDR Flow

" B HPI HDR Flow

379 gpm

374 gpm

"A" Crossover Flow

0

9Pm

" 6

Crossover Flow

0

gPm

RCS Makeup Flow

30 9Pm

440 gpm

"E" HPI HDR Flow

0 gpm

"A Crossover Flow

0

gpm

"B" Crossover Flow

317 gpm

RCS Makeup Flow

30 gpm

C. " A HPI HDR Flow

D.' " A HPI HDR Flow

140 gpm

"E" HPI HDR Flow

360 gpm

" A Crossover Flow

245 gpm

"B" Crossover Flow

0

gpm

RCS Makeup Flow

0

gpm

Wednesday, May 07,2003 01:39:19 PM

4

A.

INCORRECT: total HPI flow is less than 750 gpm (635) but the flow from the "C" HPIP

is less than 170 gpm. Encl 5.12 closed the HPIP minimum recirc valves (completion of

enc1.5.37) so the pump must have at least 170 gpm flow.

8.

INCORRECT: flow is limited to less than 750 gpm total HPI flow with only one LPI/HPI

header operable when suction is from the RBES. The 30 gpm flow that shows on RCS Makeup

flow should not be indicated as HP-120 is closed (possible leak flow due to seismic damage)

C.

INCORRECT: total HPI flow is 757 gpm (plus the 30 gpm possible damage flow)

D.

CORRECT: total HPI flow is 745 gpm.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D E D B B D D D D C

Scramble Range: A - D

Tier:

1

Group:

I

Keyword:

SELOCA

Cog level:

CIA 3.313.4

Source:

M

Exam:

OC03301

Test:

S

AuthoriReviewer: LSMiRFA

Wednpay, May 07,2003 01:39:19 PM

5

5. 000009EK101 001/1/I/SBLOCA/C/A 4.2/4.7/NEW/OC03301/R/LSM/RFA

A small break LOCA has occurred. Plant conditions are as follows:

- RCPs have been tripped due to a loss of subcooling margin.

- Primary to secondary heat transfer has been lost.

- RCPs are to be bumped.

Which one of the following is the advantage of bumping an RCP in the loop with the highest

hot leg level?

A.' to improve the chances of recoupling and establish natural circulation.

B. to allow more HPI flow to enter and refill the RCS.

C. to increase RCS pressure and allow RCS level to recover.

D. to reduce of the water hammer induced in the RCS piping and establish natural circulation.

Oconee Lesson Plan OP-OC-EAP-E22, pg 20 Obj. R14 based on 1992/01/20 bank question

A. Correct Answer

B. Incorrect. This will increase pressure and decrease HPI flow

C. Incorrect. RC Pump bumps are no longer used to collapse voids due to the reactivity

concerns associated with sweeping the voids through the core.

D. While this will help establish natural circulation, water hammer is not the reason for the

bumping.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A C A B A D A C B A

Scramble Range: A - D

Tier:

I

Group:

1

Keyword:

SBLOCA

Cog level:

C/A 4.2/4.7

Source:

NEW

Exam:

OC03301

Test:

R

Author/Reviewer: LSMiRFA

Wednesday, May 07,2003 01:39:19 PM

6

6. 00001 IEKI .O1 OOI/I/l/NATURAL CIRCICIA 4.1/4.4/NEW/OC03301/RILSM/RFA

The following plant conditions exist:

RCS Leak = 200 gpm

RCPs unavailable

Reflux boiling is occurring

Which one of the following describes the method of post cooldown long term decay heat

removal provided by the EOPs ?

A.# Initiate Natural Circulation Cooldown and ensure one LPI train in High Pressure Mode and

one LPI train in ECCS alignment with suction from the RBES.

6. Initiate Natural Circulation Cooldown and ensure one LPI train in series Mode and one LPI

train in ECCS alignment with suction from the RBES.

C. Start one RCP and ensure one LPI train in High Pressure Mode and one LPI train in ECCS

alignment with suction from the RBES.

D. Start one RCP and ensure one LPI train in series Mode and one LPI train in ECCS

alignment with suction from the RBES.

Based on Bank Question 204

EAP130701

A.

Pressure Mode while leaving the other in its ECCS alignment with suction on the RBES.

B.

Incorrect. Series mode would require use of both LPI Coolers. One train remains

aligned to the RBES to provide for replacement of water lost out of the break.

C. Actions are correct except an RCP is not used

D. Series mode would require use of both LPI Coolers. One train remains aligned to the RBES

to provide for replacement of water lost out of the break. and an RCP is not used.

Correct. The LOCA Cooldown section of the EOP will align on LPI train in the High

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A C B A D C A C D B

Scramble Range: A - D

Tier:

1

Group:

I

Keyword:

NATURAL ClRC

Cog level:

CIA 4.114.4

Source:

NEW

Exam:

OC03301

Test:

R

AuthoriReviewer: LSM/RFA

Wedn$sclay, May 07,2003 01:39:19 PM

7

7. 000015/017AA2.10 OOI/I/I/RCP/C/A 3.7/3.7lNEW/OC03301/R/LSM?RFA

Unit 3 is operating at 100 YO power.

You observe the following temperatures slowly rising on the 3A RCP.

Upper oil cooler

Motor stator coolers

Lower oil pot

All other temperatures and vibration reading do not significantly change.

Assume no operator actions. Which one of the following has caused the RCP temperature to

increase, and what actions will you take?

A. Loss of Seal Injection to the 3A pump and secure the RCP.

B. Letdown has Isolated and trip the reactor.

C.'

Loss of LPSW to the 3A pump and secure the RCP.

D. Loss of CCW to the 3A pump and trip the reactor.

REACTOR COOLANT PUMP MOTOR (PNS-CPM) LESSON PLAN

PNS-CPMrl 1 a

C.

LPSW provides cooling to:

1.

Upper oil cooler

2.

Motor stator coolers

3.

Lower oil pot

MCS

Time:

I

Points:

1.00

Version: 0 I 2 3 4 5 6 7 8 9

Answer: C A C A C D A D C D

Scramble Range: A - D

Tier:

1

Group:

1

Keyword:

RCP

Cog level:

CIA 3.713.7

Source:

NEW

Exam:

OC03301

Test:

R

AuthorIReviewer: LSM?RFA

Wednesday, May 07,2003 01:39:19 PM

8

8. 000022AK1.03 001/1/1/LOSS OF RC MAKEUPiCiA 3.0/3.4/BANK 2003/0C03301/R/LSMIRFA

I

1

Unit 1 plant conditions:

Reactor power = 100%

A leak occurs on the "1A HPI Injection header

1 RIA-32 is in alarm

1B HPI pump is available

i

Which one of the following describes how the Pressurizer level will be procedurally controlled

while in this condition?

By adjusting:

A,' letdown flow and starting 1B HPlP with flow through IHP-409 (1 HP-27 Bypass).

6. letdown flow and starting 1B HPlP with flow through IHP-410 (1 HP-26 Bypass).

C. seal injection flow and starting I C HPlP with flow through 1 HP-409 (1 HP-27 Bypass).

D. seal injection flow and starting I C HPlP with flow through IHP-410 (1 HP-26 Bypass).

Answer 142

A

A.

4.146 which instructs the operator to adjust letdown and throttle 1 HP-409 to makeup to the

RCS.

B.

1A injection header.

Correct- Step 4.140 has the operator ensure 1B HPI pump is operating and go to step

Incorrect- Seal injection is not adjusted and IHP-410 is not used since the leak is on the

C.

pump is available.

D.

pump is available. IHP-410 will not be used since the leak is on the 1A injection header.

Incorrect- Seal injection is not adjusted and the 1 C pump will not be used since 1 B HPI

Incorrect- Seal injection is not adjusted and the I C pump will not be used since 18 HPI

MCS

Time:

I

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A D B E C B B C B C

Scramble Range: A - D

Tier:

I

Group:

1

Keyword:

LOSS OF RC MAKEUP

Cog level:

CIA 3.0/3.4

Source:

BANK 2003

Exam:

OC03301

Test:

R

Author/Reviewer: LSMiRFA

Wednesday, May 07,2003 01:39:19 PM

.. .

.

..

.

9

9. 000025 AK3.01 OOl/I/l/LOSS OF RHR/C/A 3.113.4/BANK 2003/OC03301/R/LSM/RFA

Unit 1 plant conditions:

INITIAL CONDITIONS:

Time = 0200

A Turbine Building Flood is in progress

The reactor was manually tripped

Main and Emergency FDW is unavailable

The SSF and Station ASW is unavailable

CURRENT CONDITIONS:

Time = 0400

HPI Forced Cooling is in progress per Rule 4 (Initiation of HPI Forced Cooling)

The TSC desires to throttle HPI for long term DHR

Which one of the following is correct?

A. Throttle HPI in both headers to 100 gpm/header.

B. Throttle HPI in both headers to maintain ALL SCMs

c.' Isolate flow in one HPI header and throttle remaining header to 200 gpm.

D. Isolate flow in one HPI header and throttle remaining header to maintain ALL SCMs > 0 F.

bank 267

0 F.

Attachment: Page 27 of 29 of TBF

A.

B.

C.

curve.

D.

curve. SCM may be lost.

MCS

Time:

I

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C C B B C D C D D D

Incorrect, one HPI header is isolated.

Correct, Isolate flow in one HPI header and throttle remaining header to 200 gpm per

Incorrect, Isolate flow in one HPI header and throttle remaining header to 200 gpm per

Scramble Range: A - D

Tier:

1

Group:

I

Keyword:

LOSS OF RHR

Cog level:

CIA 3.113.4

Source:

BANK 2003

Exam:

OC03301

Test:

R

AuthorlReviewer:

LSMIRFA

Wednesday, May 07,2003 01:39:19 PM

10

10. 000026 GEN 2.4.24 001/1/IlCCW/C/A 3.3/3.7/NEW/OC03301/RILSM/RFA

Unit 2 is operating at 11 % power, when the Standby CC pump auto starts.

Total CC flow is 575 gpm and is slowly decreasing.

1 HP-5 closes.

All RCP seal return valves remain open.

CRD Stator Temperatures are - 155F.

Which one of the following are required Immediate Manual Actions?

A. Enter APIlIAI17001020

Do NOT Trip the Reactor

STOP ALL RCPs

Initiate AP/25

B. Enter AP/25

Trip the Reactor

Stop all RCPs

Enter APll/A/1700/20

c.# Enter AP/I/A/1700/020

Do NOT Trip the Reactor

Do NOT stop all RCPs

Do NOT Initiate AP/25

D. Enter AP/l/AII 700/020

Trip the Reactor

Do NOT stop all RCPs

Do NOT Initiate AP/25

3.1 -

IAAT both ofthe following are lost:

CC to RCPs

RCP seal injection

THEN perform the following:

A. -Trip Rx.

B. -

Stop all RCPs.

C. -Initiate

AP/25 (SSF EOP).

NOTE

If CRD stator cooling is lost, stator temperatures will reach 180 ... F in 4 minutes.

3.2 -

IAAT at least two CRD stator temperatures greater than180 ... F,

THEN trip Rx.

MCS

Time:

1

Points:

1.00

Version: 0 I 2 3 4 5 6 7 8 9

Answer: C C A A A A D C C D

Scramble Range: A - D

Tier:

1

Group:

1

Keyword

ccw

Cog level:

C/A 3.313.7

Source:

NEW

Exam:

OCO3301

Test:

R

AuthodReviewer:

LSMiRFA

Wednesday, May07,2003 01:39:19 PM

. .

. . . .. ..

.

..

.

, .

. I 1

1 1. 000027 GEN 2.1.12 00111/I/TECH SPECICIA 2.9/4.0/M/OC0330llSlLSMlRFA

Unit 1 plant conditions:

A Unit shutdown was performed following a sudden pressurizer level drop.

LPI Cooler Outlet temperature = 175" F.

RCS Low Range Cooldown pressure = 250 psig.

Pressurizer level = 120 inches.

All RCP's are off.

NO outstanding prior Technical Specification CONDITIONS at this time.

Investigations indicate that the level drop may have been due to a pressurizer level instrument

malfunction. The OSM has requested that you consider the possibility of increasing

pressurizer level to 260 inches to facilitate trouble shooting the instrument.

Which one of the following is correct?

A. Pressurizer level can be increased to 260" with no additional requirements because the

PORV is operable.

B. Pressurizer level can be increased to 2 6 0 because an LTOP operator is already

established.

C.' Pressurizer level can be increased to 2 6 0 if an LTOP operator is established.

D. Technical Specifications will not allow pressurizer level > 220" at this time.

Answer 125

REFERENCE ALLOWED - 1108101 LR CD curve and LTOP logic diagram

A. Incorrect. Although the PORV is operable, adrnin controls require pressurizer level <220"

unless an LTOP operator is established.

6. Incorrect. Since the unit is in NO Tech Spec conditions, an LTOP operator is not already

established.

C. Correct. An LTOP operator is allowed to replace any of the admin controls in Train 2 of

LTOP (see TS 3.4.12 bases).

D. Incorrect See above.

MCS

Time:

I

Points:

1.00

Version: 0 I 2 3 4 5 6 7 8 9

Answer: C A C D A A D A A D

Scramble Range: A - D

Tier:

1

Group:

1

Keyword

TECH SPEC

Cog level:

CIA 2.914.0

Source:

M

Exam:

OC03301

Test:

S

AuthorIReviewer: LSMIRFA

. .

Wednesday, May 07,2003 01:39:19 PM

12

12. 000027AK1.01 001/l/I/PRESSURIZER/M 3.l/3.4/M/OC0330I/R/LSM/RFA

I

Which one of the following is correct, following a failure of the Channel " A Pressurizer

Temperature RTD to a minimum value?

I

PZR Level #I

will

, PZR Saturation Pressure will

A. increase / increase

BY decrease / decrease

C. increase / decrease

D. decrease / increase

~

Answer 409

B

A. Incorrect, failed RTD provides 0 output => low temperature indication. Loss of temp

compensation will decrease indicated level. Indicated temp decreases to the saturation

program and this will decrease the saturated pressure for

that temperature.

B. Correct, The RTD fails LOW; decreasing both operator indications.

C. Incorrect, same as A for PZR level

D. Incorrect ,same as A for Sat temperature

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B D A C C D D D B C

Scramble Range: A - D

Tier:

1

Group:

1

Keyword:

PRESSURIZER

Cog level:

M 3.113.4

Source:

M

Exam:

OC03301

Test:

R

AuthoriReviewer: LSM/RFA

Wednesday, May 07,2003 01:39:19 PM

13

13. 000028AA2.01 001/1/2/PZR/C/A 3.4/3.6/M 1992/01/20/0C03301/S/LSM/RFA

The reactor is operating normally at 100% power with Pressurizer Level Instrument # I selectc

for control.

Which one of the following describes the resulting plant conditions when a "Data Link Failure"

is indicated on ICCM Train "A"?

A.' PZR level goes to zero, HP-120 fully opens, and PZR level HighlLow statalarms actuate.

B. PZR level goes full scale, HP-120 fully closes, and PZR level High/Low statalarms are

inoperable.

c. SASS selects the alternate PZR level signal, HP-120 throttles as demanded by the good

level signal, and PZR level High/Low statalarms are inoperable.

D. SASS selects the alternate PZR level signal, HP-120 throttles as demanded by the good

level signal, and PZR level High/Low statalarms are operable.

OP-OC-PNS-PZR

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A A C C C A C D C B

Scramble Range: A - D

Tier:

I

Group:

2

Keyword

PZR

Cog level:

C/A 3.4/3.6

Source:

M 1992/01/20

Exam:

OC03301

Test:

S

AuthoriReviewer:

LSM/RFA

Wednesday, May 07,2003 01:39:20 PM

. .

14

14. 000028AK1.01 001/1/2/PZRIC/A 2.813. I/M 1992/01/20/OC03301/~LR/LSM/RFA

Plant conditions on Unit 2 are as follows:

- Reactor trip from 100% power.

- Loss of pressurizer level control has occurred.

- Pressurizer level is 398 inches slowly increasing on all indicators.

- RCS pressure is stable.

Which one of the following describes the response of RCS pressure and the reason for this

response when PZR level increases to full scale?

A,' RCS pressure remains stable because the PZR level instrument reference leg does NOT

tap off the true top of the PZR

6. RCS pressure remains stable because the PZR level instrument variable leg does NOT tap

off the true bottom of the PZR

C. RCS pressure rapidly increases because the PZR level instrument reference leg taps off

the true top of the PZR

D. RCS pressure rapidly increases because the PZR level instrument variable leg taps off the

Oconee Lesson Plan OP-OC-PNS-PZR

MCS

Time:

1

Points:

1.00

Version: 0 I 2 3 4 5 6 7 8 9

Answer: A A A D C C B B D B

true bottom of the PZR

Scramble Range: A - D

Tier:

1

Group:

2

Keyword

PZR

Cog level:

CIA 2N3.1

Source:

M 1992101120

Exam:

OC03301

Test:

R

Author/Reviewer:

LSM/RFA

Wednesday, May 07,2003 01:39:20 PM

15

15. 000029EA2.09 001/llIIATWS/ClA 4.4/4.5NEW/OC03301/S/LSM/RFA

Which one of the following describes the procedural bases for limiting OTSG

levels to less than 85% Operating Range during an ATWS event from 100% power?

A.'

Main FDW pumps would trip on high SG level, resulting in the inability of FDW to match

power production.

B. The steam lines would be filled with water resulting in MS line failure

c. The steam generator shell would be filled solid resulting in an excessive primary cooldown.

D. Excessive negative reactivity would be added, due to the increase in heat transfer, causing

a power excursion.

OP-OC-EAP-E26,

MCS Time:

I

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A D B C C A B B D B

Scramble Range: A - D

Tier:

1

Group:

1

Keyword:

ATWS

Cog level:

CIA 4.414.5

Source:

NEW

Exam:

OC03301

Test:

S

AuthorlReviewer: LSMIRFA

Wednesday, May 07,2003 01:39:20 PM

16

16. 000029EK3.12 001/1/1/ATWSlM 4.4/4.8R\\TEWIOC0330I/R/LSM/RFA

1

Which one of the following is the reason that EP/3/A/1800/01 Section 506, Unanticipated

Nuclear Power Production, directs operators to trip the main turbine if it has not already

tripped?

A. prevent the chance of an overcooling event adding additional reactivity to the core.

B.' allow heatup of the RCS enabling moderator temperature and doppler coefficients to

reduce reactor power.

C. prevent motorizing the main generator.

D. prevent the loss of pressurizer level due to AMSAC activation.

OP-OC-EAP-E26

MCS

Time:

1

Points:

1.00

Version: 0 I 2 3 4 5 6 7 8 9

Answer: B A D B C A C B A A

Scramble Range: A - D

Tier:

1

Group:

1

Keyword

ATWS

Cog level:

M 4.414.8

Source:

NEW

Exam:

OC03301

Test:

R

AuthorlReviewer:

LSMIRFA

Wednbsday. May 07,2003 01:39:20 PM

17

17. 000033AA2.1 I 001/1/2/1NTERMEDIATE RANGEIM 3.1/3.4/BANK 1990/07/06/0C03301/R/LSM/RFA

Which one of the following describes the effect of a loss of compensating voltage on the

Intermediate Range Nuclear Instrumentation indication?

Results in:

A. a higher gamma induced current from the inner chamber.

BY an indicated neutron level higher than actual.

c. a greater indicated startup rate.

D. a decrease in the amount of overlap between nuclear instruments.

Oconee: Lesson Plan, "Nuclear Instrumentation,

OP-OC-IC-NI,

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B D D C A C A A D D

Scramble Range: A - D

Tier:

1

Group:

2

Keyword

INTERMEDIATE RANGE

Cog level:

M 3.1/3.4

Source:

BANK 1990/07/06

Exam:

OC03301

Test:

R

AuthoriReviewer: LSMiRFA

Wednesday, May 07,2003 01:39:20 PM

18

18. 000038EAl .I9 OOl/l/l/SGTR/C/A 3.4/3.4~EWIOC03301/R/LSM/RFA

The following plant conditions exist:

o A tube rupture is in progress in OTSG "A".

o RCS pressure is 1700 psig.

o RCS temperature is 540 degrees F.

o OTSG " A operating range level is 89% (-280 inches XSUR).

o The operator is steaming OTSG " A and OTSG "B".

o All RCPs are tripped.

Which one of the following is the reason for increasing the steaming rate for OTSG " A ?

A.' To prevent a trip of the MFDW pumps.

B. To maintain a 100 degrees F. per hour RCS cooldown rate with BOTH OTSGs.

C. To prevent OTSG " A from filling and lifting a MSRV.

D. To maintain Tube-to-Shell delta T within 50 degrees F.

OP-OC-EAP-E24, EP/1/Al1800/01

MCS Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A D D C B C D B D D

Scramble Range: A - D

Tier:

1

Group:

1

Keyword:

SGTR

Cog level:

C/A 3.413.4

Source:

NEW

Exam:

OC03301

Test:

R

AuthodReviewer: LSM/RFA

WednWay, May 07,2003 01 :39:20 PM

19

19. 000040AA2. I 001/1/1/EXCESSIVE HEAT TRANSICIA 3.1/4.2lNEW/OC03301/WLSM/RFA

The following plant conditions exist:

o Unit 1 reactor has tripped.

o Core subcooling margin indicates ZERO (0) degrees F

o "A" OTSG pressure is 800 psig and decreasing.

o " 6

OTSG pressure is stable.

o RCS Tc is 535 degrees F. and decreasing.

o RCS pressure is decreasing.

o Pressurizer level is ZERO (0) inches.

Which one of the following procedures should be used to mitigate these abnormal RCS

indications?

EP/2/,4/18001001 Attachment:

A. G, Steam Generator Tube Rupture.

B. I, Loss of Coolant Accident

C. E, Loss of heat Transfer

D.' F, Excessive Heat Transfer

Oconee Procedure Index

(0 Core subcooling margin indicates ZERO (0) degrees F.). This bullet implies that the

instrument is failed based on other indications.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D C D D A B C C C D

Scramble Range: A - D

Tier:

I

Group:

I

Keyword:

EXCESSIVE HEAT TRANS

Cog level:

C/A 3.114.2

Source:

NEW

Exam:

OC03301

Test:

R

AuthorIReviewer: LSM/RFA

Wednesday, May 07,2003 01:39:20 PM

20

20. 000051AA2.02 001/1/2/COND VACUUMICIA 3.914.1lBANK 2003lOCO33Ol/S/LSM/RFA

Unit 1 conditions:

INITIAL CONDITIONS:

Reactor power = 20%

Unit startup in progress

All RCPs operating

CURRENT CONDITIONS:

Reactor tripped

Reactor power = 1 YO and decreasing

RCS pressure = 1850 psig and deceasin

Condenser vacuum = 19 inches and dec

1A2 RCP tripped

asing

Which one of the following is the cause of the reactor trip?

A. Low RCS pressure.

B. Power to flow imbalance.

C. Main turbine anticipatory trip.

D.' Loss of feedwater anticipatory trip.

Answer 423

D

A. Incorrect - RCS pressure > 1810 psig.

B. Incorrect - Rx power c min. flux/flow/imb trip setpoint.

C. Incorrect - Rx power c 27.75% and decreasing, turb. anticipatory trip

bypassed.

D. Correct - Operating MFDWP tripped on low vacuum.

I

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D C C B B A A A C C

Scramble Range: A - D

Tier:

1

Group:

2

Keyword:

COND VACUUM

Cog level:

CIA 3.914.1

Source:

BANK 2003

Exam:

OC03301

Test:

S

AuthorIReviewer: LSMIRFA

Wednesday. May 07, 2003 0.1:39:20 PM

21

21 . 000054AK3.03 001/1/I/FEEDWATER/M 3.8/4.1/NEW/OC03301/R/LSM/RFA

Procedure AP/O/A/1700/19, " Loss of Main Feedwater ", requires that FDW-315 and 316

controllers [EFW control valves] have their manual loader output matched with the automatic

output AND placed in MANUAL prior to resetting a Main Feedwater Pump.

Which one of the following is the reason that this action is necessary prior to resetting a main

FDWP?

A.' FDW 315/316 automatically close when a main FDWP is reset if their controllers are in

"AUTO.

6. the main FDWP is interlocked and will not restart if FDW 313316 controllers are in

"AUTO".

C. the main FDWP is interlocked and will not restart. FDW 315/316 automatically go to full

open.

D. FDW 3151316 automatically go to full open when a main FDWP is reset if their controllers

are in "AUTO".

Based on material in a question asked in 1990/07/06

a. WHY is this action necessary prior to resetting a main FDWP? [I

.O]

a. FDW 315/316 automatically close when a main FDWP is reset if their controllers are in

"AUTO"

b. WHAT undesirable consequence(s) is this requirement protecting against?

Oconee: EP/O/A/1700/14; OP-OC-SPS-SY-EF, pp. 66 and 68, L.O. 4.n.

3.5/3.7

b. Loss of feedwater injection to the SIG's.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A B D C B D A A A D

Scramble Range: A - D

Tier:

1

Group:

1

Keyword:

FEEDWATER

Cog level:

M 3.814.1

Source:

NEW

Exam:

OC03301

Test:

R

AuthodReviewer: LSMlRFA

Wedn?sday. May 07,2003 01 :39:20

PM

22

22. 000055EA2.01 001~1lliBLACKOUT/ClA 3.4/3.7~EW/OC03301lS/LSMRFA

I

1

Following a station blackout, the crew enters AP/I/A/I 700/11.

AP/1/A/l700/11 the Turbine Bypass Valves cycle on and off. Which one of the follow has

caused this to occur?

Shortly after entry in to

A. Condenser Hotwell Level cycling at the High setpoint.

B.'

Low CCW flow as a result of gravity flow only

C. Main Steam Relief Valves unable to relieve OTSG Pressure.

D. Oscillating RCS Pressure and Natural Circulation due to cycling of the PORV.

Solution - B

Low gravity flow caused by the loss of valve position and control of the CCW system which

results in a lowering of condenser vacuum, which has in turn caused the Turbine Bypass

Valves to cycle on and off.

Reference -

Following a station blackout AP/I/A/1700/11 informs the operator that the Turbine Bypass

Valves may cycle on and off at the 7 inch Hg condenser vacuum low limit. Low CCW flow as a

result of gravity flow only.

Oconee AP-11

MCS

Time:

I

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B A C D D C D B D C

Scramble Range: A - D

Tier:

1

Group:

1

Source:

NEW

Exam:

oco3301

Keyword:

BLACKOUT

Cog level:

CIA 3.413.7

Test:

S

AuthoriReviewer: LSM/RFA

Wednesday, May 07,2003 01:39:20 PM

23

23. 000056A2.47 001/1/1/LOSP/M 3.8/3.9/BANK 2003/OC03301/R/LSM/RFA

I

Unit 1 plant conditions:

A LOCA has decreased RCS pressure to 1500 psig.

A loss of power has caused both Keowee Units to emergency start.

MFBs have been re-energized through CT-4.

Which one of the following sets of actions is required to reset the load shed signals?

The operator must:

A. reset "ES Channels 1 & 2" and secure both Keowee Units.

B. energize the startup source and push the load shed reset pushbuttons.

C.'

depress "Manual" on the Load Shed ES modules and simultaneously depress the reset

push buttons for the MFB monitor panels load shed circuit.

D. restore an offsite power source to the 230 KV "Yellow Bus" and reset both the Keowee

Emergency Start signals in Unit 1 and 2 control room.

I

bank 327

A. Incorrect, securing Keowee units not required

B. Incorrect, no loadshed reset buttons. There are Keowee reset buttons

C. Correct, depress "Manual" on the Load Shed ES modules and simultaneously depress reset

push buttons for MFB monitor panels load shed circuit.

D. Incorrect, will not reset loadshed

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C B A A B A D B D D

Scramble Range: A - D

Tier:

1

Group:

1

Keyword

LOSP

Cog level:

M 3N3.9

Source:

BANK 2003

Exam:

OC03301

Test:

R

AuthodReviewer: LSM/RFA

Wednesday, May 07,2003 01:39:20 PM

24

24. 000057 GEN 2.1.8 001/1/1IINSTRUMENTICiA 3.714.4n\\lEWiOC0330IISILSMIRFA

Vital inverter 3DIA tripped. The repairs are complete and it is ready to be returned to service.

Currently, regulated AC power from Panelboard 3KRA is supplying the load.

DC power to the inverter has been isolated.

RPS Channel testing is also due during your shift.

You have been instructed to restart the Vital Bus Inverters.

You have just directed the closure of breaker #33 on the 3DIA DC Panelboard.

The RO pressed the PRECHARGE SWITCH pushbutton.

The PRECHARGE Light illuminates.

Which one of the following actions should be directed next?

Close the:

A. AC INPUT circuit breaker and verify that the input filter capacitors discharge.

6. DC INPUT circuit breaker and verify that the input filter capacitors discharge

c. AC INPUT circuit breaker and verify that the INVERTER OUTPUT volt meter increases to

120 Volts.

D.'

DC INPUT circuit breaker and verify that the INVERTER OUTPUT volt meter increases to

120 Volts.

op/3/a/l107/004

2.2 Press the PRECHARGE SWITCH pushbutton until the PRECHARGE Light comes on.

2.3 Close the DC INPUT circuit breaker and verify INVERTER OUTPUT volt meter increases to

120 Volts.

2.4 Close the INVERTER OUTPUT circuit breaker.

2.5 Verify the IN SYNC light is on.

2.6 Position the MANUAL BYPASS SWITCH to the "NORMAL SOURCE" position.

2.7 Verify the following indications:

. INVERTER OUTPUT volt meter )) 120 Volts.

. Inverter Output frequency meter )) 60 Hz.

. INVERTER OUTPUT amp meter increases and stabilizes to match SYSTEM

OUTPUT amp meter.

MCS

Time:

I

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D R D D C B B D D B

Scramble Range: A - D

Tier:

I

Group:

1

Source:

NEW

Exam:

oco3301

Keyword

INSTRUMENT

Cog level:

CIA 3.714.4

Test:

S

AuthorIReviewer: LSMIRFA

Wednesday, May 07,2003 01 :39:20 PM

25

25. 000057AA106 001/1/11LOSS OF AC POWEWM 3.513.5lBANK 1991107/24/0C033OI/R/LSM/RFA

Which one of the following actions are to be performed from the Auxiliary Shutdown Panel

upon a loss of 1KI bus per AP/I/A/1700/23, "Loss of IKI Bus"?

A. Bypass Turbine Stop Valve controls.

B. Control RCS volume with HP-120 (RC Volume Control).

C.'

Control RCS pressure with Pressurizer Heater Bank Two.

D. Bypass 1KI Inverter.

AP/1/A/1700/23

MCS

Time:

1

Points:

1.00

Version: 0 I 2 3 4 5 6 7 8 9

Answer: C C A B A C A D A D

Scramble Range: A - D

Tier:

1

Group:

I

Keyword:

LOSS OF AC POWER

Cog level:

M 3.513.5

Source:

BANK 1991107124

Exam:

OC03301

Test:

R

AuthodReviewer: LSMIRFA

WedWsday, May 07,2003 01:39:21 PM

. .

26

26. 000058AA2.03 001/1/11DC POWERICIA 3.5l3.9lMIOCO33O1/SlLSMlRFA

Plant conditions:

1015 on 04/30/01 the "125 VDC Ground Trouble" stat alarm was received.

1215 on 04/30/01 bus to ground voltage measurements were taken.

1415 on 04/30/01 The Units' DC systems were separated using OP/O/A/1107/08,

1730 on 04/30/01 the ground has been determined to exist on Unit 2

Ground magnitude = 2.8V (-525 Ohms).

Isolation of DC Systems Between Units after gaining OSM concurrence.

Which one of the following is correct?

A. The ground detector is inoperable on Unit 1,2, & 3.

6. Both Unit 2 and Unit 3 DC systems are functional, but not operable.

c:' Unit 2 is required to initiate efforts to locate the ground by 1015 on 05/02/01

D. Unit 3 is required to measure ground and bus voltage by 0215 on 05/01/01

A.

taken prior to the separation of the buses. A ground locating effort located the ground on Unit 2

so the ground detector is operable because a hard ground existed.

B.

C.

to locate the ground be initiated 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from the receipt of the continuous ground alarm.

D.

Incorrect. Unit 3 is required to measure ground and bus voltage by 0300 on 05/01/01. This is

the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowed by condition B with the continuous ground alarm present.

Incorrect- The ground detector is operable on unit 1. Buses to ground voltages were

Incorrect- the TS definition of functional does not apply in this case.

Correct- With the magnitude of the ground at 2.8 volts, condition D requires that efforts

MCS Time:

I

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C C D C C A A C A B

Scramble Range: A - D

Tier:

1

Group:

1

Keyword

DC POWER

Cog level:

CIA 3.513.9

Source:

M

Exam:

OC03301

Test:

S

AuthoriReviewer: LSM/RFA

Weddesday, May 07,2003 01:39:21 PM

27

27. 000059AK3.01 001i112iRAD RELEASEIM 2.712.8MEWiOCO33011RLSM1RFA

Both a GWR and an LWR are in progress. IRIA-35 has just alarmed.

Which one of the following are your rewired actions?

A. Terminate both the GWR and LWR.

B. Terminate the GWR only.

C.' Terminate the LWR only.

D. Continue both releases until a confirmatory sample indicates the alarm is valid.

Per AP/l/A/1700/018 Section 4C

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C DB D C A A C B C

Scramble Range: A - D

Tier:

I

Group:

2

M 2.712.8

Keyword:

RAD RELEASE

Cog level:

Source:

NEW

Exam:

OC03301

Test:

R

AuthoriReviewer: LSM/RFA

Wednesday, May 07,2003 01:39:21 PM

28

Which one of the following Radiation Monitors is potentially unreliable under accident

conditions?

A. RIA- 4, Reactor Building Hatch Area Radiation Monitor.

B. RIA-56, High Range Stack Radiation Monitor.

C. RIA-57, High Range Containment Radiation Monitor.

D. RIA-58, High Range Containment Radiation Monitor.

-

Wedn$sday. May07,2003 01:39:21 PM

29

29. 000062AA1.07 001/1/l/SERV1CE WATEWCIA 2.9/3.O/NEW/OC03301/WLSM/RFA

During a walkdown of the fire headers you are informed that the 2HPSW-14 (Fire Hdr. 'E'

Turbine Room Tie) has been found in the failed open position.

Which one of the following is the consequence, if any, of this failure?

A. All "M" header systems inoperable.

B:' All " M header systems are operable.

C. The fire header is capable of supplying Unit 3 fire loads only.

D. EWST level indication cannot accurately be determined.

Wednesday, May 07,2003 01:39:21 PM

30

Duke Power Company Procedure No.

Oconee Nuclear Station OP/ O M 1 104/011

Revision No.

059

High Pressure Service Water

1. Purpose

To describe proper method for operating HPSW System for Unit 1, 2, and Unit 3.

2. Limits And Precautions

2.1 2HPSW-14 (Fire Hdr. 'E' Turbine Room Tie) should remain open.

- Closing this valve will make all "M" header systems inoperable.

Line Hdr. at Unit #3) cannot supply all "M" header loads.

Contact System Engineer to determine which " M headers are operable.

2.2 3HPSW-14 (Fire Hdr. 'E' Turbine Room Tie) should remain open.

as 2HPSW-14 and 3HPSW-453 are open.

2.3 With both 2HPSW-14 (Fire Hdr. 'B' Turbine Room Tie) and 3HPSW-14 (Fire Hdr. 'E'

Turbine Room Tie) closed, all isolated sprinklers and hose stations will be inoperable.

{6: Plant Sign}

3HPSW-453 is capable of supplying Unit 3 loads only, if 3HPSW-14 (Fire Hdr. 'B

Turbine Room Tie) is closed.

Contact System Engineer to determine header operability if any question arises.

2.4 Control Room EWST level indication is not accurate at very low levels.

At zero feet indicated level, there is still approximately 13' left in tank.

work, maintenance should be informed to pump remaining water from EWST as per

MP/O/B/1800/121 (ELEVATED WATER STORAGE TANK CIVIL

INSPECTION).{4}

2.5 HPSW Pumps A & B have a minimum flow requirement of 1450 gpm.

2.6 Normal system leakage is approximately 200 gpm.

2.7 If altitude valve closes while an HPSW pump is still running, pump will be deadheaded.

OP/O/A/I 104/011

Page 3 of 6

2.8 During normal operation, deadheading is prevented by automatic controls that stop

HPSW pumps upon full level in EWST (approximately 90,000 gallons), before altitude

valve closes. {3} {7: Plant sign}

2.9 Do not operate an HPSW pump with altitude valve isolated, unless provisions have been

made to ensure pump will not be operated below its minimum flow. {3}

2.10 The BASE HPSW Pump starts at 70,000 Gal. EWST Level, the STBY HPSW Pump

starts at 60,000 Gal. EWST Level, at 90,000 Gal. A & B HPSW Pumps will STOP.

(7: Plant sign}

2.1 1 Whenever an HPSW pump starts, operators should ensure that it automatically stops

when EWST is full (approximately 90,000 gallons). {3} {7: Plant sign}

2.12 SLC 16.9.7 Bases assumes the " A HPSW Pump is in STDBY and the "B" HPSW Pump

is in BASE. If required to place the HPSW pumps in any other configuration refer to

appropriate enclosure. {5}

2.13 HPSW Pump(s) can operate with the Altitude Valve closed and no additional system

flow for = 15 minutes.

NOTE: Starting duty recommendations are to extend the life of the motor however, they may be

exceeded during an emergency.

Due to piping size and length, 3HPSW-453 (ABE F1 Fire Prot. Hdr. Sup. from 'M'

With 3HPSW-14 closed, all other "M" line header loads are operable, as long

If EWST is isolated for repair or inspection inside tank, prior to releasing red tags for

Wednbsday. May 07,2003

@1:39:21 PM

31

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B A C A C A B C C C

Scramble Range: A - D

Tier:

I

Group:

1

Keyword:

SERVICE WATER

Cog level:

CIA 2.913.0

Source:

NEW

Exam:

OC03301

Test:

R

AuthorlReviewer: LSMIRFA

Wednesday, May 07,2003 01:39:21 PM

32

30. 000067 GEN 2.4.27 001/1/2/FIRE/M 3.0/3.5/NEW/OC03301/S/LSM/RFA

I

A fire near the control room door has rendered the control room unsafe. The decision has

been made to enter AP/l/A11700/08, Loss of Control Room. Which one of the following

actions are taken before transitioning out of AP/l/A/I 700/08?

1

i

A," Dispatch an operator to locally close 1-FDW-315.

B. Dispatch an operator to locally open 1-HP-24.

C. V e r i f y m Keowee Units emergency started.

D. Verify at least one Keowee Unit emergency started.

AP/l/A!I 700/008

A. Correct

B. & C . Actions taken only if the control room is abandoned for reasons other than fire.

D. This is not an action taken in AP/'l/A/1700/008

MCS

Time:

1

Points:

1.00

Version: 0 I 2 3 4 5 6 7 8 9

Answer: A A A % C % A C D C

Scramble Range: A - D

Tier:

1

Group:

2

Keyword:

FIRE

Cog level:

M 3.013.5

Source:

NEW

Exam:

OC03301

Test:

S

AuthodReviewer: LSMiRFA

Wednesday, May 07,2003 01:39:21 PM

33

31 . 000067AK3.04 001/112/PLANT FIREIM 3.314. IIBANK 2003lOC03301/R/LSM/RFA

The following conditions exist:

A fire occurred that destroyed equipment, normal power supplies, controls, and cabling.

Pumps required for plant shutdown cannot be operated from their normal power supply.

Which one of the following is correct?

I&E will align power to required Appendix R pumps from:

A. CT-5 through the Appendix R Switchgear.

B. CT-5 through motor starters on the back of the Appendix R Portable Valve Control Panel.

C. CT-4 through the Appendix R Switchgear.

D. CT-4 through motor starters on the back of the Appendix R Portable Valve Control Panel.

I

Bank 238

A Incorrect. Power to Appendix R Pumps and controls is supplied via CT-4 (Keowee

underground feeder) through the Appendix R Switchgear.

B Incorrect. Power to Appendix R Pumps and controls is supplied via CT-4 (Keowee

underground feeder) through the Appendix R Switchgear.

C Correct. Power to Appendix R Pumps and controls is supplied via CT-4 (Keowee

underground feeder) through the Appendix R Switchgear.

D Incorrect. Power to Appendix R Pumps and controls is supplied via CT-4 (Keowee

underground feeder) through the Appendix R Switchgear. Power is not through motor starters

on the back of the Appendix R Portable Valve Control Panel.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C D B D C C A A B A

Scramble Range: A - D

Tier:

1

Group:

2

Keyword:

PLANT FIRE

Cog level:

M 3.314.1

Source:

BANK 2003

Exam:

OC03301

Test:

R

AuthoriReviewer: LSMIRFA

1

J

Wednesday, May07,2003

01:39:21 PM

34

32. 001A2.13 00112/2/CRD/C/A 4.4/4.6fl\\lEW/OC0330l/S/LSM/RFA

The following conditions exist for unit 1:

AMSAClDSS Ch 1 AND Ch 2 enabled.

"Sy Max" Programmable Controllers 'Run' lights On and 'Halt' lights Off for Ch 1 8. Ch 2.

Which one of the following is correct per SLC 16.7.2?

A. At 2450 psig, the inability of control rods to respond to a DSS signal constitutes

B.' At 2450 psig, the inability of control rods to respond to a DSS signal does NOT constitute

inoperability of the DSS system.

C. At 1900 psig, the inability of control rods to respond to a DSS signal constitutes

inoperability of the DSS system.

D. At 1900 psig, the inability of control rods to respond to a DSS signal does NOT constitute

inoperability of the DSS system.

Wednesday, May 07,2003 01:39:21 PM

, .

.

. . .

. ..

,

.

35

C.

rods in Groups 5,6&7 and any rods that are on the Aux. Power Supply AND raises the Turbine

Bypass Valve setpoint WHEN RCS pressure reaches 2450 psig.

Diverse Scram System - The system is designed to automatically drop the control

1.

critical (Mode 1 and Mode 2, when Keff 1 .O)

a)

the NRC within the next 30 days.

b)

Surveillance

1)

2)

every refueling outage. (18 months)

2.

PT/600/1 Periodic Instrument Surveillance

a)

Guidance for Normal Status

1)

2)

3)

4)

5)

b)

1)

2)

3)

4)

inoperability of DSS system. This is governed by SLC 16.7.2, Anticipated Transients Without

Scram.

5)

AMSAC/DSS channels.

(Obj. R21,22,23) Selected Licensee Commitment 16.7.2 - applies when the reactor is

If one or both channels is inoperable, restore to service within 7 days or file a report to

Perform channel Logic Test at least once every 184 days.

Perform complete DSS Actuation Test from input sensors through output relays at least

DSS not actuated (statalarms & computer alarms)

AMSAClDSS Ch 1&2 not bypassed (comp. alarms and lights on UBI)

AMSAC/DSS Enabled (light on UBI)

AMSAC/DSS UPS Ch 1&2 Normal (Uninterruptible Power Supply) Computer points

"Sy Max" Programmable Controllers Ch 1&2 'Run' lights On AND 'Halt' lights Off.

(Obj. R20) Guidance for determining operability.

Surveillance requirements met (SLC 16.7.2).

AMSACDSS Ch 1 AND Ch 2 enabled.

All AMSAC/DSS circuitry functional and properly calibrated.

"Sy Max" Programmable Controllers 'Run' lights On and 'Halt' lights Off for Ch 1 & Ch 2

NOTE: Inability of control rods to respond to a DSS signal doesn't constitute

If any channel is inoperable or generates an invalid trip signal, bypass BOTH

If the reactor is critical, declare system inoperable and take appropriate actions.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B B B A B A C C A D

Scramble Range: A ~ D

Tier:

2

Group:

2

Keyword:

CRD

Cog level:

CIA 4.414.6

Source:

NEW

Exam:

OC03301

Test:

S

AuthorlReviewer: LSMIRFA

Wednesday, May 07,2003 01:3921 PM

36

33. 003 K5.04 001/2/1/RCP/M 3.1/3.5R\\[EW/OC03301/RiLSM/RFA

Unit 2 is implementing OP/l/A/11102/10. During 2/0 RCP operation, an RCP is stopped and

then later returned to service. Which one of the following is the reason for this action?

A.' To allow a more rapid cooldown to place DHR in service sooner.

6. To allow an electrical train to be taken out of service.

C. To minimize the possibility of inadvertent power increases.

D. To allow the RHR trains to be cross connected.

PIP 0-2-1374

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A D D B B C D B C C

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

RCP

Cog level:

M 3.113.5

Source:

NEW

Exam:

OC03301

Test:

R

AuthodReviewer: LSMiRFA

Wednesday, May 07,2003 0.1:39:21 PM

.. . .

. .. . .

. ..

..

.

37

34. 003A3.02 001/2/l/RCP MOTOWM 2.6/2.5fl\\lEWIOC0330l&ULSM/RFA

The transducers that are fe$d (from the voltage and current) from the three phases of the RC

Pump Switchgear read as follows:

RCP 1Al - 18 mv

RCP 1A2 - 15 mv

RCPIBI -16mv

RCP 1B2 - 16 mv

Which one of the following describe the required manual action or the expected automatic

actions?

A. 1Al should be tripped manually.

B. 1Al should trip automatically.

C. 1B1 and 182 should trip automatically.

D.' There are no required manual or automatic actions.

pns-cpmrl l a

Voltage and current from the three phases of the RC Pump Switchgear feed a transducer. At

100% power, the output from this transducer results in an 18 millivolt signal. If this signal drops

to 25% below the 18 millivolts, a signal is sent to Reactor Protective System that the RC Pump

is tripped (there is one RC Pump Power Monitor for each of the 4 RCPs).

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D B B B C D D B B D

Scramble Range: A - D

Tier:

2

Group:

1

Keyword

RCP MOTOR

Cog level:

M 2.6/2.5

Source:

NEW

Exam:

OC03301

Test:

R

AuthodReviewer: LSMiRFA

Wednesday, May 07,2003 01:39:21 PM

38

35. 004 GEN 2.4.1 1 00112/1lMAKEUP/C/A 2.5/4.0/MIOC03301/SlLSMmFA

You are the Senior Reactor Operator on Unit 1

Plant conditions:

The SSF has been activated.

The Reactor Coolant Makeup (RCMU) pump OVERRIDE switch has been positioned

to OVERRIDE.

The RCMU pump Suction valve (SF-82) fails closed.

You have dispatched an RO, in accordance with

supply Unit 1 RCP seal flow with the RCMU pump.

RCMU pump response to an attempted start?

, to the SSF to start the D/G and

Which one of the following describes the

The RCMU Pump:

A. will start and continue to run.

6. will start but will trip on lube oil pressure.

C. will start but will trip on low discharge flowrate.

D. interlock will prevent the pump from starting.

NEED PROCEDURE NUMBER FROM FACILITY

A. Correct The RCMU Pump will start regardless of Suction Valve position.

B. Incorrect. The Low Lube Oil Press trip is bypassed when Override is used.

C. Incorrect. The Low Discharge Flowrate trip is bypassed when Override is used.

D. Incorrect. The RCMU Pump will start regardless of Suction Valve position.

(Ref: NRC #081). The only interlock associated with the Override Switch is HP-398

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A C A D A B B C D B

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

MAKEUP

Cog level:

CIA 2.514.0

Source:

M

Exam:

OC03301

Test:

S

AuthodReviewer: LSMIRFA

Wednesday, May 07,2003 01 :39:21 PM

39

36. 004K2.02 001121l1MUP1M 2.913.I/NEW/OC03301/R/LSM/RFA

The AUTOlMANUAL Transfer switch associated with ACBs 5 & 716 & 8 is in AUTO.

Which one of the following would provide power to the makeup pump busses if the

Underground breaker is closed?

A.' CX transformer.

B. either the 1X or 2X 600V transformer.

C. the 1X 600V transformer only.

D. the 2X 600V Transformer only.

solution - a

this is the normal alignment

B.

Emergency Power

1.

the auxiliary switchgears are in a normal power alignment. The Normal Power alignment being

determined by the position of the Underground breaker. If the underground breaker is

CLOSED, then the Normal power is from CX transformer. If the underground breaker is OPEN,

then the Normal power is from the units respective 600V transformer (either 1X or 2X). During

a loss of power to a unit's 600V switchgear, a 6 second timer starts. If power is restored to the

Normal source within this 6 seconds, the timer resets and no breaker action occurs. When the

6 second timer times out, the Normal power supply breaker OPENS and a 30 second timer

starts. If power comes back to the Normal source during this 30 seconds, then the normal

breaker will CLOSE back in. If the 30 second timer times out, and there is power available on

the Alternate source, then the alternate breaker will close in. This breaker stays closed until

manually opened, unless this Alternate source loses power and the Normal source has

regained power. If this occurs, the alternate breaker opens after a six (6) second timer times

out. If this occurs and there is power available on the Normal source, then the normal breaker

closes in immediately. If all of these actions have occurred and the unit is back on its Normal

power source, then the timers are all reset and the transfer scheme is ready to begin again.

2.

With the transfer switch in MAN, no automatic transfers will occur. If power is lost to

either units 600V Auxiliary LC, manual action must be taken by the operator to restore power

per AP/O/A/2000/002, Keowee Hydro Station - Emergency Start.

If power is not restored to the 600V switchgears 1X &/or 2X, then two independent sets of

batteries will supply control power to operate the units. Operation in this mode is limited to " 1

hour.

With the AUTO/MANUAL Transfer switch associated with ACBs 5 &7/6 & 8 in AUTO,

MCS

Time:

1

Paints:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A 3 D C D C 3 A D C

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

MUP

Cog level:

M 2.913.1

Source:

NEW

Exam:

OC03301

Test:

R

AuthorIReviewer: LSMIRFA

Wednesday, May 07,2003 01:39:22 PM

40

37. 005K3.07 001/2/l/DHR/C/A

3.2/3.6/NEW/OC03301/FULSM/RFA

The following conditions exist on Unit 3:

The Reactor Vessel Head is removed.

The Fuel Transfer Canal is flooded.

There is a thunderstorm in the area when you receive the following alarms:

"LP DECAY HEAT LOOP A FLOW L O W statalarm (ISA-031A-8)

"LP DECAY HEAT LOOP B FLOW L O W statalarm (ISA-03/A-S)

"LP INJECTION PUMP A DlFF PRESS LOW" statalarm (ISA-Ol/C-12)

"LP INJECTION PUMP B DlFF PRESS LOW" statalarm (ISA-OIID-12)

"LP INJECTION PUMP C DlFF PRESS LOW" statalarm (ISA-Ol/E-12)

"LPI HDR 1A INJECTION FLOW" LO alarm (01A1310)

"LPI HDR 1B INJECTION FLOW" LO alarm (01A1311)

"LPSW HEADER N B PRESS L O W statalarm (ISA-OS/A-9)

"LPI COOLER 1A LPSW FLOW" LO alarm (OlA2124)

"LPI COOLER 1B LPSW FLOW" LO alarm (OlA2125).

Which one of the following describes what has happened?

A. Only one LPI pump has tripped.

6.

All LPI Pumps have tripped only.

C. all LPSW pumps have tripped only.

D.' There are no LPI or LPSW pumps currently running.

Wednesday, May 07,2003 01:39:22 PM

41

solution: C both an LPI and LPSW pump have tripped

1. Purpose

This case provides the necessary actions to mitigate a loss of decay heat removal with the

Reactor Vessel Head removed and the Fuel Transfer Canal (FTC) flooded. This case also

provides actions to take in the event of loss of water level in the FTC.

2. Symptoms

2.1 LPI pump(s) tripped:

9 "LP DECAY HEAT LOOP A FLOW LOW" statalarm (ISA-03lA-8)

P "LP DECAY HEAT LOOP B FLOW LOW" statalarm (ISA-03lA-9)

Q "LP INJECTION PUMP A DlFF PRESS LOW" statalarm (ISA-OI/C-12)

9 "LP INJECTION PUMP B DlFF PRESS LOW" statalarm (ISA-OIID-12)

Q "LP INJECTION PUMP C DlFF PRESS LOW" statalarm (ISA-OIIE-12)

Q "LPI HDR 1A INJECTION FLOW" LO alarm (01A1310)

9 "LPI HDR 1B INJECTION FLOW" LO alarm (01A1311).

2.2 Loss of LPSW flow to cooler(s):

9

"LPSW HEADER AI6 PRESS LOW" statalarm (1SA-O9/A-9)

9 "LPI COOLER 1A LPSW FLOW LO alarm (OlA2124)

P "LPI COOLER 1B LPSW FLOW" LO alarm (OlA2125).

2.3 LPI temperature increasing:

9 "LP INJECTION PUMP SUCTION TEMP HIGH HEADER E W statalarm (lSA-03/B-8)

9 "LP INJECTION PUMP SUCTION TEMP HIGH HEADER E B E " statalarm (1SA-03/B-9)

P "LP DECAY HEAT EXCH TEMP HIGH statalarm (ISA-03/59)

Q "LPI COLD SHUTDOWN TEMP HIGH" statalarm (ISA-051E-IO)

Q "LPI DHR I RBES A SUCTION HDR TEMP" HI alarm (OlA1322)

9

"LPI RBES B SUCTION HDR TEMP HI alarm (OlA1323).

2.4 Loss of RCSlFTC inventory:

P "RB REACTOR BLDG. NORM SUMP LEVEL HIGH/LOW" statalarm (ISA-OS/A-6)

Q "SF SFP LEVEL HIGH/LOW" statalarm (1SA-09/A-5)

Q "SF POOL LEVEL" LO alarm (01 D1064)

Q Decreasing level in the Spent Fuel Pool

P Decreasing Level in the Fuel Transfer Canal

9 Decreasing Level in the Pressurizer

9 Increasing Level in RBNS

Q Water spilling in the Auxiliary Building

Q IRIA-3 (Fuel Transfer Canal Wall) alarm

P IRIA-6 (Spent Fuel Pool) alarm.

MCS

Time:

I

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D C A D B A B A B C

Scramble Range: A - D

Wednesday, May 07,2003 01:39:22 PM

42

Tier:

2

Keyword:

DHR

Source:

NEW

Test:

R

Group:

1

Cog level:

CIA 3.213.6

Exam:

OC03301

AuthorlReviewer: LSMIWA

43

38. 006 GEN 2.1.7 00112111ECCSlClA 3.714.4lM 2003/OC03301/S/LSMlRFA

Unit 1 plant conditions:

SB LOCA has occurred

EOP Enclosure 5.12, ECCS Suction Swap to RBES is in progress

ILP-19 & ILP-20 (IA &1B RX BLDG SUCTION) are OPEN

ILP-21 & ILP-22 (IA & 1B LPI BWST SUCTION) are OPEN

BWST level has STOPPED decreasing with continued HPI injection flow

Which one of the following is correct concerning the current BWST level trend?

A. The constant BWST level trend is not expected and LPI pump(s)must be secured to

prevent overheating.

B. The constant BWST level trend is not expected and LPI pump(s)must be secured to

prevent hydrogen gas binding.

Cy The constant BWST level trend is expected and LPI pump(s) suction flow is currently from

RBES only.

D. The constant BWST level trend is expected and LPI pump(s) suction flow is still from the

BWST but is below the flow instrument tap.

A.

Incorrect: suction is from the RBES, LPI pump operation may continue.

B.

Incorrect: 30 minutes is allowed while pumping against a shutoff head. This is not the

case (LPIIHPI piggyback is aligned). Suction is the concern and RBES is providing suction at

this time.

C.

Correct: with both RBES and BWST suction valves open and BWST level not

decreasing, then suction is from the RBES only. RB(P) could also be high causing flow to be

from the RBES

D.

BWST.

Question 167 EAP062301 EAP062301

Incorrect: With BWST level not decreasing ,this indicates no inventory being used from

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C A D A C B B C D B

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

ECCS

Cog level:

CIA 3.714.4

Source:

M 2003

Exam:

oco3301

Test:

S

AuthorIReviewer: LSMIRFA

Wednesday, May 07,2003 01:3922 PM

44

39. 006A4.05 001/2/1/ECCS/C/A 3.9/3.8R'IEW/OC03301/FULSM/RFA

You are performing EOP Enclosure 5.1. At step 13 you find that both BWST suction valves

(1 HP-24 and IHP-25) are closed.

You then perform the following step:

IF both BWST suction valves (IHP-24 and IHP-25) are closed,

THEN perform the following:

A.

Ensure the following are open:

1 LP-6

1 LP-7

1 LP-9

1 LP-10

ILP-15

1 LP-16

B.

C.

Start 1A or 1B LPI Pump.

Dispatch an operator to open IHP-363 (Letdown Line To LPI Pump Suction Block)

(Unit 1 LPI Hatch area).

Which one of the following describes what these steps have accomplished?

A. Cross tied the HPI and LPI pump suction.

6. Cross tied the HPI and LPI pump discharge.

c. aligned HPI system discharge to the LPI pump suction.

D.? aligned LPI system discharge to the HPI pump suction.

Wednesday, May 07,2003 01:39:22 PM

45

GO TO Step 13.

A.

the same actions as steps 10 through 13 below for HPI flow verification. Therefore the RNO

skips HPI verification.

E.

1.2

If RCS is saturated, Rule #2 will be performed as a higher priority. Rule #2 will perform

If RCS is subcooled, HPI verification will be performed here.

Ensure the following are open:

1 HP-24

1 HP-25

RNO:

(OBJ R10) IF both BWST suction valves

(1 HP-24 and 1 HP-25) are closed,

THEN perform the following:

A.

Ensure the following are open:

1 LP-6

1 LP-7

1 LP-9

1 LP-10

ILP-15

1 LP-16

E.

C.

(Unit 1 LPI Hatch area).

The steps above will align LPI system discharge to the HPI pump suction.

Suction can be supplied to the HPI Pumps through ILP-15 and ILP-16 after passing through

the LPI Coolers. This flowpath would involve the LPI Pumps taking suction from the BWST..

MCS

Time:

1

Points:

1.00

Version: 0 I 2 3 4 5 6 7 8 9

Answer: D B C D C A D D C C

Start 1A or 1 B LPI Pump.

Dispatch an operator to open 1HP?363 (Letdown Line To LPI Pump Suction Block)

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

ECCS

Cog level:

C/A 3.9/3.8

Source:

NEW

Exam:

OC03301

Test:

R

AuthodReviewer: LSMiRFA

Wednesday, May 07,2003 01:39:22 PM

46

40. 007K1.03 001/2/1/QUENCH TANWM 3.0/3.2/NEW/OC03301/R/LSM/RFA

The level of the Reactor Coolant Quench Tank is slowly rising. Which one of the following

could have caused this to occur?

A. Core flood tank relief valves.

B. LPI suction relief valves.

C. Reactor high point vents.

D. RCP seal leakage.

A, b, and c not connected to quench tank

OP-OC-PNS-CPS

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D A D C D D C B A D

Scramble Range: A - D

Tier:

2

Group:

1

Keyword

QUENCH TANK

Cog level:

M 3.0/3.2

Source:

NEW

Exam:

OC03301

Test:

R

AuthoriReviewer: LSMIRFA

Wednesday, May07,2003 01:39:22 PM

47

41. 008A2.01 OO112/llCCS/ClA 3.3/3.6/NEWlOC03301/R/LSM/RFA

You are the OATC for unit 1. Unit 1 is at 73% power.

CCW flow slowly drops to 500 gpm.

CC to 2 RCPs auto isolates.

1-HP-5 remains open.

RCP seal return valves remain open.

Which one of the following are the correct actions to respond to this event?

Enter API1INl7001020 and:

A. Trip the reactor and stop the affected RCPs.

B. Trip the reactor and go to 2/0 RCP operation.

C. Trip the reactor, stop all RCPs, and enter AP/25

D: Open ICC-7, ICC-8 and start the standby CCW pump.

APll I N 1 7001020 pages 1 and 2

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D C C C B B B D C A

Scramble Range: A - D

Tier:

2

Group:

1

Keyword

ccs

Cog level:

CIA 3.313.6

Source:

NEW

Exam:

OC03301

Test:

R

AuthorlReviewer: LSMIRFA

WednBsday, May 07,2003 01:39:22 PM

48

42. 008A4.0 1 00 1121 1 ICCWICIA 3.313.1 MEWIOC0330 IIRILSMIRFA

I&E is performing testing during a refueling outage. The 17E technician inadvertently presses

the green "CC Interlock button" located in System Logic Cabinet No. 3 in the cable room.

Which one of the following is the consequence of pressing this button?

A. CC-7 and 8 will no longer close on actuation of ES Channels 5 and 6 respectively

B. Letdown cooler CC inlet valve CC-1 (CC-2) may now be opened after the letdown cooler

inlet valve HP-1 (HP-2) is opened.

C. A reactor coolant pump can now be started if CC flow is less than 575 GPM.

D? CRDs can now be energized without component cooling water.

1 .I

A.

B.

CRDs.

C.

flow will not affect a running RCP.

D.

valve HP-1 (HP-2) will open.

E.

If CC-7 or CC-8 goes closed, the CC pumps will trip and automatically restart when CC-7 and

CC-8 are reopened.

A.

(OBJ R16) The component cooling system must be in operation for any of the following

conditions:

1.

Control rod drives energized. There is an interlock to prevent the CRDs from being

energized without component cooling water, but will not de-energize the drive upon loss of

cooling water.

Instructor note:

This interlock can be overridden by pressing green "CC Interlock button" located in System

Logic Cabinet No. 3 in the cable room to allow I&E testing of CRDs during unit outage.

(OBJ R15) Interlocks Associated With the CC System

If in AUTO, the standby CC Pump starts at 575 GPM flow.

If de-energized, the CRDs cannot be energized if CC flow is less than 138 GPM to the

A reactor coolant pump cannot be started if CC flow is less than 575 GPM. Low CC

Letdown cooler CC inlet valve CC-1 (CC-2) must be open before letdown cooler inlet

CC-7 and 8 close on actuation of ES Channels 5 and 6 (respectively)

Prevents thermal damage to the CRD stators

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D B D A C C B D D A

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

ccw

Cog level:

CIA 3.313.1

Source:

NEW

Exam:

OC03301

Test:

R

AuthorIReviewer: LSMIRFA

Wednesday, May 07,2003 01 :39:22 PM

49

43. 01 OK2.01 00112111PZR PRESSURHM 3.0/3.4R\\IEWIOC0330I/R/LSM/RFA

Which one of the following describes how the pressurizer heaters for each unit are normally

supplied?

They are supplied from:

A. safety related motor control centers. The pressurizer heaters are divided among three

4160 volt ES buses.

B. non-safety related motor control centers. The pressurizer heaters are divided among two

4160 volt ES buses such that the loss of one entire 4160 volt bus.

C: non-safety related motor control centers. The pressurizer heaters are divided among three

4160 volt ES buses.

D. Safety related motor control centers. The pressurizer heaters are divided among two 4160

volt ES buses such that the loss of one entire 4160 volt bus.

Solution - C

The pressurizer heaters for each unit are normally supplied from non-safety related motor

control centers (MCCs) XH, XI, XJ, and XK. The pressurizer heaters are divided among the

three 4160 volt ES buses such that the loss of one entire 4160 volt bus will not preclude the

capability to supply sufficient pressurizer heaters to maintain natural circulation in MODE 3.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C B C B C A C D B C

Scramble Range: A - D

Tier:

2

Group:

1

Keyword

PZR PRESSURE

Cog level:

M 3.013.4

Source:

NEW

Exam:

OC03301

Test:

R

AuthoriReviewer: LSMIRFA

Wednksday, May 07,2003 01:39:22 PM

50

44. 01 1 K3.02 001i212iPZR LEVELICIA 3.5/3.7/NEW/OC03301IRILSMIRFA

Which one of the following statements describes the plant response to a pressurizer level

channel (controlling channel) failing LOW? (ASSUME no operator action taken and the reactor

is at 100% power).

HP-120:

A,' OPENS, actual Pzr level increases and RCS pressure increases.

B. CLOSES, actual Pzr level decreases and RCS pressure decreases.

C. CLOSES, actual Pzr level decreases and pressurizer heaters turn off.

D. OPENS, actual Pzr level decreases and RCS pressure decreases.

OP-OC-PNS-PZR,

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A C D D C B A A C C

Scramble Range: A - D

Tier:

2

Group:

2

Keyword:

PZR LEVEL

Cog level:

CIA 3.513.7

Source:

NEW

Exam:

OC03301

R

AuthoriReviewer: LSMIRFA

Wednbsday, May 07,2003 01:39:22 PM

51

45. 012K5.01 001/211/RPS/M 3.313.XIBANK 2003/OC03301/ULSMIRFA

Unit 1 plant conditions:

A Group 6/Rod 4 dropped into the core.

An ICs runback was completed.

Reactor power imbalance has become excessive.

I&E has lowered the RPS setpoints for the FluxlFlow/lmbalance trip.

L!

ich one of the following describes core limit(s) that will be protected by re

setpoint?

g the RPS

A. Fuel Centerline Temperature only.

B.* Fuel Centerline Temperature and DNBR.

C. Excessive core operating pressures and DNBR.

D. Excessive core operating temperatures and pressures.

Bank Question 427

A.

limit

B.

fluxlflowhmbalance trip is reduced. And is the basis for the trip setpoint

C.

D.

Pressure is not part of the basis.

Incorrect - Fuel Centerline temperature alone is not the only restrictive core operating

Correct - Fuel Centerline temperature and DNBR are concerns when the

Incorrect- pressure is not contained in the basis for the resetting of the trip setpoint.

Incorrect- the basis for the trip is temperature however it is fuel centerline temperature.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B A D B C A C B B C

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

RPS

Cog level:

M 3.313.8

Source:

BANK 2003

Exam:

OC03301

Test:

R

AuthodReviewer: LSM1RFA

Wednesday, May 07,2003 01:39:23 PM

52

46. 0 I2K6.04 00 1/2/1/RPS/C/A 3.3/3.6/NEW/OC03301/R/LSM/RFA

Unit 1 is operating at 91% power when the OATC inadvertently places the S/D Bypass Key

switch to "Bypass"? Which one of the following will occur?

A. The Unit will continue to operate at 91%. However, the low pressure trip, the variable low

pressure trip, the flux/flow - imbalance trip, and the power/RCPs trip normally associated

with the RPS will be bypassed.

B. The Unit will run back to 74%. The low pressure trip, the variable low pressure trip, the

flux/flow - imbalance trip, and the power/RCPs trip normally associated with the RPS will be

bypassed.

C.' The unit will trip on high reactor pressure.

D. At 75% power, the bypass interlock switch is bypassed.

Solution C

In addition to bypassing the four trip parameters above, the "Bypass" position automatically

inserts a high RCS pressure trip set point of 1720 psig, so that the plant cannot be operated

normally with portions of the RPS in SID Bypass.

A.

Protective Functions Bypasses

1.

(OBJ R5) Shutdown Bypass

a)

key-switch located in that channel's RPS cabinet (A2, 82, C2, or D2). (OC-IC-RPS-8)

b)

physics testing, and startup procedures. It provides the capability to reset the CRD breakers

when the plant is shut down. (Pull Group 1 to 50%).

c)

are operating. This would keep RPS tripped.

(OBJ R5.2)

a)

variable low pressure trip, the flux/flow - imbalance trip, and the power/RCPs trip normally

associated with the RPS.

b)

automatically inserts a high RCS pressure trip set point of f1720 psig, so that the plant cannot

be operated normally with portions of the RPS in S/D Bypass.

1)

While the normal high pressure trip of E2355 psig is not electrically bypassed it is

basically nonfunctional because RPS will trip before the setpoint can be reached.

The setpoint of f1720 psig is selected for the new high pressure trip so that the plant must first

be shutdown, using normal procedures, before S/D Bypass can be initiated; 1720 psig is below

the normal low pressure trip of 1800 psig, so that the plant must first be maneuvered past the

normal low pressure trip point before going to S/D bypass. 1710 psig is the actual setpoint used

for conservatism.

Certain segments of the RPS protective functions for a channel can be bypassed with a

(OBJ R5.1) Bypass function is to provide capability to perform CRD testing, zero power

(OBJ R5.2) During startup the RCS pressure is low and only one or two RCPs, at times,

Positioning S/D Bypass Key switch to "Bypass" bypasses the Low Pressure Trip, the

In addition to bypassing the four trip parameters above, the "Bypass" position

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C B C C B A D D D B

Scramble Range: A - D

Wednesday, May 07,2003 01:3923 PM

53

Tier:

2

Keyword

RPS

Source:

NEW

Test:

R

Wednesday, May 07,2003 01:39:23 PM

Group:

1

Cog level:

CIA 3.313.6

Exam:

OC03301

AuthorlReviewer: LSMIRFA

54

47.

0 1 3A1.06 0011211 IBW STIESFASICIA 3.613.9R*IEWIOC0330 1 IRILSMIRFA

Unit 1 plant conditions:

AllSCMs =o"F

RCS Temperature = 456°F and stable

BWST level = 11.5' and is slowly decreasing

ES 1-8 actuated

OTSG levels are being maintained at LOSCM Setpoint

Turbine Bypass Valves are in AUTOMATIC

Which one of the following describes the current plant condition?

The OSTGs

. The

is the water source to the RCS.

A.' can not remove heat / BWST

6. can not remove heat I RBES

c. are removing heat I BWST

D. are removing heat I RBES

Solution : A. Based on Bank 2003 question 202

A)

greater than or equal to RCS pressure since TBV's are controlling at setpoint +I25 and

minimum setpoint is 600 psig. BWST suction swap to RBES is in progress, but RBES valves

are not opened until 9' therefore even if LP-15 and 16 have been opened, suction source

remains the BWST.

B)

wrong water source

C.

D)

MCS

Time:

1

Points:

1.00

Version: 0 I 2 3 4 5 6 7 8 9

Answer: A A B D B D D B A C

Correct. SGs can not be removing heat with the TBV's in auto, SG pressure would be

SGs can not be removing heat with the TBV's in auto,

SGs can not be removing heat with the TBV's in auto, wrong water source

Scramble Range: A - D

Tier:

2

Group:

I

Keyword:

BWSTIESFAS

Cog level:

CIA 3.613.9

Source:

NEW

Exam:

OC03301

Test:

R

AuthoriReviewer:

LSMIRFA

WednBsday, May 07,2003 01:39:23 PM

. .

~.

55

48. 013K3.03 001/2/1/ESF/C/A

4.3/4.7/NEW/OC03301/R/LSM/RFA

A LOCA concurrent with a loss of some control board indications has occurred on Unit 2. The

STA calculates the RCS and containment pressure. He reports that RCS pressure - 100 psia

and containment pressure - 20 psia. The STA also notes that RB spray has not actuated.

Which one of the following describes the actions that should be taken and the basis for this

decision?

A,' No action should be taken, this is below the ES setpoint for RBS.

6. RBS should be actuated, this is below the actuation pressure assumed in the UFSAR.

C. RBS should be actuated, this is above the actuation pressure assumed in the UFSAR.

D. This is above the actuation pressure assumed in the UFSAR. Containment should be

vented, then the RES should be initiated.

The UFSAR assumes that RBS is actuated at 30 psig. The actual ES setpoint is 10 psig. The

20-psi difference between the safety analysis assumption and the plant setpoint is ample to

account for instrument uncertainty.

The purpose of the Reactor Building Spray initiation is to protect the Reactor Building by

removing heat from the RB via the LPI system decay heat coolers.

In addition, the RES system can help provide protection while not actually removing heat from

the RB.

The RBS system can be configured in many different ways while being used. The RBS can be

aligned to spray cool water from the BWST into the RB atmosphere. As the spray condenses

steam in the RB, the energy formerly in the steam is transferred to the liquid entering the RB

sump. The water in the sump is not cooled until the LPI system is realigned to pass water

through the LPI decay heat coolers. Current station procedures allow the water from the sump

to be sprayed back into the RB without being cooled. As with the injection mode of operation,

this mode will condense steam but will not remove heat from the RB. However, the

condensation of steam by the spray will work to decrease the internal pressure of the RB by

reducing the partial pressure of the steam. In this manner, the RB spray will help protect the

RB integrity without actually providing RB cooling.

The UFSAR assumes that RBS is actuated at 30 psig. The actual ES setpoint is 10 psig. The

20-psi difference between the safety analysis assumption and the plant setpoint is ample to

account for instrument uncertainty.

The UFSAR states that a 2.4-second ESFAS delay is assumed for Reactor Building Spray

actuation.

T. S. basis for the 4 psi and 15 psi setpoints is to establish a setting which would be reached

immediately in the event of a DBA, cover the entire spectrum of break sizes, and yet be far

enough above normal operation pressures to prevent spurious initiation.

Wednesday, May 07,2003 01 :39:23 PM

.

. ..

.

56

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A A C C B A D D B D

Scramble Range: A - D

Tier:

2

Group:

1

Keyword

ESF

Cog level:

CIA 4.314.7

Source:

NEW

Exam:

OC03301

Test:

R

AuthorlReviewer: LSMIRFA

Wednesday, May 07,2003 01:39:23 PM

57

49. 015 GEN 2.1.32 001/2/2R\\II/M 3.4/3.8/M 2003/0C03301/S/LSM/RFA

1

Unit 2 plant conditions:

Unit power escalation are in progress.

Reactor power = 15% and is increasing.

OP/l102/01, Controlling Procedure for Unit Startup is in progress.

Which one of the following describes the MAXIMUM NI calibration error allowed per Limits an1

Precautions of the controlling procedure?

Nls SHALL be maintained within the range of -%

conservative to -%

non-conservative,

A:IO,

4

B. 4, 10

c. 2, 2

D. 2, 1

I

Bank question 95 CPOl0302 (SRO ONLY)

A. Correct - L/P #I7 describes MAX NI error during power maneuvering 10/4

B. Incorrect - correct numbers swapped

C. Incorrect - Steady state power operation limits

D. Incorrect - Steady state calibration limits

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A C C C D B B C A A

Scramble Range: A - D

Tier:

2

Group:

2

Keyword

NI

Cog level:

M 3.413.8

Source:

M 2003

Exam:

OC03301

Test:

S

AuthodReviewer: LSM/RFA

Wednesday, May 07,2003 01:3923 PM

.. .

58

50. 0 16A2.0 1 00 1/2/2/"ISIC/A

3.013.1 /M 1 992IO 1 I20IOC0330 1 IRILSMIRFA

Plant conditions on Unit 1 are as follows:

- The SASS Channel for Th loop B is in AUTOMATIC.

- The selected Th signal for loop B slowly increases until a

mismatch of 4% with the nonselected signal has occurred.

Which one of the following describes the operation that places the "good" Th loop B signal in

operation?

A. SASS remains in AUTO and automatically selects the "good" signal.

B. SASS remains in AUTO initiating a mismatch alarm and the operator selects the good

signal with the normal select switch.

C.' SASS trips to manual and the operator must position the key switch to the "good" signal

with the normal select switch on 1 UBI.

D. SASS trips to manual and the operator must position the toggle switch to the "good" signal

in RPS Cabinet E.

Oconee Lesson Plan OP-OC-IC-RCI, pg 52-54 and Fig OP-OC-IC-RCI,

Temperature Indications

Obj. R11, R12, R36, R37, R38, R39

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C D C C D D D B A D

Scramble Range: A - D

Tier:

2

Group:

2

Keyword:

NNlS

Cog level:

CIA 3.013.1

Source:

M 1992/01/20

Exam:

OC03301

Test:

R

AuthorIReviewer: LSM/RFA

Wednpsday, May 07,2003 01:39:23 PM

59

51. 022A1.04 00112/1/CCSIM 3.2/3.3/NEW/OC03301/R/LSM/RFA

Unit 3 is operating at 100% rated power when the Component Cooling Water Containment

Return valve (CC-8) fails closed:

Which one of the following is the correct IMMEDIATE operator action and WHEN the operator

should perform the action?

A. Trip the reactor when the pressurizer low level alarm is received

B. Trip individual RCPs when motor stator temperature exceeds 185 deg F.

Cy Trip the reactor when two CRD stator temperatures exceed 180 deg F.

D. Trip the individual RCPs when their respective thermal barrier temperature exceeds 225

deg F.

MCS

Time:

I

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C B C B A B C A B A

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

ccs

Cog level:

M 3.2/3.3

Source:

NEW

Exam:

OC03301

Test:

R

AuthoriReviewer: LSMIRFA

Wednesday, May 07,2003 01:39:23 PM

60

52. 026 GEN 2.1.27 001/211/CCSIM 2.8/2.9lNEWlOC03301lR/LSMlRFA

Which one of the following describes the purpose of the Reactor Building Spray System?

A. Removes sensible AND latent heat from the containment atmosphere, entrains fission

product iodine and decreases radiation levels in containment.

B. Removes ONLY latent heat from the containment atmosphere, entrains fission product

iodine, and decreases radiation levels in containment.

C.' Removes sensible AND latent heat from the containment atmosphere and entrains fission

product iodine.

D. Removes ONLY sensible heat from the containment atmosphere and entrains fission

product iodine.

(decrease radiation levels in containment) is wrong. It may pull contaminants that give off

radiation out of the atmosphere, but it redeposits it in the sump.

(Obj R1)Purposes of the Reactor Building Spray (RBS) System

The Reactor Bldg. Spray system has no function during normal plant operation.

When actuated by high Reactor Building (RB) pressure, the system provides two major

functions:

Removes sensible and latent heat from the containment atmosphere.

Operation of the RBS System also serves to entrain fission product iodine (released into the RB

during a LOCA) into the spray water, thereby reducing possible iodine leakage to the

environment (to meet IOCFRIOO criteria concerning offsite dose limits).

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C D C D C C B D D D

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

ccs

Cog level:

M 2.812.9

Source:

NEW

Exam:

OC03301

Test:

R

AuthorlReviewer: LSMIRFA

WednFsday, May 07,2003 01:39:23 PM

61

53. 026K3.0 1 00 I/2/1/CCS/CIA 3.914. I/NEW/OC03301 IWLSMIRFA

Unit 2 is operating at 100 % power when an ESG RE pressure analog channel fails upscale.

An instrument technician is dispatched to investigate. The technician goes to the wrong

cabinet and causes an additional ESG RB pressure analog channel to fail upscale.

Assume no operator action, which one of the following will occur?

Both RBS pumps start and:

A. BS-I remains closed and BS-2 opens.

LP-21 supplies RES pumps from BWST, LP-22 remains closed.

B.* BS-I and BS-2 open.

LP-21 and LP-22 supply RES pumps from BWST.

C. BS-I opens and BS-2 remains closed.

LP-21 supplies RES pumps from BWST, LP-22 remains closed.

D. BS-1 and BS-2 remain closed.

LP-21 and LP-22 do NOT supply RES pumps from BWST.

(Obj R6) ES Mode (Channels 7 and 8 )

Setpoint

The RBS System automatically actuates if two of the three ESG RB pressure analog channels

reach 10 psig.

The TS required setpoint is < 15 psig RB pressure.

The following actions occur if the RBS System actuates:

Both RES pumps start.

BS-I and BS-2 open.

LP-21 and LP-22 supply RBS pumps from BWST.

MCS

Time:

1

Points:

1.00

Version: 0 I 2 3 4 5 6 7 8 9

Answer: B C C A B A B C D D

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

ccs

Cog level:

C/A 3.914.1

Source:

NEW

Exam:

oco3301

Test:

R

AuthoriReviewer: LSMlRFA

Wednesday, May 07,2003 01:39:24 PM

62

54. 029K1.04 001/2/2/PURGE/M 3.0/3.1/M 2003/0C03301/R/LSM/RFA

Following a LOCA, potential leakage past the purge system reactor building isolation valves is

prevented from being released directly to the environment by which one of the following?

A. inlet and outlet bleed lines open-ended into containment.

B. Outlet bleed lines open-ended into the Penetration Rooms and inlet bleeds lines open

ended into containment.

C. Inlet bleed lines open-ended into the Penetration Rooms and outlet bleeds lines open

ended into containment.

D I Inlet and outlet bleed lines open-ended into the Penetration Rooms,

Modified bank 2003 question 549

A, B, and C - new distractors

D) Correct- bleed lines are located between the outer most isolation valves on both the inlet

and outlet purge duct work. These bleed lines vent any leakage from the RB through the purge

isolation vales into the Penetration Rooms. The PRV system will then process the leakage and

the leakage will not be released to the environment.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D D D C B C D B D D

Scramble Range: A - D

Tier:

2

Group:

2

Keyword:

PURGE

Cog level:

M 3.0/3.1

Source:

M 2003

Exam:

OC03301

Test:

R

AuthodReviewer: LSMiRFA

Wednesday, May 07,2003 01:39:24 PM

63

55. 034 GEN 2.1.21 0011212lFUEL HANDLINGIM 2.8/2.9/NEW/OC03301IRILSMIRFA

Which one of the following is the correct purpose of the fuel handling system?

The system is designed to:

A,' MINIMIZE the possibility of mishandling that could cause fuel assembly damage and/or

potential fission product release AND provide a safe, effective means of transporting/

handling fuel from the time it reaches the station in an unirradiated condition until it leaves

the station after post irradiation cooling.

B. PREVENT the mishandling that could cause fuel assembly damage and/or potential fission

product release ONLY.

C. MINIMIZE the possibility of mishandling that could cause fuel assembly damage and/or

potential fission product release ONLY.

D. PREVENT the mishandling that could cause fuel assembly damage and/or potential fission

product release AND provide a safe, effective means of transporting/ handling fuel from the

time it reaches the station in an unirradiated condition until it leaves the station after post

irradiation cooling.

RFA rewrote the Q.

FH-FHS Lesson Plan

ENABLING OBJECTIVES # 1

State the purpose of the Fuel Handling System and discuss the problems that the Fuel

Handling System is designed to prevent. (RI)

The fuel handling system is designed to provide a safe, effective means of transporting and

handling fuel from the time it reaches the station in an unirradiated condition until it leaves the

station after post irradiation cooling. The system is designed to minimize the possibility of

mishandling that could cause fuel assembly damage and/or potential fission product release.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A D D D D C B B B D

Scramble Range: A - D

Tier:

2

Group:

2

Keyword

FUEL HANDLING

Cog level:

M 2.812.9

Source:

NEW

Exam:

oco3301

Test:

R

AuthorlReviewer: LSMIRFA

Wednesday, May 07,2003 01:39:25 PM

64

56. 035A4.05 00112/2/SG SYSTEMICIA 3.8/4.0/M 1992/01/20/OC03301/RILSM/RFA

Which one of the following are the key parameters monitored as the OTSGs fill to the OTSG

natural circulation level setpoint?

A. Pressurizer level and CETC temperatures.

B. Pressurizer pressure and hot leg temperatures.

c. OTSG levels and CETC temperatures.

D.' OTSG pressures and cold leg temperatures.

Oconee: OP-OC-TA-AM1

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D D A B D B B A C B

Scramble Range: A - D

Tier:

2

Group:

2

Keyword:

SG SYSTEM

Cog level:

C/A 3.814.0

Source:

M 1992/01/20

Exam:

OC03301

Test:

R

AuthorIReviewer: LSMIRFA

Wednesday, May 07,2003 01:39:25 PM

65

57. 039K1.02 OOl/Z/l/ADV/M 3.3/3.3/NEW/OC03301/RILSM/RFA

Just inside the 5th floor of the turbine building, a 12" line on each main steam line taps off and

runs back outside the turbine building. Which one of the following is the purpose of the valves

on these lines?

These valves are designed to be used for a controlled plant cooldown in the event that the:

A. Atmospheric Dump Valves (ADVs) become inoperative. These valves are manually

operated.

B:' Turbine Bypass Valves (TBVs) become inoperative. These valves are manually operated.

c. Atmospheric Dump Valves (ADVs) become inoperative. These valves are two chain

operated "drag" valves designed to allow maintenance on MS-153 & MS-155.

D. Turbine Bypass Valves (TBVs) become inoperative. These valves are two chain operated

"drag" valves designed to allow maintenance on MS-153 & MS-155.

A.

1.

and runs back outside the turb. bldg.

Atmospheric Dump Valves (ADVs) / Main Steam Vents

Just inside the 5th floor of the turb. bldg., a 12" line on each main steam line taps off

2.

controlled plant cooldown in the event that the Turbine Bypass Valves (TBVs) become

inoperative.

a)

ADVs are credited for reducing SG pressure and cooling the RCS when condenser

vacuum is lost during SGTR and SBLOCA event analysis

3.

Originally two manual gate isolation valves were installed on each atmospheric vent line

(MS-153 & 154 "A" line and MS-155 & 156 on " B line). Due to the difficulty in operating these

valves (caused by the large DP), additional piping and valves were added on each unit.

A 1" bypass line now exists around MS-153 & MS-155. A 1" gate valve installed in each

bypass line allows for reducing the DP across these 12" gate valves which allows for ease of

operation.

Another line which bypasses MS-154 and MS-156 has a chain operated "drag" valve installed.

These drag valves are much easier to operate and are suited better for throttling. Many turns

of the handwheel are required for stroking these valves which will provide for a more controlled

cooldown in the event they are needed.

(OBJ R11) There are manually operated valves on these lines designed to be used for a

MCS

Time:

I

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B C D C D D C B A A

Scramble Range: A - D

Tier:

2

Group:

1

Keyword

ADV

Cog level:

M 3.3/3.3

Source:

NEW

Exam:

OC03301

Test:

R

AuthodReviewer: LSMiRFA

Wednesday, May 07,2003

01:39:25 PM

66

58. 039K5.01 001/2/1/MAIN STEAMIM 2.9/3.1/NEW/OC03301IRILSM/RFA

Which one of the following describe the system that Oconee uses to prevent water hammers

from occurring in an "idle" steam line.

All steam lines in the plant have small drain lines that

valve.

A. automatically open on the downstream

B." automatically open on the upstream

side of the isolation

C. are operated manually on the downstream

D. are operated manually on the upstream

I

A.

1.

to collect condensation in the line where the steam is bottled up.

2.

valve in the line, to keep the condensation from building up.

3.

steam line from filling with water andlor to prevent water hammers from occurring. This is

accomplished by the use of a steam trap.

Thermostatic steam traps at Oconee are basically a valve with an expandable bellows acting as

a valve disk.

Steam Traps (OBJ R14, 15)

An "idle" steam line (one in which there is no flow due to a closed isolation valve) tends

All steam lines in the plant have small drain lines on the upstream side of the isolation

These small drain lines automatically drain condensate to the condenser to prevent the

MCS

Time:

I

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B C D B B C B D D A

Scramble Range: A - D

Tier:

2

Group:

1

Keyword

MAIN STEAM

Cog level:

M 2.913.1

Source:

NEW

Exam:

OC03301

Test:

R

AuthorlReviewer: LSM/RFA

Wednesday, May 07,2003 01:39:25 PM

67

59. 055A3.03 00112/2/CARS/M 2.512.7/NEWlOC03301/R/LSM/RFA

Valve 1V-I96 (CSAE Exhaust to Stack Drain) must be locked closed at all times if activity

above background exists on the OTSG secondary side.

Which one of the following is the reason for this action?

A,' This prevents the release of radioactive liquid to the trench.

B. This prevents the CSAE relief valve from cycling.

C. This prevents the condenser from being isolated on high activity.

D. This maintains high backpressure on CSAE.

A.

all times if activity above background exists on the OTSG secondary side. (This prevents the

release of radioactive liquid to the trench.)

In May of 1999, Unit 3 3C CSAE relief valve began lifting and closing several times. The steam

supply was isolated hoping the relief valve would reseat. As a result, air entered through the

relief valve and entered the condenser causing U3 to begin losing vacuum. Power was

reduced per the AP to 73%, 3C CSAE was fully isolated and the Main Vacuum Pumps were

placed in service

Faulty Air Removal

a)

High condensate temperature to the CSAE will cause a reduction in air ejector

efficiency.

b)

Low steam pressure or clogged steam strainers will reduce the velocity of steam and

thus reduce the volume of air the CSAE will handle.

c)

High backpressure on CSAE will affect air removal.

Loss of loop seal would "short cycle" the air back into the system.

(0BJ.RG)Valve (1)(2)(3) V-196 (CSAE Exhaust to Stack Drain) must be locked closed at

d)

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A D A D A C D A D A

Scramble Range: A - D

Tier:

2

Group:

2

Keyword:

CARS

Cog level:

M 2 3 2 . 7

Source:

NEW

Exam:

OC03301

Test:

R

AuthorIReviewer: LSM/RFA

Wednesday, May 07,2003 01:39:25 PM

68

60. 056A2.04 0011211IC0NDENSATEICIA 2.612.81M 2003lOC03301lSILSMlRFA

Unit 1 conditions:

INITIAL CONDITIONS:

Unit startup in progress

Reactor power = 30% and increasing

"1A Main Feedwater Pump operating

" I C and "IB" HWPs are operating

"1A HWP in AUTO

" I C CBP is operating

"1A CBP in AUTO

CURRENT CONDITIONS:

" I C CBP trips due to a breaker electrical fault

Which one of the following automatic actions has occured?

The operator will refer to the Annunciator Response Procedure and verify thz

A. reactor tripped on low MFDWP suction pressure.

the:

B. operating MFDWP tripped on low MFDWP suction pressure after 30 seconds.

C.' standby CBP auto started on low MFDWP suction pressure.

D. standby HWP auto started on low CBP suction pressure.

2003 bank question # 37

A.

would take the loss of both main feedpumps to cause the trip.

incorrect, there is not a reactor trip on low main feedwater pump suction pressure. It

B.

pressure and the running feedwater pump should not trip. Does not trip until f 235 psig on the

feedwater pump suction.

C.

correct, the standby condensate booster will start when feedwater pump suction

pressure decreases to 360 psig.

D.

incorrect, condensate booster suction pressure will not decrease because the Hotwell

pump is still running.

incorrect, the standby booster pump will start at 360 psig on the feedwater pump suction

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C C C B B A B B A B

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

CONDENSATE

Cog level:

.

CIA 2.612.8

Source:

M 2003

Exam:

OC03301

Test:

S

AuthorIReviewer: LSMIRFA

Wedn-sday, May 07,2003 01 :39:25 PM

69

61 . 059A1.03 001/211/MFW/M 2.712.9/NEWlOC03301/R/LSM/RFA

The Main FDW Block Valves are placed in OPEN when the Startup Control Valves reach 90%.

Which one of the following describes the basis for this step?

A:'

To prevent feedwater flow swings.

B. To prevent feedwater pump cavitation.

C. To allow complete closure of the minimum flow valves before reaching 100% power.

D. To bypass the Main FDW Block Valve auto open at a composite demand of 9.0%.

Wednesday, May 07,2003 01:39:25 PM

70

CF-FDWrlla

Automatic ICs demand signals to the Main and Startup Control Valves are developed from a

common signal source called the Valve Composite Demand

1)

Control Valve), a bistable will automatically open the Main FDW Block Valve (if in AUTO).

1.

Main Blocks (FDW-31 and FDW-40)

a)

Motor operated from control room (UBI).

b)

OPEN, AUTO, CLOSE.

c)

ICs sends a signal to close the Main FDW Blocks on a Rx trip.

d)

Automatic ICs demand signals to the Main and Startup Control Valves are developed

from a common signal source called the Valve Composite Demand

1)

Power increase: At a composite demand of 9.0% (equivalent to 90% open on the SU

Control Valve), a bistable will automatically open the Main FDW Block Valve (if in AUTO).

2)

Power decrease: At a composite demand of 5.0%, the Main FDW Block Valve will close

(if in AUTO)

e)

During some unit startups, when the Main Blocks were opened, leakage past the seat of

the closed Main Control Valves would cause SG levels to increase. This would result in the SU

Control Valves, which are controlling SG levels to start close and return SG levels to setpoint

(25 inches SUR).

1)

would close. After they closed, leakage past the seat of the Main Control Valves would stop,

and SG levels would decrease, causing the SU Control Valves to re-open.

2)

up a Feedwater cycle that could quickly become divergent. Once divergent cycle starts, a

FDWP trip could occur due to Overspeed or High Discharge Pressure if not properly mitigated.

This would lead to a UnitlReactor Trip.

Power increase: At a composite demand of 9.0% (equivalent to 90% open on the SU

With the Main Blocks in AUTO, as the SU Control Valves reached 50%, the Main Blocks

As the SU Control Valve reaches 90%, the Main Block would once again open, setting

3)

OPEN when the Startup Control Valves reached 90%, and were left in OPEN until Feedwater

demand was high enough to ensure that the SU Control Valves would not close. Current

procedures require that the Main Blocks (and SU Blocks) be in AUTO prior to exceeding 700

psig MS pressure (to satisfy MSLB/AFIS circuit operability requirements).

Procedures do allow FDW-31 and 40 to be placed in OPEN if FDW control problems occur as a

result of the valves opening in AUTO. The blocks will then be placed in AUTO when the Main

Control Valve has reached 10% OPEN, since at that point, the SU Control Valve demand is at

loo%, and is not likely to decrease until power level decreases for unit shutdown.

2)

(if in AUTO)

d)

from a common signal source called the Valve Composite Demand

1)

Control Valve), a bistable will automatically open the Main FDW Block Valve (if in AUTO).

2)

(if in AUTO)

To prevent the Feedwater swing described above, the Main Block Valves were placed in

Power decrease: At a composite demand of 5.0%, the Main FDW Block Valve will close

Automatic ICs demand signals to the Main and Startup Control Valves are developed

Power increase: At a composite demand of 9.0% (equivalent to 90% open on the SU

Power decrease: At a composite demand of 5.0%, the Main FDW Block Valve will close

Wedn$sday, May 07,2003 01:39:25

PM

71

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A D B D B A B B B B

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

MFW

Cog level:

M 2.712.9

Source:

NEW

Exam:

OC03301

Test:

R

AuthorlReviewer: LSMIRFA

Wednesday, May 07,2003 01:39:25

PM

72

62. 061A3.01 001/2/1/AFWlClA 4.2/4.2lNEWIOC03301/WLSMIRFA

You are the NCO on Unit 2. Per EOP Rule 3, you attempt to ensure that an Emergency

Feedwater automatic start occured. It did not. You place the MDEFWPs control switches in

"Run." The pumps still do not start.

You attempt to start the TDEFWP. It also fails to start.

You direct an NE0 to manually start the Emergency Feedwater pump.

Which one of the following describe the Local steps that will be required to start the pump?

Isolate:

A. IA supply to MS-93, then bleed air off the regulator using the moisture petcock and then

start the pump.

B.' IA and AIA supply to MS-93, then bleed air off the regulator using the moisture petcock and

then start the pump.

C. IA, AIA and N2 supply to MS-93, then bleed air off the regulator using the vent port on the

MS-93 supply line and then start the pump.

D. N2 supply to MS-93, then bleed air off the regulator using the vent port on the MS-93

supply line and then start the pump.

A. Needs AIA

B. Correct

C. No N2 supply not vented through port

D. Method required for unit 1

Manual Start of TDEFDWP

a)

MS-93 Failure

1)

Per EOP Rule 3, the NCO should ensure Emergency Feedwater is operating, if

MDEFWPs are not operating, the control switch is placed in "Run" this should open MS-93 by

de-energizing the solenoid. If this fails to start the TDEFWP, an NE0 is sent to manually start

the pump with a (PS) Procedure. Local step will require:

(d)

replace the Swagelok body protector with the vent port on the supply line going to IMS-93.

Bleed air off regulator using moisture petcock. (Not available on Unit 1). On Unit 1

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B B A B B A C D A A

Scramble Range: A - D

WednWay, May 07,2003 01:39:25 PM

. .

73

Tier:

2

Keyword

AFW

Source:

NEW

Test:

R

Wednesday. May 07,2003 01:39:25

PM

Group:

1

Cog level:

CIA 4.214.2

Exam:

OC03301

AuthorlReviewer: LSMIRFA

74

63. 061K6.01 001/2/l/EFWIC/A 2.5/2.8lNEW/OC03301/RILSM/RFA

SG pressure is 1000 psig. The TDEFWP is running. A controller failure has caused FDW-315

& 316 to fail full open.

Which one of the following indications would enable the OATC to determine that this failure

had occured?

The crew would:

A. see a flow mismatch on Total EFDW Flow indications but would NOT see it on the

MDEFDWP Discharge Flow gages.

B.' NOT see a flow mismatch on Total EFDW Flow indications but would see it on the

MDEFDWP Discharge Flow gages.

C. see a mismatch between the indicated flows to each SG. This indicated flow mismatch

could be as much as 300 gpm

D. NOT see a flow mismatch on Total EFDW Flow indications but would see a level change

between the OTSGs because the SG are level dominant.

EFW lesson plan

1.

for pump and discharge piping protection. When a MDEFDWP is started, the ARC (Automatic

Recirculation Control) valve automatically provides recirculation flow.

NOTE: An event has occurred at another plant concerning these same type ARC valves. The

valves failed open due to internal valve failure. One of the problems that came from this failure

was the operators were not able to determine from their flow indications that these valves had

failed. Some examples of what the Oconee operator might see if these MDEFDWP

recirculation valves failed open follows:

The MDEFDWPs have approximately 300 gpm (per pump) recirculation flow to the UST

The initial assumption is that the TDEFDWP is not running.

If SG pressures were at about 1000 psig and the A MDEFDWP recirculation valve failed

open, there would be a mismatch between the indicated flows to each SG. This indicated flow

mismatch could be as much as 300 gpm if FDW-315 & 316 were full open. The operator would

see the flow mismatch and depending on decay.heat could see a lower SG level on the side

with the failed valve. There would not be a pump runout concern unless SG pressures were

800 psig or less and FDW-315 & 316 were full open.

EFDW Flow indications but would see it on the MDEFDWP Discharge Flow gages.

If the operator sees a flow mismatch or low SG level and the TDEFDWP is available, he should

start the TDEFDWP. Starting the TDEFDWP will assure adequate flow to the SGs

If the TDEFDWP were running, the operator would NOT see a flow mismatch on Total

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B C C C A B A A C A

Scramble Range: A - D

Tier:

2

Group:

1

Source:

NEW

Exam:

oco3301

Keyword:

EFW

Cog level:

CIA 2.5/2.8

Test:

R

Author/Reviewer:

LSMlRFA

Wednesday, May 07,2003 01:39.25 PM

75

64. 062A2.10 00 II2IIIAC ELECTRICAL/C/A 3.0/3.3R\\TEW/OC03301/R/LSM/RFA

An NLO reports that a HYCE gauge on the front board for the pressure transmitter for Main

Steam line 1A is reading zero. There are I&C activities currently in the area attempting to

switch power supplies within the panel. Assuming activities in the area have caused a false

instrument reading, which one of the following could have caused this reading?

A,' An interruption of IA to the pressure transmitter.

B. An interruption of DC power to the gauge.

C. A loss of AC electrical power to the gauge.

D. A loss of AC electrical power to the gauge coincident with a loss of DC power to the

pressure transmitter.

Facility check to make sure distractor " B not correct also.

There is a pressure transmitter for each Main Steam line that feeds the HYCE gauge on the

front board. These indications utilize Instrument Air (IA) instead of electrical power and will be

available for use on a Loss of Power but not on a Loss of IA.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A C C B B A A B D A

Scramble Range: A - D

Tier:

2

Group:

I

Keyword:

AC ELECTRICAL

Cog level:

C/A 3.013.3

Source:

NEW

Exam:

OC03301

Test:

R

AuthodReviewer: LSM/RFA

Wedn!?sday, May 07,2003 01:39:25 PM

76

Plant conditions are as follows on Unit 2:

- A Load Shed and a LOCA have occurred concurrently.

- LPI pump B has failed to start.

65. 062K4.02 001/2/l/AC ELECTRICALIM 3.313.4lM 1992/01120/0C03301lR'LSM/RFA

Which one of the following descriptions is correct?

The operation of LPI pump C Automatically:

A. starts after a 5 second time delay.

B. trips and locks out after a 5 second time delay.

C.' trips but can be manually started after a 5 second time delay.

D. started 5 seconds after taking manual control of the Load Shed circuit channels 1 and 2.

1992/01/20

Oconee Lesson Plan OP-OC-PNS-LPI, pg 34

Obj. 14

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C A B C C B A C C D

Scramble Range: A - D

Tier:

2

Group:

1

Keyword

AC ELECTRICAL

Cog level:

M 3.313.4

Source:

M 1992101/20

Exam:

OC03301

Test:

R

AuthorIReviewer: LSMIRFA

Wednesday, May 07,2003 01:39:26 PM

77

66. 063A4.01 001/2/1/DC POWERICIA 2.813.1IBANK 2003lOC03301IWLSMlRFA

During alignment of the SSF DC electrical system, the operator is cautioned NOT to open the

SSF inverter DC input breaker (CB-1) until the inverter is swapped to an AC-line.

Which one of the following is the expected adverse consequence if the operator fails to adhere

to this precaution?

A!

The KSF inverter power fuse may blow.

6. The SSF 600v load center XSF will de-energize.

C. Voltage spikes may damage loads on the bus.

D. Automatic transfer of SSF control power to ES valves will occur.

Bank 2003 Question 350

A. Correct.

B. Incorrect. The inverter supplies power to panelboard KSFC, not load center

XSF.

C. Incorrect. Inverter fuses and rectifiers will limit voltage spike.

D. Incorrect. An automatic swap does not exist.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A D C A C A B A C D

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

DC POWER

Cog level:

CIA 2.813.1

Source:

BANK 2003

Exam:

OC03301

Test:

R

AuthorIReviewer: LSMIRFA

WednWay, May 07,2003 01:39:26 PM

78

67. 063K2.01 0011211lLOSS OF DC POWEWCIA 2.913.11MIOC03301IWLSMIRFA

A loss of DC power to the Turbine Driven Emergency Feedwater Pump (TDEFDWP) has

occurred.

Which one of the following describes the starting of the TDEFDWP if an AUTOMATIC initiation

signal is received?

A. Automatically started because the steam supply valve, MS-93, will be opened when its pilot

solenoid deenergizes, and the operating valve, MS-95, fails open on loss of oil pressure.

B. Manually started by placing the Control Room control switch to RUN due to a loss of auto

initiation logic control power.

C.' Manually started by tripping the trip throttle valve, MS-94, and pulling up on the local hand

starting lever, resetting and slowly opening MS-94 to admit steam for rolling the turbine.

D. Cannot be started since the low oil pressure start permissive for the turbine cannot be met.

Oconee Lesson Plan OP-OC-CF-EF

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C A B A B C A C B A

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

LOSS OF DC POWER

Cog level:

CIA 2.913.1

Source:

M

Exam:

OC03301

Test:

R

AuthorIReviewer: LSMlRFA

Wednesday, May 07,2003 01:39:26 PM

79

68. 064K4.03 001/2/1/EDG/C/A 2.5/3.0/BANK 2003/0C03301/RILSM/RFA

INITIAL CONDITIONS:

The SSF has been manned for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months due to a sustained Loss of HPI and CC.

CURRENT CONDITIONS:

The SSF Diesel Generator speed = 970 RPM.

Which one of the following has failed on the Diesel Generator?

A. Startup Governor.

6. Hydraulic Amplifier.

Cy Electric Governor.

D. Mechanical Governor.

Bank 2003 Question 148

A.

not a Startup Governor associated with the SSF Diesel.

6.

magnetic speed signal to a useable signal by the hydraulic section of the electric governor

system.

C.

speed control and maintain diesel speed between 950-980 RPM.

D. Incorrect- the mechanical governor is what is controlling the speed.

Incorrect- the startup of the SSF Diesel is controlled by the Electric Governor. There is

Incorrect- this is a component controlled by the Electric governor to convert the

Correct- this is the component, which failed. The mechanical governor will take over

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C B D A B B B C C D

Scramble Range: A - D

Tier:

2

Group:

1

Keyword

EDG

Cog level:

C/A 2 3 3 . 0

Source:

BANK 2003

Exam:

OC03301

Test:

R

AuthodReviewer: LSMIRFA

Wednesday, May 07,2003 01:39:26 PM

80

69. 071K4.01 0011212/WGDT/M 2.6/3.0lNEWIOC03301lWLSM/RFA

Which one of the following is the reason that the interim building gas tanks should not be used

as the "in service gas tank?

A. There is no way to recirc interim building gas tank contents.

B. There is no way to align the interim building gas tank to reduce the hydrogen concentration.

C. The only release path is direct to atmosphere.

D.' The interim building gas tank requires about 20 psi Nitrogen pressure to have control of

vent header pressure.

Solution - D

B.

Tank Isolation

1.

Tank should be isolated prior to high pressure alarm (70 psig).

2.

Interim building gas tanks should not be used as the "in service" gas tank since it

initially requires about 20 psi Nitrogen pressure to have control of vent header pressure.

3.

Basic procedure:

a)

Tank should be > 5 psig prior to placing in service, add Nitrogen if required to increase

tank pressure.

b)

Close "recirc" valve for isolated tank and open "recirc" valve for tank placed in service.

c)

Close inlet valve for tank to be isolated and open inlet to tank to be placed in service.

d)

Sample isolated tank for hydrogen.

e)

After tank has been isolated for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , verify that isolated tank pressure is not

decreasing and vent header is controlling normally.

4.

Reducing Hydrogen in a GWD Tank

a)

If hydrogen is > 3%, lower tank to 50 psig by transferring some for the gas to another

tank.

b)

Add 20 psig nitrogen to tank

c)

Resample for hydrogen

d)

Repeat until hydrogen < 3%

C.

Transferring Gas Between Tanks

1.

Normally done from in-service tank to another tank, this adds operational flexibility to

determine which tank is used for in-service work and which tank(s) are used for isolation and

decay.

2.

Procedure:

a)

Open inlet for tank receiving gas

b)

Close inlet for tank transferring gas.

1)

In-service tank pressure should begin decreasing and tank receiving gas should be

increasing pressure as gas flows:

From the in-service GWD Tank

Through GWD-1

To the vent header

Wedngsday, May 07,2003 01:39:26 PM

. .

81

Is compressed by GWD compressor

Discharges to tank being transferred to

When transfer is complete, open inlet for tank remaining in service and close inlet for

Sample isolated tank for hydrogen.

Sampling of waste gas decay tank

5 times weekly and after isolation for hydrogen

Prior to release for activity

Sample flowpath: (sample flows from tank, through sample apparatus, to the vent

(Obj R5) Cross-connecting the vent header

Isolation valves GWD-132 (Vent Header Tie Unit 1) and GWD-134 (Vent Header Tie

Either system (1&2's) or (3's) can be shutdown.

The other system can carry the load.

Should only be made when:

Additional tank space is needed.

Acceptable meteorological conditions exist as indicated on OAC.

c)

tank to be isolated.

d)

D.

1.

Sampling is done

a)

b)

2.

header)

E.

1.

Unit 3) are opened to make essentially one common vent header.

2.

3.

F.

Gaseous Waste Releases

1.

a)

b)

1)

Unfavorable conditions are:

(a)

Positive delta temperature

(b)

Very low wind speed

2)

process of deciding to submit a sample request for release should involve anticipating

Meteorological conditions that will exist at time of desired release.

Sign Off step for Meteorological conditions are in the body of the procedure. Part of the

3)

Atmospheric inversions

(a)

The use of vertical temperature gradients is a practical and universally accepted method

of determining atmospheric stability. An inversion is defined as: air at ground level colder than

air aloft. Simply stated, unusually stable atmospheric conditions exist when an inversion exists,

meaning that vertical air movement is stifled. Clear, calm nighttime conditions are usually very

stable because the earth's surface cools rapidly, thus cooling the ground surface air. This is

usually the time of day that an inversion will exist. The absence of winds prevents this cool air

from "mixing" with the warmer air above. It is under these unfavorable, stable atmospheric

conditions that the release of radioactive gases would not be desired.

2.

and therefore release as little activity as practicable.

3.

determine:

a)

Types of activity

b)

4.

a)

b)

5.

Procedure

procedure if more detail is desired.

We should hold tanks as long as possible to allow maximum radioactive decay (ALARA)

Prior to release, the operator submits a sample request and RP samples the tank to

Quantities of each isotope present

RP also calculates and notes on sample request

Setpoints for RIA-37 & 38

Maximum allowable release flow rates

Steps described are a general description of actual procedure steps. Refer to

Wednesday, May 07,2003 01:39:26 PM

a2

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D C A C A D D C A D

Scramble Range: A - D

Tier:

2

Group:

2

Keyword

WGDT

Cog level:

M 2.613.0

Source:

NEW

Exam:

OC03301

Test:

R

AuthorlReviewer: LSMIRFA

WednBsday, May 07,2003 01:3926 PM

83

70. 075K1.01 001/2/2/CWS/SWS/M 2.5/2.5/M/OC03301/R/LSM/RFA

Which one of the following is correct concerning the Siphon Seal Water supply?

"A" and "B" SSW Headers are normally in service with LPSW aligned to both headers and with

HPSW:

A. throttled in the " A

header and in recirc in the "B" header

6." throttled in the " A Header and isolated in the " B Header.

C. isolated in the "A

Header and throttled in the " B Header

D. throttled in both the "A" and " B Headers.

Bank 2003 question 777

B

A Incorrect - HPSW is throttled in the "A" Header and isolated in the "B" Header

B Correct

C Incorrect - HPSW is throttled in the "A" Header and isolated in the "B" Header.

D Incorrect - HPSW is throttled in the "A" Header are isolated in the "B" Header.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B C D B D D B B D B

Scramble Range: A - D

Tier:

2

Source:

M

Test:

R

Keyword

cws/sws

Group:

2

Cog level:

M 2.512.5

Exam:

OC03301

AuthodReviewer: LSM/RFA

Wednesday, May 07,2003 01:39:26 PM

84

7 1 . 076A2.0 1 00 1/2/1 ISW SIM 3.5/3.7/NEW/OC0330 1 ISILSMIRFA

A valve in the SSW A header has failed closed and the header is inoperable. The SSW B

header remains operable. The A LPSW pump is in off. The B LPSW Pump is in run. Which

one of the following describes what must be done to ensure that the ESV meets TS 3.7.8

(ECCW) requirements?

A,' The required LPSW pumps for the B SSW header must be operable and the LPSW Pump

that must be placed in Auto Start on the Unit supplying the B SSW header must be

operable.

B. The required LPSW pumps for the B SSW header must be operable, the LPSW Pump

must be left running on the Unit supplying the B SSW header, and the A LPSW pump must

be placed in Pull-to-lock.

C. The B SSW header flow must be maintained so that changes in SSW header flow caused

by startinglstopping ESV pumps are < 50 gpm.

D. The required LPSW pumps for the B SSW header must be operable, the LPSW Pump

must be running on the Unit supplying the B SSW header, and the B SSW header flow

must be maintained so that changes in SSW header flow caused by startinglstopping ESV

pumps are < 50 gpm.

Wednftsday, May 07,2003 01 :39:26

PM

85

A Correct

B Must be in Auto Start

C. For Entry into SLC 16.9.12

D. Combination of B and C

Duke Power Company Procedure No.

Oconee Nuclear Station OP/ O/A/l104/052

Describe the proper procedure for operation of the Siphon Seal Water (SSW) System.

2. Limits and Precautions

2.1 One SSW header is required to be operable for ESV to meet TS 3.7.8 (ECCW)

requirements. For the required SSW header to be operable, the required LPSW pumps to

that header must be operable (Ref SLC 16.9.12), AND LPSW Pump Auto Start on the

Unit supplying the operating SSW header must be operable (Ref TS 3.3.28).

2.2 Normal SSW lineup should be as follows:

A SSW Header in service with LPSW (SSW-1) valved in; HPSW-901 throttled to

maintain balanced flow between A and B SSW Headers to within 20 gpm.. {I}

B SSW Header in service with LPSW (SSW-2) valved in, HPSW-900 closed.

A and B SSW Headers supplying all CCW and ESV pumps.

Maintain > 50 gpm in a single SSW Header, to allow surveillance of SSW

strainer .P. {I}

2.3 Entry into SLC 16.9.12 is NOT required IF SSW header flow < 50 gpm due to changes

in SSW header flow caused by startinglstopping ESV pumps, large changes in HPSW

pressure, etc Enclosure "Balancing Flow Between SSW Headers" can be performed as

needed.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A A C A C D C D A B

Scramble Range: A - D

Tier:

2

Group:

1

Keyword

sws

Cog level:

M 3.513.7

Source:

NEW

Exam:

OC03301

Test:

S

AuthorIReviewer: LSMIRFA

WedMsday, May 07,2003 01:39:26 PM

86

72. 078K 1.04 00 1/2/1/IA/M3. I13.41M 2003/0CO3301 /R/LSM/RFA

INITIAL CONDITIONS:

Maintenance has just been completed and the Instrument Air Compressors are aligned as

follows for post maintenance testing:

Primary IA compressor: Running

Backup IA compressors " A and " B in Standby 1

Backup IA compressor " C in Standby 2

Auxiliary IA compressor: Auto

IA-2718 (Air Supply to Radwaste Facility) Open

Radwaste Air pressure 78 psig (and stable)

CURRENT CONDITIONS:

~

A large leak in the cooling water system has caused the air compressors to overheat

IA pressure has decreased to 88 psig.

and the IA System pressure is falling.

Which one of the following is the expected response of the IA system?

All Standby:

A. 2 IA compressor(s) start only

B. 1 IA compressor(s) start only.

C.'

1 AND 2 IA compressors start; Auxiliary IA Compressor starts.

D. 1 AND 2 IA compressors start; IA-2718 (Air Supply to Radwaste Facility) CLOSES.

Modified question 593. Different answer

C

A.

pressure reaches 90 psig, the stem identifies pressure at 91 psig.

B.

psig.

C.

do not start until AIA receiver pressure reaches 88 psig. Changed stem to 88 psig-

D.

INCORRECT- See 'B' above, IA-2718 (Air Supply to Radwaste Facility) closes at IA pressure

below 85 psig.

INCORRECT - The 'B B/U instrument air compressor in STBY #2 will not start until IA

INCORRECT - ONLY the 'A' and 'c'

BIU IA compressors will start and they started at 93

Correct - Same as 'A' above for B/U instrument air compressors. The AIA compressors

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C B A D A C B A A B

Scramble Range: A - D

Tier:

2

Group:

1

Keyword:

IA

Cog level:

M3.113.4

Source:

M 2003

Exam:

OC03301

Test:

R

AuthodReviewer: LSM/RFA

73. 078K3.02 001/2/1/IA/M 3.1/3.4/NEWlOC03301/FULSM/RFA

A complete Loss of Instrument Air will result in which one of the following?

RCS Normal Makeup

A.' is lost, increases.

B. increases, increases.

C. is lost, is lost.

D. increases, is lost.

and RCP seal injection

OP-OC-SPS-SY-HPI,

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A B C B A D D A D A

Scramble Range: A - D

Tier:

2

Group:

1

Keyword

IA

Cog level:

M 3.113.4

Source:

NEW

Exam:

OC03301

Test:

R

AuthorlReviewer: LSMIRFA

WeWsday, May 07,2003

01:39:26 PM

88

74.

079A2.0 I 00 II2I2ISTATION AIRiM 2.9I3.2lNEWiOC03 30 1 /R/LSM/RFA

The station air system pressure is decreasing rapidly and the cross connection with the ISA

system has failed to open. The loss of SAS procedure directs you to use which one of the

following as a source of air during this emergency situations?

A.' A diesel-driven air compressor that can be aligned to the Station Air header and manually

started to help supply total IA requirements.

B. A motor driven air compressor that is aligned to the Station Air header and is automatically

started to help supply total IA requirements.

C. A diesel-driven air compressor that can be aligned to the Breathing Air header and

manually started to help supply total IA requirements.

D. A motor driven air compressor that is aligned to the Breathing Air header and is

automatically started to help supply total IA requirements.

Wednesday, May 07,2003 01:39:26 PM

89

1.

INTRODUCTION

1.1

the Instrument Air and Service Air Systems. The major components in the systems,

components operated by compressed air and the effects on plant operations if these

components lose IA are discussed.

1.2

(Obj. R1)The purpose of the Instrument Air System is to supply a reliable source of clean, dry,

oil-free compressed air, at the proper pressure, to the numerous valves, controllers, and

instruments throughout the plant that operate on compressed air. The IA System is the normal

supply for instrument air to the Radwaste Facility.

1.3

plant, are designed to operate by means of compressed air. Controllers translate demand

signals to the devices by throttling the amount of compressed air reaching them. The amount of

throttling is determined by the operator at the control station, which can then be set to

automatically maintain the required supply. Some instruments operate on an air signal,

proportional to the value of the parameter being measured. Numerous valves throughout the

plant are positioned by either admitting compressed air to an operating cylinder, or by bleeding

air from the cylinder. 1.4

The Primary IA compressor normally maintains IA header pressure. The Backup IA

compressors normally serves as a backup to the Primary IA compressor.

1.5

A third set of Service Air compressors supply air for equipment such as air drills, paint

sprayers, air hoses and the sewage ejectors. Operating pressure is approximately that of the

Instrument Air System. There are two rotary screwtype Sullair compressors. It normally only

takes one compressor to meet the needs of the Service Air System. If required, these

compressors supply another backup source to supply Instrument Air loads.

A fourth source of air during emergency situations is from a diesel-driven air compressor that

can be aligned to the Station Air header and manually started to help supply total IA

requirements.

This lesson plan discusses the normal and abnormal operation of the plant in relation to

Numerous controllers and instruments in the control room, and valves throughout the

The IA System supplies the air pressure to operate these devices.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A C B A B A A D B A

Scramble Range: A - D

Tier:

2

Group:

2

Keyword

STATION AIR

Cog level:

M 2.9/3.2

Source:

NEW

Exam:

OC03301

Test:

R

AuthodReviewer: LSM/RFA

WednBsday, May 07,2003 01:39:26 PM

90

75. 086 AK4.03 003/2/2/FIRE/M 3.1/3.7/NEW/OC03301/R/LSM/RFA

You are the OATC on unit 2. The Unit 2 control room (Keowee Statalarm Panel Trouble) has

just actuated. You determine that the fire is in zone 3. Which one of the following is the fire

location?

A,' Generator #I.

B. CT-5.

C. CT-4.

D. Operating Floor or Equipment Gallery.

2.5

A.

The system consists of a common Fire Indicating Unit that receives inputs from four Zone

Indicating Units. Ionization type smoke detectors provide inputs to the Zone Indicating Units.

The four fire detection zones are:

1,

2.

3.

Generator #I.

4.

Generator #2.

B.

Indicating Unit which, in turn, transmits a signal to the Fire Indicating Unit.

1.

and statalarms in the Keowee control room and Unit 2 control room (Keowee Statalarm Panel

Trouble) will actuate.

2.

The alarm can be silenced and the statalarms acknowledged, but any subsequent "triggering"

of a detector will reflash the alarm and statalarms.

(Obj R11) Keowee Hydro Station Fire Detection System

Operating Floor and Equipment Gallery.

Battery Room, Control Room, and Computer Room.

Upon detection of smoke, the detector energizes a relay in the associated Zone

A common alarm lamp and the associated zone lamp will light on the Fire Indicating Unit

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A A B A B D C A C B

Scramble Range: A - D

Tier:

2

Group:

2

Keyword

FIRE

Cog level:

M 3.113.7

Source:

NEW

Exam:

OC03301

Test:

R

AuthodReviewer: LSM/RFA

Wednesday, May 07,2003 01:39:27 PM

91

76. BWIAOI AAI .2 00111/2/RUNBACWM 3.213.5lM 2003/0C03301/PJLSM/RFA

Unit 1 is at 82 % power in power ascension. "IAI" RCP has just tripped.

Which one of the following describe the automatic responses?

A. Tave input to ICs from Loop " A is selected and Tcold is near zero.

BY An ICs runback to 74% at 25% per minute will occur and final FDW flow will be equivalent

to 100% power in the "B" Loop.

C. A runback to 74% CTP, demanded at 25% per minute occurs with the affected loop SG

being on low level limits.

D. An initial 2:l FDW ratio followed by a reactor trip due to RPS occurs followed by variable

low pressure bistables tripping.

B

A. Incorrect: Loop "B" Tave will be selected

B. Correct: 74% is load limit. No RPS trip due to initial power level at 85%. Re-ratio will require

-5.5 mpph in "B' header which equals the 100% value for that header.

C. Incorrect: FDW flow in " A header will be -2.5 mpph ... well above that for 25"SU level and

LLL.

D. Incorrect: Ratio will be 1:2, RPS trip will not be generated.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B D B C A D C B B D

Scramble Range: A - D

Tier:

1

Group:

2

Keyword:

RUNBACK

Cog level:

M 3.213.5

Source:

M 2003

Exam:

OC03301

Test:

R

AuthorIReviewer: LSMIRFA

Wednesday, May 07,2003 01 :39:27

PM

92

77. BWIA04 AA2.1 00111/2iTURBINE TRIPICIA 3.113.7BANK 2003/OC03301/R/LSMlRFA

-

Unit 3 plant conditions:

A Reactor trip occurred.

The OATC is performing IMAs and has depressed the TURBINE TRIP pushbutton.

The Main Steam Stop Valve positions indicate "OPEN."

The Generator Output breakers (PCB-58 & 59) indicate "CLOSED."

Which one of the following is the next IMA step required by the OATC?

A. Open BOTH generator output breakers.

B. Place the operating EHC pump to the OFF position.

c.* Place the EHC pumps control switches to the PULL-TO-LOCK position.

D. Send an operator to PULL the local turbine trip lever at the front standard.

Answer 159

A. Incorrect - PCBs are not opened during the performance of IMAs.

B. Incorrect - This would only start the automatic pump and the MSSVs would remain open.

C. Correct - This action secures both EHC pumps and allows the MSSV to close

D. Incorrect - This would be a method to locally trip the turbine if C did not work but, is operator

knowledge and not part of IMA's.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C A A C A A D D B A

Scramble Range: A - D

Tier:

1

Group:

2

Keyword:

TURBINE TRIP

Cog level:

CIA 3.713.7

Source:

BANK 2003

Exam:

OC03301

Test:

R

AuthorlReviewer: LSMIRFA

Wedwsday. May 07,2003 01:39:27 PM

93

78. BWIAO5 AK2.1 0011112/EDG/M 3.014.0lNEWlOC0330IR'LSMlRFA

A thunderstorm was in the area, and there were instabilities in the grid. The OATC has been

instructed to start the SSF Diesel Generator. The Diesel has been emergency started and the

output breaker is OPEN.

The OATC has been instructed to parallel the diesel to the grid. Which one of the following

describes the paralleling of the SSF Diesel Generator?

The DG should:

A. not be paralleled because it is in speed droop mode.

B.' not be paralleled because it is in isochronous mode.

C. be paralleled because it is in speed droop mode.

D. be paralleled because it is in isochronous mode

Oconee Lesson Plan OP-OC-EAP-SSF

I

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B C C A C A A D C A

Scramble Range: A - D

Tier:

1

Group:

2

Keyword:

EDG

Cog level:

M 3.0/4.0

Source:

NEW

Exam:

OC03301

Test:

R

AuthorlReviewer: LSMIRFA

Wednesday, May 07,2003 01 :39:27

PM

94

79. BW/E02EK2.2 001/1/l/VITAL SYSTEM VERFICIA 4.214.21M 2003/OC03301/R/LSM/RFA

A reactor trip has occured with the following parameters observed:

" A SG SU Level = 15" and decreasing

"A" SG Startup Control valve = 100% demand

" A SG Startup FDW flow = "0" gpm

"B" SG SU Level = 2 5 and stable

"B" SG Startup Control valve =15% demand with green and red light

RB pressure = 0.23 psig and steady

Which one of the following is the correct diagnosis of what is occurring?

A,' The " A SG is experiencing inadequate heat transfer due to insufficient level.

B. The "B" SG level is inaccurate due to degraded reactor building.

C. The "B" SG S/U FDW valve is not opening properly.

D. The " A SG is indicating a SG tube leak

Bank 184

A.

B.

C.

Correct - B SG is performing as required (now an inadequate heat transfer)

Incorrect - RB pressure is < 3 psig so SG level is accurate

Incorrect - A SG CV operating properly as level is ablove LLL.

D. Incorrect - conditions indicate a no FDW

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A C B A B B B B A D

Scramble Range: A - D

Tier:

1

Group:

1

Keyword:

VITAL SYSTEM VERF

Cog level:

CIA 4.214.2

Source:

M 2003

Exam:

OC03301

Test:

R

AuthodReviewer: LSMlRFA

Wednesday, May 07,2003 01:39:27 PM

95

80. BWlE04EK2.2 00111lllINADEQUATE HEAT TRANICIA 4.214.2lNEWIOC03301IWLSMIRFA

Unit 3 has implemented the inadequate heat transfer procedure due to a complete loss of

feedwater.

The crew has just completed Steps 9 and 10 which opened the RCS High Point Vents.

RCS pressure will be governed by which one of the following?

A. a combination of HPI pump discharge pressure, the high point vent flow capacity and the

decay heat level.

B. a combination of HPI pump discharge pressure, the PORV relief flow capacity, the high

point vent flow capacity and the decay heat level.

C.'

a combination of HPI pump discharge pressure, the PORV relief flow capacity and the

decay heat level.

D. HPI pump discharge pressure only.

Inadequate Heat transfer Lesson plan page 15

Steps 9 and 10 opens the RCS High Point Vents which will result in lower RCS pressure, which

will allow greater injection flow and therefore better core cooling.

RCS pressure will be governed by a combination of HPI pump discharge pressure, the PORV

relief flow capacity and the decay heat level.

RFA removed " which will result in lower RCS pressure, which will allow greater injection flow

and therefore beffer core cooling" from the stem because it teaches.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C D D B A C D B D C

Scramble Range: A - D

Tier:

1

Group:

1

INADEQUATE HEAT TRAN

Cog level:

CIA 4.214.2

Keyword

Source:

NEW

Exam:

OC03301

Test:

R

AuthodReviewer:

LSMIRFA

Wednesday, May 07,2003 01:39:27 PM

96

81. BWlE04EK3.3 00111lliHEAT TRANSFEWCIA 4.2/3.8/NEWIOC03301IWLSMIRFA

The "Loss of Heat Transfer" Tab has been implemented when Unit 1 suffered a loss of Main

and Emergency Feedwater.

FDW is not yet restored, but RCS conditions do not yet require HPI cooling.

Which one of the following describe the preferred configuration of the RCPs?

A,' One RCP per loop

B. Any One RCP

C. 1Al RCP and any other RCP

D. All RCPs running

THEN GO TO Step 4.

RNO:

1.

FDW is not yet restored, but RCS conditions do not yet require HPI cooling. Two RCPs are left

running to reduce total heat input to the RCS. The preferred configuration is one RCP per loop

so that forced flow exists in both SGs when feedwater is restored. Since it is not known in

which SG(s) feedwater will be restored, or if it will be restored, one RCP should be left running

in each loop if possible. The selection of RCPs to run should consider pressurizer spray flow

capacity.

Further Explanation of C - while 1Al RCP provides the best PZR spray, the preferred

configuration is one pump per loop

(Obj. R2) Reduce operating RCPs to one pumplloop.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A B D A A C B C D A

Scramble Range: A - D

Tier:

1

Group:

1

Keyword:

HEAT TRANSFER

Cog level:

CIA 4.2/3.8

Source:

NEW

Exam:

OC03301

Test:

R

AuthorlReviewer: LSMIRFA

WedWsday. May 07,2003 01:39:27 PM

97

82. BWlE08 GEN 2.4.1 8 0011112lCOOLDOWNlC/A 2.7l36./NEW/OC03301/R/LSMlRFA

You are the OATC on unit 3. The crew is in the LOCA CD procedure with EFDW being

supplied from unit 2. A single EFDW control valve has failed open. The crew enters

EP/3/A/1/1800/001 Enclosure 5.27. Which one of the following will you acomplish using this

procedure?

A? Isolate the EFDWP supply from unit 2.

B. Swap the EFDWP supply from unit 2 to unit 1.

C. Take manual control of the failed unit 2 EFDW control valve.

D. Regulate EFDWP flow with the unit 2 control valve that has not failed.

EP/3/A/1/1800/001 Enclosure 5.27.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A D C B C D A A C D

Scramble Range: A - D

Tier:

1

Group:

2

Keyword:

COOLDOWN

Cog level:

CIA 2.7136.

Source:

NEW

Exam:

OC03301

Test:

R

AuthorlReviewer: LSMIRFA

Wedngsday, May 07,2003 01:39:27

PM

98

83. BW/E13 EA2.1 001/112/EOP RULES/M 3.4/4.0/BANK 2003/OCO33Ol/S/LSM/RFA

I

Unit 1 plant conditions:

An MS Line Break has occurred

Manual control of HPI is desired

Which one of the following is the minimum requirement to take manual control of HPI and

throttle flows under the above plant conditions?

The BOP can take manual control of HPI:

A. if the severity of the transient will be increased based on their judgment.

B. if the safety system is not required to perform its intended safety function.

C. as directed by EOP Section 5.0.

D.' as directed by Rule 6.

A)

SRO.

B)

SRO.

C)

manual control of ES components.

Correct- procedural guidance is contained in Rule 6 for taking manual control of ES and

throttling HPI.

Incorrect- Non-procedural bypassing requires two licensed operators, one of which is an

Incorrect. Non-procedural bypassing requires two licensed operators, one of which is a

Incorrect- EOP Section 5.0 (Subsequent Actions) does not contain directions on taking

D)

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D C B A B A B C C C

Scramble Range: A - D

Tier:

1

Group:

2

Keyword

EOP RULES

Cog level:

M 3.4/4.0

Source:

BANK 2003

Exam:

OC03301

Test:

S

AuthodReviewer: LSMiRFA

Wednesday, May 07,2003 01:39:27 PM

99

84. GEN 2.1.1 1 00113NTECH SPECiM 3.013.8IBANK 1990/07/06/0CO330I/S/LSM/RFA

I

The power-imbalance limits defined in Tech Spec 3.5.2," Control Rod Group and Power

Distribution Limits ", are based upon which one of the following?

A. Assures that an acceptable power distribution is maintained for control rod mislignment

analysis.

6. Assures that the potential effects of control rod misalignment on steam line break accident

analyses are minimized.

c.' Assures LOCA analysis limits on maximum linear heat rate for maximum cladding

temperature are not exceeded.

D. Assures that the nuclear uncertainty factor in LOCA analyses will not exceed the Final

Acceptance Criteria.

REFERENCE

Oconee Tech Specs bases 3.5.2.6 2.613.8

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C D A A C A A B C A

Tier:

3

Group:

Keyword

TECH SPEC

Cog level:

M 3.0/3.8

Source:

BANK 1990/07/06

Exam:

oco3301

Test:

S

AuthoriReviewer: LSMIRFA

Scramble Range: A - D

Wednesday, May 07,2003 01:39:27 PM

100

85. GEN 2.1.14 001/3//ADM1N/M 2.513.3IMlOC03301ISILSMIRFA

You are the assigned Control Room SRO. You have just been notified that a draining

evolution in the East Penetration Room has just been completed. Before the RO supervising

the drain down leaves the area, you inform him that OMP 1-2, requires an additional

notification that the task is complete? Which one of the following do you instruct the RO to

notify?

A. RP only.

B.'

Chemistry only.

C. Operations Shift Manager only.

D. RP, Chemistry and Operations Shift Manager.

Based on - ADM040306

A.

SRO be informed when the draining evolution is stopped or concluded and NOT RP.

B. Correct: OMP 1-2, 5.9.1(1) requires that chemistry and the assigned Control Room SRO be

informed when the draining evolution is stopped or concluded.

C. OMP 1-2, 5.9.1 (I) required that chemistry and the assigned Control Room SRO be informed

when the draining evolution is stopped or concluded and NOT the Operations Shift Manger.

D. Incorrect: OMP 1-2, 5.9.1 (I) required that chemistry and the assigned Control Room SRO be

informed when the draining evolution is stopped or concluded

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B A A C C A B C C D

Tier:

3

Group:

Keyword:

ADMlN

Cog level:

M 2.513.3

Source:

M

Exam:

OC03301

Test:

S

AuthorlReviewer: LSMIRFA

Incorrect: OMP 1-2, 5.9.1 (I) required that chemistry and the assigned Control Room

Scramble Range: A - D

Wednesday, May 07,2003 01:39:27 PM

101

86. GEN 2.1.27 00113llSYSTEM PURPOSEIM 2.812.9lNEWIOC03301IRILSMIRFA

Which one of the following describes the operation of the AMSAC (ATWS Mitigation Safety

Actuation Circuit) and the DSS (Diverse Scram System) during an ATWS with a complete loss

of Main Feedwater?

AMSAC:

A. trips the main turbine while DSS trips the regulating rods and starts the EFDWPs.

B. trips the regulating rods while DSS trips the main turbine and starts EFDWPs.

C! trips the main turbine and starts EFDWPs while DSS trips the regulating rods.

D. starts EFDWPs while DSS trips the regulating rods and trips the main turbine.

Oconee Lesson Plan OP-OC-CF-EF, Obj. R24

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C D C B B C B D C C

Tier:

3

Group:

Keyword

SYSTEM PURPOSE

Cog level:

M 2.812.9

Source:

NEW

Exam:

OC03301

Test:

R

AuthorIReviewer: LSMIRFA

Scramble Range: A - D

Wedeesday, May 07,2003 01:39:27 PM

102

87. GEN 2.1.32 00113l/LlMITS & PRECAUTIONS/C/A 3.413.8iBANK 2003/0C03301IRILSM/RFA

INITIAL CONDITIONS

TIME = 0900

The Reactor tripped on Loss of Main FDWPs

The EFDW system is operating

CURRENT CONDITIONS

TIME = 1000

The EFDW system is operating

Which ONE of the following describes the MAXIMUM UST temperature per OP/IINl 102101,

Controlling Procedure for Unit Startup to ensure the EFDW system adequately removes core

decay heat?

A. a 5 0 ~

B:' 125" F

C. 145°F

D. 150" F

Bank 2003 question 94

A.

B.

states that UST temperature is limited to 125°F two hours following a reactor trip.

C.

conditions.

D.

Incorrect - This is the EFDW system piping design temperature.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B D D A D C D C A A

Tier:

3

Group:

Keyword

LIMITS & PRECAUTIONS

Cog level:

C/A 3.413.8

Source:

BANK 2003

Exam:

OC03301

Test:

R

Author/Reviewer: LSMlRFA

Incorrect - This is the minimum temperature limit for feeding the SG's

Correct - OP/1/AJ1102/01, Controlling Procedure for Unit Startup, Limit and Precautions

Incorrect - This is the limit for power operations up to 30% power and for shutdown

Scramble Range: A - D

Wednesday, May 07,2003 01:39:28 PM

103

88. GEN 2.1.6 001/3//ADMlN/M 2.114.3lBANK 1994/03/07/0C03301ISILSMIRFA

Which one of the following is the Control Room SRO authorized to do without being relieved?

A. Provide relief for the Control Room operators.

B. Prepare Removal and Restorations (R&Rs).

C.' Designate another SRO as reader of the EOP.

D. Prepare procedure changes.

BANK 1994/03/07

REFERENCE

OMP 2-1 Rev 10/15/93, End. 4.5

EAP-Ell, Obj. R7

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C D A B C B C D B B

Tier:

3

Group:

Keyword

ADMlN

Cog level:

M 2.114.3

Source:

BANK 1994103107

Exam:

OC03301

Test:

S

AuthorIReviewer: LSMIRFA

Scramble Range: A - D

Wednesday, May 07,2003 01:39:28 PM

1 04

89. GEN 2.2.12 00113//SURVEILLANCE/C/A 3.013.4lBANK 2003lOC03301lFULSMIRFA

An NE0 performing surveillances on the ESVISSW systems observes the following indications

Both SSW Headers are in service

"A" SSW Hdr gpm = 85

" B SSW Hdr gpm = 65

" A SSW Hdr Strainer DP = 10.5

" 6 SSW Hdr Strainer DP = 5.5

Which ONE of the following is the correct action in response to these indications?

[Assume normal ESVISSW system operation and valve alignment]

A,' Declare the " A SSW Header inoperable.

B. Swap and clean the " A

and "B" SSW Header Strainers.

c. Declare both SSW Headers and both associated ECCW Siphon Hdrs inoperable

D. Increase the "B" SSW Hdr flow rate and reduce the " A

SSW Hdr flow rate until strainer P

is within operability limit.

Question 778 STG220301

Reference: OPIOIAII 104I052

A. Correct. With both SSW Headers in service, L&P 2.6.2 states that if strainer dp of 10 psid is

received, then declare the SSW Hdr inoperable. The curve is used when only one SSW Hdr is

in service.

8. Incorrect The "A" SSW Hdr should be declared inoperable due to the strainer dp. The "B"

SSW Hdr strainer is not rquired to be cleaned until 6 psid and the operability limit is 10 psid.

C.lncorrect, The " A SSW Hdr is ioperable only based on L&P 2.6.2

D. Incorrect, The operability limit of 10 psid has been exceeded in only the " A Hdr.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A C A C D D B B B C

Tier:

3

Group:

Keyword

SURVEILLANCE

Cog level:

CIA 3.013.4

Source:

BANK 2003

Exam:

OC03301

Test:

R

Author/Reviewer: LSM/RFA

Scramble Range: A - D

Wednesday, May 07,2003 01:39:28 PM

105

go. GEN 2.2.17 001/3//DEFINITIONS/M

2.3/3.5/NEW/OC03301/S/LSM/RFA

You are the Shift Supervisor. Mechanical maintenance is planning to work on the HPI system.

You get a report from engineering that during maintenance the system will be FUNCTIONAL.

Which one of the following describes if you should allow the maintenance to take place with the

unit at 100% power?

The work can:

A:' occur because the HPI system can perform its intended service; however, applicable TS

requirements or licensing/design basis assumptions may NOT be maintained.

B. NOT occur because the HPI system cannot perform its specified function even with all

applicable TS or SLC requirements satisfied.

C. NOT occur because the A Module of ORAM-SENTINEL has assigned a color of WHITE to

the HPI system.

D. occur because the A Module of ORAM-SENTINEL has assigned a color of GREEN to the

HPI system.

A correct

B. Definition of Operable

C and D. PRA information related to risk, not system operability of function

Reference

ADMMRr03

ENABLING OBJECTIVES: 1.

Define and relate the following terms and their application to the assessment of equipment

removed from service. (R2)

a.

Functional

b.

Maintenance

c.

Operable

d.

Probability Risk Assessment (PRA)

e.

Risk

f.

Risk Significant System (RSS)

The following are some of the definitions adopted by the industry and Duke Power Company for

consistent interpretation of the Maintenance Rule. These definitions are from the regulation

lOCFR50.65, NUMARC 93-01, or were specifically developed for Duke Power.

MCS Time: 1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A A B C A D A C B D

Scramble Range: A - D

Wednesday, May 07,2003 01 :39:28

PM

106

Tier:

3

Keyword

DEFINITIONS

Source:

NEW

Test:

S

Group:

Cog level:

M 2.313.5

Exam:

OC03301

AuthoriReviewer: LSMRFA

WednWay, May 07,2003 01 :39:28 PM

107

91. GEN 2.2.2 00113l/CONTROLS/M 4.013.5lBANK 199l/Ol/24/0CO330I/R/LSM/RFA

Which one of the following determines when the Megawatt Calibrating Integral will be

controlled by turbine header pressure error?

A. The bypass valves controls are in manual

B. The diamond control is in manual.

C. The SGlRX control is in manual.

D.* Turbine Bailey is in hand while all other stations are in auto.

REFERENCE

LP Vol. 11, ICs, OP-OC-STG-ICS p.59

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D 3 D A A C C A D C

Tier:

3

Group:

Keyword:

CONTROLS

Cog level:

M 4.013.5

Source:

BANK 1991101124

Exam:

OC03301

Test:

R

AuthoriReviewer:

LSMIRFA

Scramble Range: A - D

Wednesday, May 07,2003 0.1:39:28 PM

108

92. GEN 2.3.2 00113llALARA/ClA 2.5/2.9/M/OC03301/R/LSM/RFA

A point radiation source in the auxiliary building reads 500 mRem/hr at a distance of two feet.

Two options exist to complete a mandatory assignment near this point source.

OPTION 1.

Operator X can perform the task in 30 minutes while working at a distance of

FOUR (4) feet from the point source.

Operators X and Y, using an extension tool, can perform the task in 75 minutes

at a distance of EIGHT (8) feet from the point source.

OPTION 2.

Operator X has a quarterly dose of 902 mRem

Operator Y has a quarterly dose of 11 15 mRem

Which one of the following choices is the preferred option, if any, to complete the assignment

in accordance with ALARA? (Assume no dose extensions have been authorized)

A.* Option 1

B. Option 2

C. Option 1 and 2 are equally acceptable.

D. Neither Option 1 nor 2 can be used.

Solution - A - Option 1 62.5 mRem

REFERENCE

Oconee: ALARA Manual, General Employee Training Handbook

194001 K104 (3.3/3.5)

Modified - Original Question:

QNUM

29735

HNUM

30083 (Do NOT change If

9,000,000)

ANUM

29745

QCHANGED FALSE

ACHANGED FALSE

QDATE

1991/07/24

FAC

269

Oconee 1,2 & 3

RTYP

PWR-B&W177

EXLEVEL

R

EXMNR

QVAL

SEC

SUBSORT

KA

194001 K104

QUESTION

A point radiation source in the auxiliary building reads 500

mRem/hr at a distance of TWO (2) feet. TWO (2) options exist to

WednBsday, May 07,2003 01:39:28 PM

109

complete a mandatory assignment near this point source.

OPTION 1.

Operator X can perform the task in 30 minutes while

working at a distance of FOUR (4)

feet from the

point source.

OPTION 2.

Operators X and Y, using an extension tool, can

perform the task in 75 minutes at a distance of

EIGHT (8) feet from the point source.

WHICH ONE (1)

of the following choices is the preferred option,

with correct rationale, to complete the assignment, in accordance

with ALARA?

a. Option 1, as X's exposure is 62.5 mRem.

b. Option 1, as X s exposure is 125 mRem.

c. Option 2, as the exposure per person is 39 mRem.

d. Option 2, as the exposure per person is 156 mRem.

ANSWER

a. [+1.0]

REFERENCE

Oconee: ALARA Manual, General Employee Training Handbook

194001K104 (3.3/3.5)

Wednesday, May 07,2003 01:39:28 PM

MCS

Time:

I

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

110

93. GEN 2.3.3 00113llRAD RELEASEICIA 1.812.9lBANK 1995107107/OC03301lSILSM/RFA

Which one of the following describes the most favorable meteorological conditions for making

a Gaseous Waste Release?

wind speed with air at ground level

than air aloft.

A. LOW I COLDER

B. LOW I WARMER

C. HIGH I COLDER

D. HIGH I WARMER

REFERENCE

OP-OC-WE-GWD, Revision 05, page 22

(252.8) #49

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D B A B D D B D A A

Tier:

3

Group:

Keyword

RAD RELEASE

Cog level:

CIA I.8/2.9

Source:

BANK 1995107107

Exam:

OC03301

Test:

S

AuthorIReviewer: LSMIRFA

Scramble Range: A - D

Wednesday, May 07,2003 01:39:28 PM

111

94. GEN 2.4.12 00113llADMINIM 3.413.9lBANK 2003/OC03301/R/LSMiRFA

Unit 1 plant conditions:

1.

2.

3.

4.

Which one of the following statements is correct concerning this condition?

A. ES will NOT actuate if power is lost to two out of three ES analog channels.

B. Channels 1-6 RZ module Blue and White lights should be "ON" and verified "ON" by the

operator performing Enclosure 5.1, ES Actuation.

A Reactor trip occurred on low RCS pressure

RCS pressure = 1200 psig

RB pressure = 2.0 psig

The BOP is performing Rule #2, Loss of SCM

C. Enclosure 5.1, ES Actuation, shall be performed by the BOP after Rule #2 is completed,

while the OATC performs EOP LOSCM tab actions.

D? Enclosure 5.1, ES Actuation, shall be performed by the OATC after IMAs are verified,

symptoms check is completed, and while the BOP performs Rule #2.

A.

Incorrect - analogs will trip on a loss of power.

B.

Incorrect - at this time only ES 1 and 2 have or should have actuated.

C.

Incorrect - end. 5.1 should be performed as soon as possible. It has higher

priority than LOSCM tab actions and should be performed as soon as an operator is

available.

D.

Correct: BOP performs Rule #2. When IMAs and symptom check completed by the

OATC, a Parallel Action of LOSCM is to perform Encl. 5.1. OATC will have to perform

this with the BOP running rule #2.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D B A B C D A C D A

Tier:

3

Group:

Keyword

ADMIN

Cog level:

M 3.413.9

Source:

BANK 2003

Exam:

OC03301

Test:

R

AuthoriReviewer: LSMlRFA

Scramble Range: A - D

Wednpsday, May 07,2003 01:39:28 PM

112

95. GEN 2.4.23 001/3//CRITICAL SAFETY/M 2.813.8iBANK 1991/01/2410C03301/RILSM/RFA

Which one of the following represents the correct order of priority (from highest to lowest

priority) for the following critical safety functions?

A. Inadequate Core Cooling, Subcriticality, RCS Integrity, Heat Sink.

B. Inadequate Core Cooling, Subcriticality, Heat Sink, RCS Integrity.

c. Subcriticality, Inadequate Core Cooling, RCS Integrity, Heat Sink.

D.' Subcriticality, Inadequate Core Cooling, Heat Sink, RCS Integrity.

GEN 2.4.23

REF ERE N C E

LP Vol V.. SPDS. OP-OC-SPS-IC-SPDS, p.9,LPROILPSO 2a

MCS

Time:

1 . Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: D C B A D B A A A C

Tier:

3

Group:

Keyword

CRITICAL SAFETY

Cog level:

M 23/33

Source:

BANK 1991/01/24

Exam:

OC03301

Test:

R

AuthodReviewer: LSMIRFA

Scramble Range: A - D

Wednesday, May 07,2003 01:39:28 PM

113

96. GEN 2.4.25 001/3/IFlRE/C/A 2.913.4lBANK 2003/0C03301lRlLSWRFA

Which one of the following areas does the HPSW system provided sprinkler fire protection for?

A. Reactor Building.

B.# 230 KV switchyard.

C. Keowee Hydro Units.

0. CCW Intake Structure.

Question 587 SSSO30301 SSSO30301

Which one of the following areas is provided sprinkler fire protection via the HPSW system?

Answer 587

B

A. Incorrect. supplied from LPSW

B. Correct. supplied from Yard header (Major Fire Loop load).

C. Incorrect. has own water supply system

D. incorrect. no sprinkler system supplied for intake structure

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: B C C D A C C D B A

Tier:

3

Group:

Keyword

FIRE

Cog level:

CIA 2.913.4

Source:

BANK 2003

Exam:

OC03301

Test:

R

AuthoriReviewer: LSMIRFA

Scramble Range: A - D

Wednbsday, May 07,2003 01 :39:28 PM

114

97. GEN 2.4.3 00113llPOST ACCIDENT INSIM 3.513.81MIOC03301IRILSMIRFA

The Reactor Building Hydrogen Analyzer system Gaseous Post Accident Sample Panel is in

operation. You are the OATC and notice that some of the RZ module white and blue lights

have illuminated. You determine that Channel 1 has inadvertently been activated.

Which one of the following, states the required immediate actions?

A. MANUALLY close the reactor building isolation valves for the Hydrogen Analyzer system,

then return the Gaseous Post Accident Sample Panel to service.

B. Verify the Gaseous Post Accident Sample Panel remains in service, then verify the reactor

building Hydrogen Analyzer system isolation valves AUTOMATICALLY open.

Cy MANUALLY close the reactor building isolation valves for the Gaseous Post Accident

Sample Panel, then place the reactor building Hydrogen Analyzer system in service.

D. Verify the reactor building isolation valves for the Gaseous Post Accident Sample Panel

AUTOMATICALLY close, then place the reactor building Hydrogen Analyzer system in

service.

Original Question - Question 562 PNS582 PNS582 SRO ONLY (Modified to be RO)

The Limits and Precautions of OP/1,2,3/A/I102/22, Reactor Building Hydrogen Analyzer

system, directs immediate operator actions if the Gaseous Post Accident Sample Panel is in

operation when an ES actuation occurs.

Which ONE of the following lists the required immediate actions? (.25)

A)

system, then return the Gaseous Post Accident Sample Panel to service.

B)

reactor building Hydrogen Analyzer system isolation valves AUTOMATICALLY open.

C)

Sample Panel, then place the reactor building Hydrogen Analyzer system in service.

D)

Verify the reactor building isolation valves for the Gaseous Post Accident Sample Panel

AUTOMATICALLY close, then place the reactor building Hydrogen Analyzer system in service.

Answer 562

C

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C A D C C A A C B A

Tier:

3

Group:

Keyword:

POST ACCIDENT INS

Cog level:

M 3.513.8

Source:

M

Exam:

OC03301

Test:

R

AuthorIReviewer: LSMIRFA

MANUALLY close the reactor building isolation valves for the Hydrogen Analyzer

Verify the Gaseous Post Accident Sample Panel remains in service, then verify the

MANUALLY close the reactor building isolation valves for the Gaseous Post Accident

Scramble Range: A - D

Wednesday, May 07, 2003 0.1:39:28 PM

.. .

. .

. ..

. .

.

.~ ..

.

115

98. GEN 2.4.41 002/3//ADMlN/C/A 2.314.lIBANK 2003/0C03301/S/LSM/RFA

Unit 2 sequence of events:

Time=l200

Unit 2 is shutting down with a 30 gpm tube leak in the 2B SG

An Unusual Event (NOUE) has been declared

Time=1230

While taking the Turbine Generator off-line a Turbine Trip occurs.

Time=l255

One Main Steam Relief valve on the 28 SG will NOT reseat

Time=l300

2B SG has been isolated

The blowing Main Steam Relief valve on 28 SG Main Steam Relief did NOT reseat

when the SG was isolated

PRESENT TIME=1305

Assume NO additional failures occur and that "Emergency Coordinator Judgment/ EOF Directoi

Judgment" is NOT used as a reason for the classification.

Which one of the following correctly classifies the event?

A? Remain as an NOUE

6. Upgrade to an Alert

C. Upgrade to a Site Area Emergency

D. Upgrade to a General Emergency

Wednesday, May 07,2003 01:39:29 PM

116

Answer 223

REFERENCE ATTACHMENT REQUIRED

A.

point earned from the other two barriers.

B.

point earned from the other two barriers. No EAL above a NOUE have been met.

C.

point earned from the other two barriers. No EAL above a NOUE have been met.

Correct: Enclosure 4.1 Fission Barrier Matrix Containment Barriers gives 3 points. No

Incorrect: Enclosure 4.1 Fission Barrier Matrix Containment Barriers gives 3 points. No

D.

Incorrect: Enclosure 4.1 Fission Barrier Matrix Containment Barriers gives 3 points. No point

earned from the other two barriers. No EAL above a NOUE have been met.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A C C B A C A B D B

Tier:

3

Group:

Keyword

ADMIN

Cog level:

C/A 2.3/4.1

Source:

BANK 2003

Exam:

OC03301

Test:

S

AuthorIReviewer: LSMIRFA

Scramble Range: A - D

Wednesday. May 07,2003 01:3929 PM

117

99. GEN 2.4.6 001/3l/PRA/M 3.114.OMEWlOC03301ISILSMIRFA

Which one of the following does the Oconee PRA analysis NOT identify as an

Important Human Action associated with a turbine building flood?

A. Swap HPI Suction to Spent Fuel Pool.

B. Refill the Elevated Water Storage Tank.

C." Connect HPI pump power to ASW switchgear.

D. Activate the SSF.

Wednesday, May07,2003 01:39:29 PM

118

Important Human Actions

The following are some important human actions from the Oconee PRA. More detailed

information can be found in the Oconee PRA Report Rev. 2, Chapter 3.

Event or Sequence

Loss of all AC Power, TB Flood

LOCA

Turbine Building Flood

Loss of 416OvAC during a tornado

Operator Action

Activate the SSF

Establish recirc. from containment

sump

Refill the Elevated Water Storage Tank

Connect HPI pump power to ASW

Large LOCA

Small or Medium LOCA

TB Flood, Tornado (w/ BWST Failure)

Loss of All LPSW

Activate the SSF -Activation of the SSF is important for many types of events,

including: Seismic, Flood, and Station Blackouts (including Tornado and TB Fire).

Establish Recirculation From the Sump - Swap to sump recirculation and

establishing high pressure recirculation are important to prevent ECCS failure following

a LOCA.

Refilling the Elevated Water Storage Tank - Refilling the EWST is important

following a Turbine Building flood by providing backup cooling for the HPI pumps.

HPI to ASW Switchgear -Tornado damage to the 4160 V switchgear in the Turbine

Building can be mitigated by connecting an HPI pump to the ASW switchgear.

Throttling the LPI Pumps - Throttling the LPI pumps is an important human action to

prevent pump failure from operating in run-out conditions following a large LOCA.

Stopping the LPI Pumps - Stopping the LPI pumps for small and medium LOCA

sequences prevents pump damage from dead-heading against the high RCS

pressure.

Swap HPI Suction To The SFP - Depletion of the BWST inventory during a TB Flood

can be mitigated by realigning the HPI suction to the SFP. This can also be used in

Tornado Sequences which damage the BWST.

Cross-Connect LPSW To Another Unit - LPSW flow from another unit can be used to

cool important loads including such as the HPI motor coolers and the CC Coolers.

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: C D B A A C B A A B

Scramble Range: A - D

switchgear

Throttle LPI Pumps

Stop the LPI Pumps (Pumping Against

Shutoff Head)

Swap HPI Suction to Spent Fuel Pool

Cross-connect LPSW Header to other

Wednesday, May 07,2003 01:39:29 PM

119

Tier:

3

Keyword

PRA

Source:

NEW

Test:

S

Group:

Cog level:

M 3.1/4.0

Exam:

OC03301

AuthorlReviewer: LSMIRFA

Wednesday, May 07,2003 01:39:29 PM

120

100. GEN 2.4.7 001/3//ADMIN/M 3.113.8iBANK 2003/0C03301/RILSM/RFA

Unit 2 plant conditions:

INITIAL CONDITIONS:

2A1 is secured

CURRENT CONDITIONS:

AP129 is in progress

Reactor power = 43% and is decreasing

The BOP is swapping Auxiliaries:

When he attempted to close 2TA SU 6.9 FDR, a 2TA switchgear lockout occured.

Which one of the following describes your actions as the Procedure Director?

A,' GO TO the EOP and stop APE9 directions.

B. Refer to the EOP and continue with APE9 in parallel.

C. Suspend AP129 directions until 2TA switchgear can be returned to service.

D. Continue APB9 until the GO TO OP/1102/10, Controlling Procedure for Unit Shutdown is

reached.

bank 250

A. Correct - When 2TA swgr lockout occurs the reactor will trip on flux1flow (loss of 2 RCPs)

this meet entry conditions to the EOP. APE9 should be stopped as the first note say AP129

should not be used when EOP entry conditions exist. This note is conflicting later in AP129

when tripping the reacfor per APE9 then the EOP is not entered.

6. Incorrect - APE9 is stopped when EOP entry conditions are met.

C. Incorrect - EOP entry condition - reactor trip - have been met.

D. Incorrect - EOP entry conditions have been met

MCS

Time:

1

Points:

1.00

Version: 0 1 2 3 4 5 6 7 8 9

Answer: A B D D B C B B B A

Tier:

3

Group:

Keyword:

ADMIN

Cog level:

M 3.U3.8

Source:

BANK 2003

Exam:

OC03301

Test:

R

AuthodReviewer: LSMlRFA

Scramble Range: A - D

WednEsday, May 07,2003 01:39:29 PM

121

ML032471483

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