ML032480798

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June 50-269/2003-301 Final Outlines
ML032480798
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 08/11/2003
From: Ernstes M
Operator Licensing and Human Performance Branch
To: Rosalyn Jones
Duke Energy Corp
Shared Package
ML032521014 List:
References
50-269/03-301, 50-270/03-301, 50-287/03-301, ES-301, ES-301-1, NUREG-1021, Rev 9 50-269/03-301, 50-270/03-301, 50-287/03-301
Download: ML032480798 (17)


See also: IR 05000269/2003301

Text

Final Submittal

OCONEE JUNE 2003 EXAM

50-26912003-301

JUNE 16 - 27,2003

FINAL SAMPLE PLANS / OUTLINES

ii

\\

i/

ES-301

Administrative ToDics Outline

Form ES-301-1

inial Submittal

Facility: Oconee

Examination Level (circle one): RO / SRO

Date of Examination: June 16,2003

Operating Test Number: 1

Administrative Topic

Conduct of Operations

GEN 2.1.23 (3.9/4.0)

Conduct of Operations

GEN 2.1.7 (3.7/4.4)

Equipment Control

GEN 2.2.12 (3.0/3.4)

Radiation Control

GEN 2.3.4 (2513.1)

Describe activity to be performed

CRO-203, Calculate Final SFP Boron Concentration

0P/l&2/Nl104/006 C (SFP Makeup), Enclosure 4.9 (SFP

Makeup With DW) (group activity) (new) ( I O min)

CRO-043, Perform Manual RCS Leakage Calculation;

PT/0600/010 (RO Only) (group activity) (18 min)

CRO-204, Perform weekly surveillance test to

determine RIA40 setpoint

PT/230/001 Encl. 13.10 (Operation of RIA-40)

(new) (20 min)

CRO - 205, Calculate the Maximum Permissible Stay

Time Within Emergency Dose Limits (group activity)

(new) (20 min)

Note: All items (5 total) are required for SROs. RO applicants require only 4 items

unless they are retaking only the administrative topics, when 5 are required.

NUREG-1021. Draft Revision 9

i ,

-

ES-301

Administrative Topics Outline

Form ES-301-1

inial Submittal

Facility: Oconee

Examination Level (circle one): RO / SRO

I

Date of Examination: June 16,2003

Operating Test Number: 1

Administrative Topic

Conduct of Operations

GEN 2.1.23 (3.914.0)

Conduct of Operations

GEN 2.1.3 (3.013.4)

Equipment Control

GEN 2.2.12 (3.013.4)

Radiation Control

GEN 2.3.4 (233.1)

Emergency Plan

GEN 2.4.38 (2.214.0)

Describe activity to be performed

CRO-203, Calculate Final SFP Boron Concentration

OP/l&2/A/I 104/006 C (SFP Makeup), Enclosure 4.9 (SFP

Makeup With DW) (group activity) (new) (IO min)

JPM-003, Evaluate Overtime Eligibility

OMP 2-01 Attachment C, NSD 200 (SRO only)

(25 min)

CRO-204, Perform weekly surveillance test to

determine RIA40 setpoint

PT/230/001 Encl. 13.10 (Operation of RIA-40)

(new) (20 min)

CRO - 205, Calculate the Maximum Permissible Stay

Time Within Emergency Dose Limits (new)

(20 min)

SRO-206, Determine Emergency Classification and

Protective Action Recommendations (SRO only)

(group activity) (new)

(20 min)

Note: All items (5 total) are required for SROs. RO applicants require only 4 items

unless they are retaking only the administrative topics, when 5 are required.

NUREG-1021, Draft Revision 9

ES-301

System / JPM Title

a. CRO- 083, Re-establish RCS letdown flow

[KA: 004 A2.07 (3.4/3.7)]

Pressure S 550 psig EOP Encl. 5.1 (ES Actuation)

[KA: EPEOll EA1.13 (4.1/4.2)]

AP/32 (Loss of Letdown)

CRO- 066, Perform Required Actions for RCS

b.

Control Room/ln-Plant Outline

Form ES-301-2

Type

Safety

Code*

Function

M, A, S

2

3

D, A, s

~~

c. CRO-202, Reset RIA40 setpoints and enter the

OAC Pri to Sec Admin Limit

PT/230/001 End. 13.10 (Operation of RIA-40)

[KA: 073 A4.02 (3.7/3.7)] (new)

N, S

7

d. NLO-022, Station ASW Pump Alignment

EOP Encl. 5.10 [KA: APE054 AA1.01 (4.5/4.4)]

(last exam)

e. NLO-007, Start Diesel Air Compressor And Align

To Service Air Header

AP132, Encl. Emergency Start of the Diesel Air

Compressor, [KA: APE-065 AA1 .04 (3.5*/3.4*)]

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

D, R, L

4s

8

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path,

(C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

NUREG-1021, Draft Revision 9

ES-301

Control Room/ln-Plant Outline

Form ES-301-2

inial Submittal

Facility: Oconee

Date of Examination: 06/16-25/03

Exam Level (circle one): RO I SRO(I) I SRO(U) Operating Test No.: 1

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

N, S

System I JPM Title

7

a. CRO-200, Makeup to the LDST

OP/l103/004 (Soluble Poison Control)

[KA: 004A4.13 (3.3/2.9)] (new)

b. CRO- 083, Re-establish RCS letdown flow

AP132 (Loss of Letdown)

[KA: 004 A2.07 (3.4/3.7)]

c. CRO- 066, Perform Required Actions for RCS Pressure 5

550 psig EOP Encl. 5.1 (ES Actuation)

[KA: EPEOll EA1.13 (4.1/4.2)]

d. CRO-013, Align MDEFDWP Suction to the Hotwell and

Feed the SGs

EOP Encl. 5.9 [KA: APE054 AA1.01 (4.5/4.4)]

EOP, End. 5.6 [KA: 003 A4.06 (2.9*/2.9)] (new)

CRO-202, Reset RIA40 setpoints and enter the OAC Pri to

Sec Admin Limit

PT/230/001 End. 13.10 (Operation of RIA-40)

[KA: 073 A4.02 (3.7/3.7)] (new)

e. CRO-201, Restart RCP

f.

D

9. CRO-IIA, Align Intake Canal For Recirc On Dam Failure

AP/13 (Dam Failure), [KA: 075 A2.01 (3.0/3.2)]

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

h. NLO-022, Station ASW Pump Alignment

EOP End. 5.10 [KA: APE054 AA1.01 (4.5/4.4)]

(last exam)

CRO-47, Emergency start SSF Diesel Generator and

supply power to the SSF ASW and SSF RCMU pumps

AP/25, [KA: 062 A2.11 (3.7/4.1)]

NLO-007, Start Diesel Air Compressor And Align To

Senrice Air Header

AP/32, End. "Emergency Start of the Diesel Air Compressor",

i.

j.

[KA: APE-065 AA1.04 (3.5*/3.4*)]

8

Safety

Code*

Function

NS

D, L, S

N, S

4P

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path,

(C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

NUREG-I 021, Draft Revision 9

.S-301

Control Room/ln-Plant Outline

Form ES-301-2

inial Submittal

Facility: Oconee

Date of Examination: 06/16-25/03

Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: 1

Safety

Function

1

2

3

4s

4P

6

-

7

a 1

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title

i, NLO-022, Station ASW Pump Alignment

(last exam) (12 min)

CR047, Emergency start SSF Diesel Generator and

supply power to the SSF ASW and SSF RCMU pumps

AP/25, [KA: 062 A2.11 (3.7/4.1)] (IO min)

k. NLO-007, Start Diesel Air Compressor And Align To

EOP End. 5.10 [KA: APE054 AA1.01 (4.5/4.4)]

D, R, L

j.

M, A, L

Service Air Header

D

a. CRO-200, Makeup to the LDST

OP/l103/004 (Soluble Poison Control)

[KA: 004A4.13 (3.3/2.9)] (new) (15 min)

4s

6

a

b. CRO- 083, Re-establish RCS letdown flow

AP132 (Loss of Letdown)

[KA: 004 A2.07 (3.4/3.7)] ( I O min)

c. CRO- 066, Perform Required Actions for RCS Pressure S

550 psig EOP End. 5.1 (ES Actuation)

[KA: EPEOll EA1.13 (4.1/4.2)] (15 min)

d. CRO-013, Align MDEFDWP Suction to the Hotwell and

Feed the SGs

EOP End. 5.9 [KA: APE054 AA1.01 (4.5/4.4)] ( I O min)

EOP, Encl. 5.6 [KA: 003 A4.06 (2.9*/2.9)] (new) (20 min)

CRO-009, Following a Keowee Emergency Start Transfer

from CT-4 to CT-5

OP/O/N1106/019 End. 4.12

[KA: 062 A4.01 (3.3/3.1)] ( I O min)

g. CRO-202, Reset RIA40 setpoints and enter the OAC Pri to

Sec Admin Limit

PT/230/001 End. 13.10 (Operation of RIA-40)

[KA: 073 A4.02 (3.7/3.7)] (new) ( I O rnin)

h. CRO-IIA, Align Intake Canal For Recirc On Dam Failure

AP/13 (Dam Failure), [KA: 075 A2.01 (3.0/3.2)] (15 min)

e. CRO-201, Restart RCP

f.

n-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

Type Code"

N, S

.

.. ~... . ~~.

~ .~.~..~.

~

AP/32, End. "Emergency Start of the Diesel Air Compressor",

[KA: APE-065 AA1.04 (3.5*/3.4*)] (IO min)

I

'Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room,

S)imulator, (L)ow-Power, (R)CA

NUREG-1021, Draft Revision 9

ES-401

PWR Examination Outline

Form ES-401-2

Final Submittal

II

11 Note: 1

L

2.

3.

4.

5.

6.*

7.

h.

I.

inappropriate WA statements.

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.1.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 fl

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

Final

ES-401

PWR Ex:

Emergency and Abnormal Plan

I E/APE#/Name/SafetyFunction

K1

K2

K3

A I

A2

000007 TW/-EOZ&ElO; .CE/E02)

02

Reactor rip Stabilization

Recovery / 1

I

I

I

I

I

000008 Pressurizer Vapor Space

22

Accident / 3

I

I

I

I

I

01

i5

39

000009 Small Break LOCA / 3

00001 1 Large Break LOCA / 3

000015/17 RCP Malfunctions 14

10

000022 Loss of Rx Coolant

Makeup I 2

000025 Loss of RHR System I 4

000026 Loss of Component

Cooling Water / 8

I

I

I

I

I

000027 Pressurizer Pressure

Control System Malfunction/3

I I

I

I

I

000029 ATWS / 1

12

09

000038 Steam Gen Tube

19

Rupture/3

Steam Line Ru ture ~ Excessive

Heat TransferP4

Feedwater / 4

000055 Station Blackout / 6

000040 (BW/EO5; CE/EO5; W/E12)

01

000054 (CE/EO6) Loss of Main

03

i

00057 Loss of Vital AC Inst. Bus /

W/E04; W/E05 Inadequate Heat

r - Loss of Secondary Heat

WA Category Totals:

1 3 1 2 13/i 1 2 1614

iubmittal

[ination Outline

Form ES-401.:

.volutions - Tier I/Group 1 (ROISRO)

Ability to determine and interpret the loss

of cooling water as it applies to RCP

malfunctions

Loss of RC effects on PZR level

SRO ONLY Knowled e o f the reasons

for shift to alternate #ow path as it

applies to Loss of RHR

I

Definition of saturated as it applies to PZR

Actions contained in EOPs for ATWS

Reactor Trip/trubine trip as it applies to

I ATINS

MFW as it applies to SGTR

Selection of procedures associated with

Excessive heat transfer

KA moved from K2 because of importance

factors

SRO ONLY Existing valve position on

loss of instrument air associated with

Proper operation of EDG load sequencer

Manual control of components, ,

outsrde ihe CR

2.1.8

SRO.ONLY Coordinate Activities

SRO ONLY DC Loads lost

Flow rates to components furnished by

NCMI

+

4.214.7

2

3.313.4

i

4.314.7

i

4.213.9

4.414.7

1

4.414.5

1 I

3.413.4

1

3.014.2

1

3.814.2

1

3.M.7

1 I *

3.813.6

Heat removals stems associated with

inadequate heay transfer

I Manioulation of controls associated with

I inadequate heat transfer

I

212

I Group Point Total:

I 18/7

qF

4.213.8

1 Of 34

NUREG-1021, Draft Revision 9

PWR-Examination Outline

II ES-401

Emergency and Abnormal Plant Evolutions -Tier I /

Adherence to a propr,ale

3 713 7

procedures antoperational ,:m 1s I

ElAPE # / Name / Safety Function

K1

K2

K3

A I

A2

G

000001 Continuous Rod Withdrawal I 1

1

11

I

I

I

I I

I 2.4.'

000003 Dropped Control Rod / 1

Control and safety systems.

including instrumentation and

interlocks

000028 Pressurizer Level Malfunction / 2

4.013.8

1

000059 Accidental Liquid RadWaste Rel. I 9

01

000060 Accidental Gaseous Radwaste Rel. I 9

000061 ARM System Alarms / 7

01

000067 Plant Fire On-site /48

04

EOP Rules- facility conditions

and selection of appropnate

procedure

I I I

I

I

I

24.27

3.44.0

1

000068 (BW/AO6) Control Room Evac. / 8

000074 (W/E06&E07) Inad. Core Cooling / 4

000076 High Reactor Coolant Activity I 9

Group Point Total:

I I I

1 2 1 I

BW/AOI Plant Runback/ 1

915

BWIAO4 Turbine Trip / 4

BW/E08' WlE03 LOCA

BW/E13&E14 EOP Rules and Enclosures

WA Category Point Totals:

I

2

2

1

213

112

oup 2 (RO/SRO)

Form ES-401

WA Topic@)

IR

I

I

SRO ONLY EOP entry

PZR sensonldetectors

2.612.7

1

SRO ONLY PZR Level

3.4l3.6

1

Indications

I

I

Fuel handling incident

3.414.1

1

I

SRO ONLY Conditions

ARM detector limitations

Actions contained in EOPs for

lant fires

knowledge of fire in the plant

procedures

3JL7.5

0 erating behavior.characteristics

3.213.5

0 the facility associated with P

Runback

Knowledge of EOP Basis

I 2.713.6 I 1

'i/

NUREG-1021, Draft Revision 9

2 of 34

Form ES-401-:

ES-401

System # / Name

K1

K2

PWR-Examinatic

Systems -Tier ?.IC

Outline

'up l(ROlSR0)

-

-

IR

3.213.5

2.612.5

2.913.1

3.40.8

-

-

-

3.213.6

KIA Topi@)

RCP Shutdown effect on

Secondary Parameter

RCP Motor current

I

I

JReactor

Coolant Pump

004 Chemical and Volume

Control

MUP power supply

SRO ONLY - Knowledge

of abnormal condltlon

procedures

Refueling

005 Residual Heat Removal

006 Emergency Core Cooling

3.913.8

3.7/4.4

ECCS Flowpath

SRO ONLY - ECCS -

Abllify to evaluate plant

pWf0mta"Ce

wnneCtion to RCS

Loss of CCW to CRDsl

05s opf CNI pump

indications and controls

PZR Heaters

3.013.2 -

2.913.1

3.313.6

3.313.1

007 Pressurizer ReliefIQuench

03

Tank

I

I

008 Component Cooling Water

3.013.4 -

3.313.8

3.313.6

4.314.7

3.613.9 -

-

010 Pressurizer Pressure

01

Control

012 Reactor Protection

I

I

DNB

Bypass Block Circuits

Containment

EWST Level

^-? Containment Cooling

NIA

3.914.1

2.812.9

3.313.3

2.913.1

2.rn.8

-

-

-

2.712.9

026 Containment Spray

039 Main and Reheat Steam

CCS malfunction

System Puwse

ADV

Water Hammer

Predlct the Impact of the

loss of condpurnp

MFW Power Restrictions

056 Condensate

059 Main Feedwater

I

I

061 AuxiliarylEmergency

Feedwater

malhmction of EFW

controller

AFW start-up

2.512.8

1.214.2 -

2.512.7

E

2.612.8

2.813.1

062 AC Electrical Distribution

063 DC Electrical Distribution

Circuit Breakers

switching power supplies

System Loads

Major breakers and

control power fuses

Governor Valve operation

SRO ONLY Impact of the

loss Of sws

Containment air systems

Cocling waterto

wmpressor

2.513.0 -

3.si3.7

076 Service Water

3.113.4

2.612.9 -

-

078 Instrument Air

,Category Point

3

3

Ikdals:

5

2

Group Point Total:

3 of 34

NUREG-1021. Draft Revision 9

\\u,

NUREG-1021, Draft Revision 9

4 Of 34

Final Submittal

ES-401

Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3

I

2.

EsuiDment

Facility:

Oconee

z&q-iG

2.2.2

Ability to manipulate control consoles as required to operate between

4.0

1

shutdown and power operations. RO ONLY

I

2.1.6

2.1.27

Vuclear Station

Date of Exam:

06/27/03

Topic

Ability to supervise and assume management roles during plant

transients and upset conditions. SRO ONLY

Knowledge of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS action statements. SRO ONLY

Knowledge of system status criteria requiring notification of plant

personnel. SRO ONLY

Knowledge of system purpose or function. RO ONLY

Ability to explain and apply all system limitations and precautions. RO I

2.3.3 t

2.3.2

Knowledge of SRO responsibilities for auxiliary systems outside the

Knowledge of facility AIARA program. RO ONLY

2.5

1

2.9

1

control room. SRO ONLY

Procedures I

I

T l G l

I 000028K1.01

I KA not applicable to ONS. New KA = 000028K2.02

I

I

Reason for Rejection

T I G2

T l G l

000033A2.11

00001 1 K1.01

KA not applicable to ONS (ONS no longer has IR Detectors).

New KA = 000036AA2.02

LBLOCA redefined at ONS (A 200

SBLOCA. New KA to fit Q is OOOOO%A2.39

m leak will not saturate the plant). Q fits

T2G1

T2G2

5 of 34

000022A1.04

000079A2.01

KA not applicable to ONS. New KA = 000008K3.02

KA not applicable to ONS. IA does not backup SA. New KA = 000014A1.02

NUREG-1021, Draft Revision 9

T2G2

000034G2.1.27

ONS fuel handling s stem ur ose is to limited to write a good discriminatory Q.

I Changed KA. New

= 060834G2.2.27

Appendix D

Scenario Outline

Form ES-D-1

Event

No.

Oa

Ob

Oc

1

2

Facility: Oconee

Scenario No.: 1

Op-Test No.: 1 (Final Submittal)

Examiners:

Operators:

Malfunction

Event Type*

Event

No.

Description

TD EFDW Pump Fails to Start

Pre-Insert

MSS330

Pre-Insert

SASS in manual

Updater

Pre-Insert

AMSACIDSS bypassed

Updater

MP1121. 100

I. BOP. SRO

N, BOP, SRO

De-Lithiation with the Normal deborating Demin.

PZR LVL #I

Transmitter Fails HIGH

4

5

6

7

8

I

~~~~

~

~~

~~~~~~

~

I

.

~,

3

I MCR021

I C, OATC, SRO 1 Drop CR Group 2 Rod 6, (TS)

MPS440 (40-

C, BOP, SRO

80%)

MP1281

1, OATC, SRO

AT,fails HIGH when RCP secured

MCR022

MELO90

M, ALL

ATWS

MELl8O

M, ALL

Keowee Unit 1 Emergency Lockout (blackout,

IA, RCP High Vibration (secure RCP)

C, OATC, SRO

Second dropped control rod, requiring a manual

reactor trip

CT-1 Lockout (Loss of Power)

p w

I Override

I

I Diamond blocked from AUTO operation

u

NUREG-1021, Draft Revision 9

Page 1 of 14

Appendix D

Scenario Outline

Form ES-D-1

Facility: Oconee

Scenario No.: 2

Op-Test No.: 1 (Final Submittal)

Examiners:

Operators:

Initial Conditions:

100% Reactor Power (IC-41)

Turnover:

AMSAC/DSS bypassed for I&E testing

SASS in manual for I&E testing

A Condensate Booster Pump OOS, breaker to be replaced

Keowee Unit 2 00s for unplanned reasons

Keowee Unit 1 aligned to underground

Event

Malfunction

Event Type*

Event

No.

No.

Description

Oa

Pre-Insert

AMSAC/DSS bypassed

Ob

Pre-Insert

NI-9 00s

MN1082

Oc

Pre-Insert

A AFlS circuit disabled

AOR

B AFlS circuit disabled

MEL180

Od

Pre-Insert

Keowee Unit 2 Emergency Lockout

Oe

Pre-Insert

l a

Override

N, BOP, SRO

Low A CFT Pressure (N2 makeup)

I b

Override

C, BOP, SRO

IN-298 (N2 Fill CFT IA) fails OPEN

ES Channels 7 and 8 fail to automatically actuate

2

MPSO9O

C, OATC, SRO

IHP-120 (RC Volume Control) Fails closed

3

MCSOO4

I, OATC, SRO

Controlling Tave fails HIGH

4

Override

Seismic event (PRA)

C, BOP, SRO

1A RBCU rupture (TS)

5

I MPS020

I C,ALL

I 1 B SG Tube leak 5 gpm (TS)

6

I MPS020

I C A L L

I 1B SG Tube leak increases to ruoture of 100 aom

I

I

I

I.

7

I R, OATC, SRO I Unit Shutdown

8

I MSS360.50 I M.ALL

I 1A Main Steam line break in RB

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent,

(M)ajor

i/

NUREG-1021, Draft Revision 9

Page 1 of 11

Auuendix D

Scenario Outline

Form ES-D-1

Facility: Oconee

Scenario No.: 3

Op-Test No.: 1 (Final Submittal)

zxaminers:

Operators:

-

Initial Conditions:

25% Reactor Power (IC-45), startup in progress

Turnover:

Unit 1 TD EFDW Pump 00s to repair oil leak

NI-9 OOS, to be replaced next outage

Keowee Unit 2 00s for unplanned reasons

Keowee Unit 1 aligned to underground

Operability test of Keowee Unit 1 is to be performed per PT/620/009 (Keowee Hydro

Operation) after turnover and before startup continues. ONS to perform remote

Keowee start.

Event

Malf. No.

Event Type*

Event

No.

Description

Oa

Pre-Insert

TD EFDW Pump Fails to Start

MSS330

Ob

Pre-Insert

SASS in manual

Oc

Pre-Insert

AMSAC DSS bypassed

Od

Pre-Insert

Keowee Unit 2 Emergency Lockout

1

MEL020

N, BOP, SRO

Operability test Unit 1

Updater

Updater

MEL180

Override

c,

SRo

Keowee Unit 1 Gen Field Flashing Breaker fails

to OPEN automatically

pump fails to start (TS)

2

MPS460

C, OATC, SRO

A

HPI Pump sheared shaft and standby HPI

3

MN1032

I, OATC, SRO

Controlling NI fails LOW

4

MSS310

C, BOP, SRO

Loss of Instrument Air

5

MP1290

Main FDW Pump Trips

C, OATC, SRO

6

MSS280,lOO

M, ALL

A TBVs fail open

7

MPSOIO

M, ALL

A SG Tube Rupture

Override

Main Turbine Fails to trip (Lockout EHC Pumps)

1MS-17 (A TBV Block) fails to close

Override

(N)ormal,

(R)eactivity,

(I)nstrument,

(C)omponent,

(M)ajor

NUREG-1021, Draft Revision 9

Page 1 of 11

d

c

~

6

Appendix D

Scenario Outline

Form ES-D-1

MCR040

C, OATC, SRO

R. O A K . SRO

Facility: Oconee

Scenario No.: SPARE

Op-Test No.: 1 (Final Submittal)

Examiners:

Operators:

Initial Conditions:

50% Reactor Power, shutdown in progress (IC-44)

Turnover:

AMSAClDSS bvpassed for I&E testing

NI-9 OOS,

to bereplaced next outage

Event

Pre-Insert

MN1082

oc

I Pre-Insert

OCI

I Pre-insert

I

_ _

. .-

~.

I

1

1 MP1171, 100 I I , OATC. SRO

MP1500, 100

MPS290

C, BOP, SRO

+-I---

Override

3

I MPS110

! C. BOP. SRO

4

I MPS405

1 C. BOP. SRO

7 I MPS400.5

! M.ALL

~

I

(N)ormal,

(R)eactivity,

(I)nstrument,

1

Event

Description

AMSAC/DSS bypassed

NI-9 00s

IHP-26 Failed CLOSED

E W - 3 1 6 Failed OPEN

Th Fails HIGH (repair return to auto)

1A CC Pump trips (1B CC Pump fails to auto

start)

1 HP-5 Fails closed

Unidentified RCS leak in RB (20 gpm) (TS)

Inability for CRD insertion in automatic during

shutdown.

Manual CRD power decrease

SBLOCA

)omponent,

(M)ajor

NUREG-1021, Draft Revision 9

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