Text

June 2004 Exam 50-269/2004-301 Final Sample Plans/Outlines
	ML042190120
Person / Time
Site:	Oconee
Issue date:	08/17/2004
From:	Ernstes M; Operator Licensing and Human Performance Branch
To:	Bradley Jones; Duke Energy Corp
References
	50-269/04-301, 50-270/04-301, 50-287/04-301
	Download: ML042190120 (43)
	v • d • e

Final Submittal

OCONEE JUNE 2004 EXAM

50-269/2004-301,

50-27012004-301 I &

50-28712004-301

JUNE 14 - 18 & 25,2004

~.

_

~

ES-301

Administrative Topics Outline

Form E§-301-1

Final Submittal

-

Facility: Qconee

Examination Level (circle one): RO / SRO

Date of Examination: June, 2004

Operating Test Number:

Conduct of Operations

GEN 2.1 2 3 (3.W4.0)

Conduct of Operations

GEN 2.1.7 (3.U4.4)

Equipment Control

GEN 2.2.12 (3.0/3.4)

Radiation Control

GEN 2.3.4 (233.1)

GEN 2.4.39 (3.3/3.1)

Describe activity to be performed

Adrnin-100, Determine SDM with a Dropped Control

Rod

PT/1/A/1103/15, Reactivity Balance (1 0 min)

Adrnin-103, Perform Manual RCS Leakage Calculation;

PT/0600/010 (RO Only)

(last exam) (group activity) (18 min)

___

~

-~

~~

Adrnin-202, Perform Surveillance to Verify SSF RCMUP

Qperability

PT/600/001 Enci. 13.1 (Mode I & 2) (new) (15 min)

Adrnin-402, Perfom Actions for Medical Emergency

RP/l000/016, Encl. 4.1 (Medical Response)

(RO Only) (15 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

E§-304

Control Roomlln-Plant Outline

Form E§-301-2

System / JPM Title

I Typecode*

a. CR0-012A, Recover a dropped rod

AP/1/A/1700/15, OP/O/Nl 105/09, Enci 4.10

[KA: 005 AA2.03 (3.5/4.4)1 (20 min)

D, S, A

b. CRO- 067, Perform Required Actions for ES ACtUatiQn (> 3psig)

EOP Enclosure 5.1 (ES Actuation)

[KA: EPE-009 EA1.13 (4.4/4.4)] (6 min)

D, A, S

c. CRQ-97, Transfer ECCS Suction to the Emergency Sump (ILP-15

Failed Closed)

EOP Enclosure 5.27. Alternate Methods for Controlling EFDW Flow

IAPE-054 AA2.04 (4.2/4.311 (20 min)

CRO-700, Place ICS In Auto following LOSS Of Auto Power

AP123 (Loss Of ICs Power) Enclosure 5 5 (Placing ICs In Auto)

IKA: BWIAO2 AA1 .I (4.013.8)l (new) (20 min)

N. A. S

f.

CRO-060, Perform Required Actions For Turbine Building Flood

[KA: APE BW/A07 AA1.3 (3.3135)) (7 min)

APllO (Turbine Building Flood)

D. s

g. CRO-900, Release GWD Tank

OP/1&2/N1104/018 Encl. 4.9 (GWD Tank Release)

InPlant Systems (3 for RO;

3 for SRO-I; 3 or 2 for SRO-U)

Safety

Function

1

3

4P

4s

7

8

i.

NLQ-039, Prime The Spent Fuel Pool Fill Line

EOP End. 5.7, #PI Pump Operations From ASW Pump Switchgear

[KA: APE022 AK3.02 (3.5/3.8)] (16 min)

EOP Encl. 5.14 IKA: EFT074 AB1.01 (3.6/3.9)1 (7 min)

NLO-036, Startup A Vital Bus Inverter

OP/l107/004 Enclosure 4.2 [KA: 062 A3 04 (2.7/2.9)1 (3 min))

NUREG-2021, Draft Revision 9

E§-301

Control Roorn/ln-Plant Outline

Form E§-301-2

Facility: Oconee

Bate of Examination: June, 2004

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

Control Room Svstems (8 for RO: 7 for SRO-I: 2 or 3 for SRO-U)

System i

JPM Title

a. CRO-012A, Recover a dropped rod

APIliAf1700115, OP/O/N11O5/09. Encl 4.10

[KA: 005 AA2.03 (3.514.4)] (20 min)

b. CRO- 067, Perform Required Actions for ES Actuation (> 3psig)

EOP Enclosure 5.1 (ES Actuation)

IKA: EPE-009 EA1.13 64.4/4.4)1 (6 min)

c. CRO-97, Transfer ECCS Suction to the Emergency Sump (ZLP45

Failed Closed)

EOP. Enclosure 5.12 [KA:BWIE08 EAl.1 (4.0/3.7)] (PRA) (9 min)

d. CRO-015, Establish EFDW Flow Through Startup Valves

EOP Enclosure 5.27, Alternate Methods for Controiiing EFDW Flow

[APE-054 AA2.04 (4.2/4.3)] (20 min)

e. CRO-700, Place ICs In Auto following Loss Of Auto Power

AP123 (Loss Of ICs Power) Enclosure 5.5 (Placing IC§ In Auto)

[KA: BWIA02 AAI .I (4.0i3.8)l (new) 15 min)

CRO-060, Perform Required Actions For Turbine Building Flood

APilO (Turbine Building Flood)

rm: AFT BWiAQ7 AAI .3 (3.3/3.5)1 (7 min)

f.

g. CRO-900, Release GWD Tank

OPil&2/A/11C41018 Encl. 4.9 (GWD Tank Release)

[KA: 071 A4.26 (3.1i3.9) (new) (15 rnin)

In-Plant Svstems (3 for RO: 3 for SRO-I: 3 or 2 for SRO-U)

Type Code*

D, S, A

D, A, S

Safety

Function

1

3

4P

4s

7

8

9

i.

NLO-039, Prime The Spent Fuel Pool Fill Line

EOQ Encl. 5.7, HPI Pump Operations from ASW Pump Switchgear

[KA: APE022 AK3.02 (3.5i3.8)I (16 min)

j.

CRO-053, Bypass Coolant Pump Starting lnterlocks

EOP Encl. 5.14 [#a: EPE074 AA1.01 (3.6/3.9)1 (7 min)

D, L, R

2

k. NLO-036, Startup A Vital Bus Inverter

OPil107iOO4 Enclosure 4.2 [KA: 062 A3.04 (2.7/2.9)] (9 min))

B

6

Type Codes: (D)irsct from bank, (M)odified from bank, (N)ew, (8)lternate path, (C)sntrol room,

(S)imulator. (L)ow-Power, (W)CA

NUREG-1021, Draft Revision 9

ES-302

Control Roorn/ln-Plant Outline

Form ES-301-2

Bate of Examination: June, 2004

b. CRO- 067, Perform Required Actions for ES Actuation &= 3psig)

EOP Enclosure 5.1 (ES

Actuation)

[KA: EQE-009 EA1.13 (4.4/4.4)] (6 min)

d. CRO-025, Establish EFDW Flow Through Startup Valves

EOP Enclosure 5.27, Alternate Msthods for Controlling EFDW Flow

[APE-054 AA2.04 (4.2/4.3)] (6 min)

I

' e.

CRO-750, Place ICs In Auto following Loss Of Auto Power

AP/23 (Loss Of ICs Power) Enclosure 5.5 (Placing ICs In Auto)

[KA: BW/A02 AA1.1 (4.0/3.8)] (new) 20 min)

i. NLO-539, Prime The Spent Fuel Pool Fill Line

EBP Encl. 5.7, HPI Pump Operations from ASW Pump Switchgear

IKA: APE022 AK3.02 13.5/3.8)1 (16 min)

B, L, R

2

k. NLO-036, Startup A Vital Bus Inverter

OP/l107/004 Enclosure 4.2 [KA: 062,4304 (2.7/2.3)] (9 min))

I D

Type Codes: (DJirect from bank. (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room,

(S)irnulator, &)ow-Power, (R)CA

NUREG-1021, Draft Revision 9

ES-401

PWR Examination Outline

Form ES-401-2

Facility 0

Date of Exam

I

II

Vote: 1.

2.

3.

4.

5.

6.*

7.

8.

9.

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

the 80 outline (i.e., the "Tier Totals" in each WA category shall not be less than two).

Refer to Section B.l .c for additional guidance regarding SRO sampling.

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

in the table. The final point total for each group and tier may deviate by a1 from that

specified in the table based on NWC revisions. The final RO exam must total 75 points

and the SRQ-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 priurities.

Systemslevolutiofls within each group are identified on the associated outline.

The shaded areas are not applicable to the category/tier.

The generic (e) 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 SKO-level learning objective.

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

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

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

table above; summarize all the SRO-only knowledge and non-A2 ability categories in

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

Fur 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 inappropriate

.....

....

......

...

.-.

.-

.....

...

KIA statements.

-.

.....

....

..

iS.401

P W R Examinilori OLrlfre

Form FS-401.2

,...-

......... -

......

F m r m @ m

' & E E ! A = - ? : . : . T t - r

1'Guu-u- !.W3... .....

....-

.......

-.

...

....

NUREG-1021, Drafl Revision 9

24 of 34

Tier 1 Group 1

, . . . . . . . . . . ._

. . . . . . . . . . . . . . . . ...

Loss of Nuclear Svc

Wale1 I 4

Stabilization -

4

I I

.

45.13)

December 17,2003

- ~

Name I Safety Function

Continuous Rod Withdr

Dropped Control Rod /

inoperablelStuck Conk

' Steam Generator Tube

PLANT EVOLUTION):(CFR: 41.10 143.5 I

associated

g as they apply to ABNORMAL

EVOLUTIQN):(CFR: 41.10 143.5 I

PLANT EVOLUTION):(CFR: 41.10 143.5 /

___~

~

~ ~.

Decemt

_ _ ~ ~

~

Accidental Gaseous Ri

1

Plant Fire On-site I 8

Control Room tvac. 1 E

Loss of CTMT Integrity

Inad. Core Cooling I 4

High Resctor Coolant I

i ,

associated,

I

/

i

Tier 1 Group 2

g as they apply to A

EVOLUTBON):(CFR.

following as they apply to (EMERGENCY

PLANT EVOLUTION):(CFR: 41 . I O i

43.5 /

I l l

45.13)

PLANT EVOLUTION):(CFR: 41.10 143.51

I l l

45.13)

I

December 17.2003

Pier 1 Group 2

I mitigation strategies.

associated.

and abnormal operating procedures.

associated.

require the notification of plant personnel.

~

~~

December 17,2003

m e I Safety Functio

F

Auxilialy/trnergency

Feedwater

!

lT--m--

rocass a iation

Monitoring

Nice Water

I=-----

' containment

I

548

Tier 2 Group 1

procedures to correct. control. or

mitigate the consequences of those

abnormal operation:(CFR: 41.5 I43.5 /

associated

Pier 2 Group 1

hemicai and

Jolume Control

Residual Heat

Removal

krnergency Core

Cooling

Pressurizer

Relief/Quench Tank

Component Cooling

Water

Pressurizer

Pressure Control

Reactor Protection

.-

ation:(CFR: 41.5 143.5 /

procedures to correct, control, or

mitigate the consequences Of those

abnormal operation:(CFR: 41.5 143.5 /

.

,

Tier 2 Group 1

Cooling

I k

Steam

L- -

based i n those predictions. use

procedures to correct, control, or

mitigate the consequences of those

abnormal operatin:(CFR: 41.5 / 43.5 /

45.3 145.13)

based on those predictions, use

procedures to correct, control, of

mitigate the consequences of those

abnormal operatim:(CFR: 41.5 143.5 I

45.3 / 45.13)

d A Randomly Rejected

folbwing on the (SYSTEM) an

based on those predictions, use

procedures to correct, control, or

mitigate the conquenms of those

abnormal operation:(CFR: 41.5 I43.5 I

.

.-

-

p5GG2.22

Q6A2.08

339A2.04

056A2.04

~. !&cemi

1 tmergency Diesel

I Generator

3

a

3

Tier 2 Group 1

..

~

.~

~~ ....

. .-

KA

1 RO

.

~~~~~.~

1

Question Type

KIA Topic(6)

I Drocedures to correct, control. or

I

the consequences of those

operation:(CFR: 44.5 / 43.5 /

45.3 145.13)

I

procedures to correct, control. or

mitigate the consequences of those

abnormal operation:(CfR: 41.5 I43.5 /

December 17,2003

Pier 2 Group 2

Name / Sate Functl

r-

1 Reactor Coolant

b

ressurizer eve

Control

' Nuclear

i Instrumentation

Ih]an-nuclear

,Instrumentation

7-

Question Type

0 Ability to (a) predict the impacts of the

following on the (SYSTEM) and (b)

based on those predictions, use

procedures to correct, control, or

mitigate the consequences of those

abnormal operation:(CFR: 41.5 I43.5 /

procedures to correct. control, or

mitigate the amsequences of those

mitigate the consequences of those

abnormal operation:(CFR: 42.5 / 43.5 /

abnormal operation:(CFR: 41.5 / 43.5 I I

December 17, 2003

ame I Safety Functi6

Cn-core

Temperature

Monitor

' Contalnment lodine

, Removal

iydrogen

qecombiner and

'urge Control

ontainmant Purge

ipent Fuel Pool

ooiing

uel Handling

iquipment

Tier 2 Group 2

I

&&tiOll

Type

wa ~~

P 0

~

~ -

...

.

0 I Ability to (a) predict the impacts of the

I WA Randomlv Reiected

. .

following ofl the (SYSBEMj and (b)

based on those predictions, use

procedures to correct, control, or

mitigate the consequences of those

abnormal opetation:(CFR: 41.5 143.5 I

. .

b a d on those predictiins, use

procedures to correct, control, or

mitigate the consequences of these

abnormal opemtion:(CFR: 41.5 143.5 /

45.3145.13)

based on those predictions, use

procedures to correct, control, or

mitigate the consequences bf those

abnormal operation:(CFR: 41.5 / 43.5 I

procedures to correct, control, or

mitigate the consequences of those

abnormal 0peration:jCFR: 41.5 I 43.5 I

KA

117A2.01

mGG2 .1.2f

28GG2.1.2

12982.01

33A2.02

3482.02

Decembei

Tier 2 Group 2

.

b 0 0 i Ability tc (ajprcdict the impacts of the

j .

.

j

j following on the (SYSTEM) and (b)

based on those predictions. use

procedures to wrfect, control. or

mitigate the consequences of those

abnormal opention:(CFR: 41.5 I43.5 /

abnormal ogeiation:(CFR: 41.5 / 43.5 I

___ .....

KIA Tople(s)

Randomly Rejected

kandomly Rejected

Randomly Rejected

of waste gas release monitors,

ition. gas flow rate and totalizer

~~.~

s(A

035A2.05

9441 GG2.4.36

O45A2.17

355GG2.2.21

s8GG2.4.6

071A2.02

072A2.02

!

ire Protection

Pier 2 Group 2

mitigate the consequences of those

abnormal operation:fCFW: 41.5 / 43.5 I

45.3 145.13)

I

~~ I..

.

December 17,2003

Tier 3

.

December 17,200:

ES-401

Tier I

Group

W G 1

TUG2

TaG2

TUG 1

TUG2

~~

Record of Rejected WAS

Form E§-401 -4

Randomly Selectec

WA

BEO5EG2.1.14 (9)

003A2.05 (1 3)

063GG2.1.30 (14)

(364A2.15 (I 6)

028GG2.1.2 (17)

SRO EXAM

Reason for Rejection

Cannot write a discriminating question on this KA. The

new randomly selected KA is BE05EG2.2.6.

System configuration does not apply to OW. The new

randomly selected KA is 003A2.01.

Not SRO oniy KA. No SRO only learning objective. The

new randomly selected KA is 88GG2.1 .I%.

ON§ does not have Emergency Diesels and the

malfunction (water buildup in cylinders) will not

translate to our hydro units. The new randomly

selected KA is 064A2.16.

ONS has deleted all requirements for Hydrogen

Recombiners and Purge. The new randomly selected

KA is 02982.01.

I

NUREG-1021, Draft Revision 9

NarnelSsfemnc&

Reactor Trip -

Stabilization

Small Break LOCA I 3

i1 a

T

7

9

T

7

i 2

T

7

L1

T

7

9

7

-

C

PLANTEVOLUT

,.

145.73)

conciitidn

I

p t y p F M n x

ressurizer ressure

Control System

Malfunction I 3

Steam Line Rupture -

i Excessive Heat

~ Transfer I 4

I

' Loss of Main

Feedwater I 4

Station Blackout / 6

Loss of 0 -site Power r

Tier I Group 1

~. ..

. .

KA

Question Type

127AK4.01

I Knowledge of the operational implications

of the following concepts as they apply to

I the (ABNORMAL PLANT

EVQdbUTION):(CFR: 41.8to41.10145.3)

responses as they apply to

(EMERGENCY PUNT

NOLUTION):(CFR: 41.5 / 41 . I O I 4 5 6 I

EVOLUTlON):(CFR: 41.5/41.10/45.6/

following as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR: 41.7 I 4 5 5 I

Closing the normal charging header

isolation valves

Leak rate vs. pressure drop

Sensors and detectors

MFW line break depressurizes the SIG

(similar to a steam line break)

Actions contained in EOP for loss of

offsite and onsite power

KIA Randomly Rejected

December 17,2003

Tier 1 Group 1

Stabilization -

Recovery I I

,Transfer / 4

Transfer - Loss of

Secondary Heat Slnk I

I I I I

PLANT EVOLUTI0N):JCFR: 41.7 I45.5 /

foilowing:(CFR: 41.7 145.7 / 45.8)

PLANT EVOLUTION):(CFR: 41.5 141.10/

PLANTkVOLU?lQN):(CFR: 41 . I O 143.5 /

anb emergency operations.

45.13)

failure modes. and automatic and

.

December 17,

_.

RO

3-3-

31

0

37

3

-

2.5

-

3.8

4.4

80

Tier I Group I

December 27,2003

Tier 1 Group 2

d use of the response

R: 41.7 145.7 145.8)

LANT EVOLUTION) and the

41.3/45.7145.8)

):(CFR: 41.7 / 45.5 I

Decem

lnad

ore Cooling I 4

H

Tier 1 Group 2

following:(CFR: 41.7 145.9 I45.8)

41.8 to 41.10 145.3)

following as they apply to ABNORMAL

PLANT EVBLUTION):(CFR: 41.10 143.5 I

Decem

Tier 1 Group 2

WA Randomly Rejected

igh Reactor Coolant d .

mergency Diesel Actr

Inadequate Subcmling

-

i1 -

a

is

B

r2

a

n

a

0

B

-

a

is

B

Question Type

AANTEVQLLITIQN):(CFR: 41.5141.101

45.6 145.13)

PLANT EVOLUTION):(CFR: 41.9 / 45.5 I

they apply to (ABNORMA

UTION):(CFR: 41.5141.10

responses as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR: 41.5141.101

45.6 /45.13)

EMERGENCY PLANT EVOLUTION):(CFR:

41 8to41.10145.3)

Decem

KIA Topie(@

Failed fuel-monitoring equipment

WA Randomly Rejected

UA Randomly Rejected

r 17,2003

Tier1 Group2

I

... . . ..

.~

~

rZ ~d~

,.

KA

QudieiTy pe

KIA Topic(s)

0 I 0 I BEQ8EA1.2

I Abilitv to ooefate and / or monitor the

I K/A Randomlv Weieeted

I

0 I 0 I BEOSEK1.1

1 Knowledge of the operational implications of I WA Randomly Rejected

I

j the followirig wnsepts as they apply to the

!EMERGENCY PLANT EVCLUTLONI.ICFR

.

~

,

\\~~

41.8 tQ 41.10 / 48.3)

1.8 to 41.10 145.3)

LaNT EVOLUTIONI:(CFR: 41.7 i 45.5 /

I .

I I

45.6)

automatic and manual features.

owing as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR: 42.7 / 45.5 /

.

ABNORivAL PLANT EVOLUTION) and the

I: 41.7 I45.7 / 45.8)

December 17,2003

Tier 2 Group 1

ffo

-

C!

a

7

5

-

(1 a

a

7

3

a

B

.

~.

G

Z

Question ?ype

0 I Knowledae of electrical Dower sumlies

..

to the foliowing:(CFR: 41.7)

fellowing:(CFR: 41.2 to 41.9 I 4 5 7 to

....

~

..... ....

__

-__

December 17,2003

Tier 2 Group 1

RO

providakr the following:(d!=k: 41.7)

recirculation mode, possibly

sed by clogged sump screen, pump

t high temperature exceeded

avitation, voiding) or sump ievei below

45.3 / 45.13)

l

l l

I

1 This is a Generic, no stern statement is

Knowledge of the purpose and function

03962.1.26

.2 .3

associated.

of maior svstem components and

.

controls.

I

I I

specifications

i

Tier 2 Group 1

' Generator

Instrument ir r"

Containment

Monitoring

.. .

.

on the following:(CFR: 41.7 145.6)

1 1

145.5 to45.8)

i

l

I

v

the (gYSTEh4) includiflg:(CFk: 41.7 1

compressor

45.5)

I

l

I

0 0 1 This is a Generic, no stem statement is

Ability to recognize indications for

system operatina Darameters which are

assmiated.

I ! !

ehtly-levil conditions for technical

specifkations.

procedures to correct, control, or

mitigate the consequences of those

abnormal operation:(CFR: 42.5 / 43.5 1

December 17,2004

Tier 2 Group I

nQ

provide for the foliowing:(CFR: 41.7)

to41.9145.3tO

j

..

.

i

-,

December 17,2003

Tier 2 Group 2

-

.- -

m e / safely Functio

ydrogen

ecombiner and

urge Control

.ontainment Purge

pent Fuel Fool

ooling

uel Handling

iquipment

procedures to correct, control, or

mitigate the mn?&?quences of those

abnormal operation:(CFW: 41.5 143.5 I

45.3145.13)

145.8)

based on those predictions. use

procedures to correct, control, or

mitigate the consequences of those

abnormal operation:(CFR: 41.5 / 43.5 I

procedures to correct, control, or

+

l35K4.0

-.

~

!

Area Radiation

Monitoring

'Station air

rpo

Tier 2 Group 2

the (SYSTEM) including:(CFR: 41.7 /

. .~

Re

!

Controi Rod Drive

Instrumentation

Incore

Temperatwe

Monitor I

ontainment Iodin

Removal

Tier 2 Group 2

ased on those predictions, use

ocedures to correct, control. or

itigate the consequences of those

I

/to

Tier 2 Group 2

Qecember 17,2003

RQ

2.8

Conduct of Operations

1 G2.1.27

1 Knowledge of system purpose and or hnction.

Tier 3

2.9

. .

December 17,200:

Tier 1 Group 1

ppyQ

FGiaGl

eactor rip-

h a g s Break LOCA / 2

I

1 RCP Malfunctions I 4

i

' Loss of Rx Coolant

Makeup / 2

kizamma

PLANT EVBLUTION):(CFW: 41.15 /43.5/

I .

45.13)

I

45.13)

I

5 I026AA2.55

I Ability to determine and interpret the

following as they apply to ABNORMAL

I PLANTEVOLUTIONI:ICFR:41.10/435/

ktowl6dge of bases in technical

specifications for limiting conditions for

operations and safely limits.

KIA Randomly Rejected

kiA Randomly Rejected

When to jog RCPs during ICC

WA Randomly Rejected

UA Randomly Rejected

.

December 17

-.

RO

4.1 -

2 - r

5.g

42

3.4

__

3.4

_.

4.6

__

2.4

m3

Pier 1 Group 1

I

1...1

I

L

... . .-

I I

45.13)

I I

associated.

45.i3)

I I

associated

PLANT EVOLUBION):(CFR: 41.10 / 43.5 /

ES-404

Tier I'

Group

T1IG1

Tl/G2

PllG2

TUG 1

T2/G 7

TUG 1

TUG2

TaG2

TUG2

Randomly

Selected KIA

029EK3.04 (9)

032881 .Qi

(21)

068AK3.14 (23)

068AK3.12 (23)

008A4.09 (33)

878K4.03 (48)

026K4.06 (51)

103K4.01 (52)

064A3.04 (55)

028K2.01 (56)

055G2.2.22 (61)

027A2.01 (65)

Record of Rejected WAS

RO EXAM

Form ES-404 -4

Reason for Rejection

ON§ does not isolate the normal charging header when

emergency borating for an A'WnlS. The new randomly

selected KA is 029EK3.14

Selected new KA. At ON§ operators do not select

alternate power supplies for the Source Range Nuclear

Instrumentation. This would be performed by !&E. On the

new KA the question will be written concerning overlap

with Wide-range Nls instead of Intermediate-range Nls.

ON§ no longer has Intermediate-range Nls. The new

randomly selected KA is 032AA2.04.

ONS does not have a Safety injection setpoint for main

steam Bine pressure. The new randomly selected KA is

068AK3.12.

Could not write a discriminating question on this KA.

Sequence of actions contained in the Control Evacuation

AP is not significant. The new randomly selected KA is

068AK3.12.

Replace KA. ON§ does not have a CCWS temperature

control valve. The new randomly selected KA is 008A4.07

Could not write a discriminating question on this KA. The

new randomly selected KA is 078K4.02.

ONS does not have Recirculation spray system. The new

randomly selected KA is 026K4.86.

ONS does not have vacuum breakers associated with the

containment. The new randomlv selected KA is 103K4.86.

ONS does not have Emergency Diesels and the WA

(number of starts available with an air compressor) does

not translate well to our hydro units. The new randomly

selected KA is 064A3.07.

ONS no longer has Hydrogen recombiners. The new

randomly selected KA is Q29K4.03.

ON§ has no limiting conditions or safety limit associated

with condenser air removal. The new randomly selected

KA is 056G2.d .32.

ONS does not have an Iodine Removal System. The new

randomly selected KA is 01 6K3.02.

NUREG-I 021 I Draft Revision 9

T3

I T3

I (32.2.23 (71)

I SRQ only KA. The new randomly selected KA is G2.2.30.

( 2 . 1 2 4 (66)

Could not write a discriminating question on this KA. This

KA is better evaluated on the operating exam. The new

At ONS Reactor Operators are not qualified to serve on

the fire brigade. The new randomly selected #A is

NUREG-1021, Draft Revision 9

ML042190120

Text

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