ML042190120

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June 2004 Exam 50-269/2004-301 Final Sample Plans/Outlines
ML042190120
Person / Time
Site: Oconee  Duke Energy icon.png
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)


See also: IR 05000269/2004301

Text

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 Date of Examination: June, 2004

Examination Level (circle one): RO / SRO Operating Test Number:

Describe activity to be performed

Adrnin-100, Determine SDM with a Dropped Control

Conduct of Operations

Rod

GEN 2.1 2 3 (3.W4.0) PT/1/A/1103/15, Reactivity Balance (10 min)

___ ~ -~ ~~ ~~

Adrnin-103, Perform Manual RCS Leakage Calculation;

Conduct of Operations PT/0600/010 (RO Only)

GEN 2.1.7 (3.U4.4) (last exam) (group activity) (18 min)

Equipment Control Adrnin-202, Perform Surveillance to Verify SSF RCMUP

Qperability

GEN 2.2.12 (3.0/3.4)

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

Radiation Control

GEN 2.3.4 (233.1)

Adrnin-402, Perfom Actions for Medical Emergency

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

GEN 2.4.39 (3.3/3.1)

(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* Safety

Function

a. CR0-012A, Recover a dropped rod

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

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

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

EOP Enclosure 5.1 (ES Actuation) D, A, S

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

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

Failed Closed) 4P

EOP Enclosure 5.27. Alternate Methods for Controlling EFDW Flow 4s

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

CRO-700, Place ICS In Auto following LOSS Of Auto Power N. A. S

AP123 (Loss Of ICs Power) Enclosure 5 5 (Placing ICs In Auto) 7

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

f. CRO-060, Perform Required Actions For Turbine Building Flood

APllO (Turbine Building Flood) D. s 8

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

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)

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 iJPM Title Type Code* Safety

Function

a. CRO-012A, Recover a dropped rod

APIliAf1700115, OP/O/N11O5/09. Encl 4.10 D, S , A 1

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

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

EOP Enclosure 5.1 (ES Actuation) D, A, S

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) 4P

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 4s

[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) 7

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

f. CRO-060, Perform Required Actions For Turbine Building Flood

APilO (Turbine Building Flood) 8

rm:AFTBWiAQ7AAI .3 (3.3/3.5)1 (7 min)

g. CRO-900, Release GWD Tank

OPil&2/A/11C41018 Encl. 4.9 (GWD Tank Release) 9

[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)

i. NLO-039, Prime The Spent Fuel Pool Fill Line

EOQ Encl. 5.7, HPI Pump Operations from ASW Pump Switchgear D, L, R 2

[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)

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

I

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

EOP Enclosure 5.1 (ESActuation)

[KA: EQE-009EA1.13 (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)

' 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 B, L, R 2

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

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: (DJirectfrom 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 I II

Vote: 1. 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.

2. 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.

3. 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.

4. Systemslevolutiofls within each group are identified on the associated outline.

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

6.* 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.

7. 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.

8. Fur Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on

Form ES-401-3.

9. 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 -

45.13)

II

4

December 17,2003

- ~

Name I Safety Function

Continuous Rod Withdr

Dropped Control Rod /

inoperablelStuck Conk

PLANT EVOLUTION):(CFR:41.10 143.5 I

associated

g as they apply to ABNORMAL

EVOLUTIQN):(CFR: 41.10 143.5 I

' Steam Generator Tube

PLANT EVOLUTION):(CFR: 41.10 143.5 /

_ _ ~ ~ ___~

~ ~ ~ ~ ~ ~ ~ ~ ~.

~ ~

Decemt

Accidental Gaseous Ri

associated,

I / i

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

,

Tier 1 Group 2

g as they apply to A

EVOLUTBON):(CFR.

I

following as they apply to (EMERGENCY

PLANT EVOLUTION):(CFR:41 . I O i43.5 /

Ill 45.13)

PLANT EVOLUTION):(CFR:41.10 143.51

Ill 45.13)

December 17.2003

Pier 1 Group 2

associated. Imitigation strategies.

and abnormal operating procedures.

associated. require the notification of plant personnel.

~ ~

~ ~~

December 17,2003

548

Tier 2 Group 1

F m e I Safety Functio

procedures to correct. control. or

mitigate the consequences of those

abnormal operation:(CFR:41.5 I43.5 /

!Auxilialy/trnergency

Feedwater

lT--m--

rocass a iation

Monitoring

I=-----

Nice Water

associated

' containment

I

Pier 2 Group 1

ation:(CFR: 41.5 143.5 /

hemicai and

Jolume Control

procedures to correct, control, or

mitigate the consequences Of those

abnormal operation:(CFR: 41.5 143.5 /

Residual Heat

Removal

krnergency Core

Cooling

Pressurizer

Relief/Quench Tank

Component Cooling

Water

Pressurizer

Pressure Control

Reactor Protection

.- . ,

Tier 2 Group 1

Cooling

based i n those predictions. use

procedures to correct, control, or

mitigate the consequences of those

abnormal operatin:(CFR: 41.5/ 43.5/

45.3145.13)

p5GG2.22

Q6A2.08

based on those predictions, use

procedures to correct, control, of

mitigate the consequences of those

abnormal operatim:(CFR: 41.5143.5I

45.3/ 45.13)

I

k Steam folbwing on the (SYSTEM) an

d A Randomly Rejected 339A2.04

based on those predictions, use

procedures to correct, control, or

mitigate the conquenms of those

abnormal operation:(CFR: 41.5I43.5I

056A2.04

. .- - ~.

L- -  !&cemi

Tier 2 Group 1

. ~~~~~.~ ..- .. .~ ....

1 Question Type

~ ~~

KIA Topic(6) KA 1RO

I Drocedures to correct, control. or I I I

the consequences of those

operation:(CFR:44.5 / 43.5 / I I

1

tmergency Diesel 3 a 3

45.3 145.13)

I I

I Generator

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 7- Question Type

-r 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 /

1 Reactor Coolant

b ressurizer eve

Control

procedures to correct. control, or

mitigate the amsequences of those

'i Nuclear

Instrumentation

mitigate the consequences of those

abnormal operation:(CFR:42.5 / 43.5 /

Ih]an-nuclear

,Instrumentation

abnormal operation:(CFR:41.5 / 43.5 I

December 17, 2003

Tier 2 Group 2

... . -

ame I Safety Functi6 I

~ ~

&&tiOll Type wa ~~ P 0 KA

Cn-core 0 IAbility to (a) predict the impacts of the I WA Randomlv. Reiected

. 117A2.01

Temperature following ofl the (SYSBEMj and (b)

Monitor based on those predictions, use

proceduresto correct, control, or

mitigate the consequences of those

abnormal opetation:(CFR: 41.5 143.5 I

,

' Contalnment lodine

Removal

mGG2.1.2f

iydrogen 28GG2.1.2

qecombiner and

'urge Control

ontainmant Purge 12982.01

..

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)

ipent Fuel Pool 33A2.02

ooiing

based on those predictions, use

procedures to correct, control, or

mitigate the consequences bf those

abnormal operation:(CFR: 41.5 / 43.5 I

uel Handling 3482.02

iquipment

procedures to correct, control, or

mitigate the consequences of those

abnormal 0peration:jCFR: 41.5 I 43.5 I

Decembei

Tier 2 Group 2

___ ..... ~~.~

KIA Tople(s) s(A

. . .

. . .

b 0 0 i Ability tc (ajprcdict the impacts of the Randomly Rejected 035A2.05

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: 41.5I43.5 /

kandomly Rejected 9441 GG2.4.36

Randomly Rejected O45A2.17

Randomly Rejected 355GG2.2.21

Randomly Rejected s8GG2.4.6

of waste gas release monitors, 071A2.02

ition. gas flow rate and totalizer

abnormal ogeiation:(CFR: 41.5/ 43.5I

072A2.02

Pier 2 Group 2

mitigate the consequences of those

abnormal operation:fCFW:41.5 / 43.5I

45.3145.13)

I I

!

ire Protection

~~ I.. .

December 17,2003

Tier 3

.

.

December 17,200:

~~

ES-401 Record of Rejected WAS Form E§-401-4

SRO EXAM

Tier I Randomly Selectec Reason for Rejection

Group WA

WG1 BEO5EG2.1.14 (9) Cannot write a discriminating question on this KA. The

new randomly selected KA is BE05EG2.2.6.

TUG2 003A2.05 (1 3) System configuration does not apply to O W . The new

randomly selected KA is 003A2.01.

TaG2 063GG2.1.30 (14) Not SRO oniy KA. No SRO only learning objective. The

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

TUG 1 (364A2.15 (I 6) 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.

TUG2 028GG2.1.2 (17) 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& i1 i2 L1

Reactor Trip - a T T

Stabilization

T 7 7

Small Break LOCA I 3 T 7 7

7 7 7

PLANTEVOLUT

9 7 7

T 7 9

T 7 7

-

7 7 C

,.

145.73) Iconciitidn

Tier I Group 1

~. .. . .

p t y p F M n x KA Question Type

ressurizer ressure 127AK4.01 IKnowledge of the operational implications

Control System

Malfunction I 3 Iof the following concepts as they apply to

the (ABNORMAL PLANT

EVQdbUTION):(CFR: 41.8to41.10145.3)

Closing the normal charging header

responses as they apply to isolation valves

(EMERGENCY P U N T

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

Leak rate vs. pressure drop

I

Steam Line Rupture - Sensors and detectors

i Excessive Heat

~ Transfer I 4

' Loss of Main MFW line break depressurizes the SIG

Feedwater I 4 (similar to a steam line break)

Station Blackout / 6 Actions contained in EOP for loss of

offsite and onsite power

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

r

Loss of 0 -site Power

following as they apply to (ABNORMAL

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

KIA Randomly Rejected

December 17,2003

Tier 1 Group 1

_.

RO

3-3-

IIII 31

PLANT EVOLUTI0N):JCFR:41.7 I45.5 /

0

foilowing:(CFR:41.7 145.7 / 45.8)

37

PLANT EVOLUTION):(CFR:41.5 141.10/

3

Stabilization

Recovery I I

-

-

2.5

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

45.13)

-

3.8

,Transfer/ 4

4.4

Transfer - Loss of

Secondary Heat Slnk I

failure modes. and automatic and

.

December 17,

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

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

H

lnad ore Cooling I 4

Decem

Tier 1 Group 2

-

i1

- r2 ;

- Question Type KIA Topie(@

AANTEVQLLITIQN):(CFR: 41.5141.101

45.6 145.13)

.

igh Reactor Coolant d a a a Failed fuel-monitoring equipment

PLANT EVOLUTION):(CFR:41.9 / 45.5 I

a a a WA Randomly Rejected

a n a WA Randomly Rejected

a a a

they apply to (ABNORMA

UTION):(CFR: 41.5141.10

mergency Diesel Actr a a a WA Randomly Rejected

is 0 is UA Randomly Rejected

responses as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR:41.5141.101

45.6 /45.13)

Inadequate Subcmling B B B UA Randomly Rejected

EMERGENCY PLANT EVOLUTION):(CFR:

41 8to41.10145.3)

Decem r 17,2003

Tier1 Group2

rZ ~d~ ,. ... . . .. .~

I

~

KA Q u d i e i T y pe KIA Topic(s)

0 I 0 IBEQ8EA1.2 IAbilitv to ooefate and / or monitor the I K/A Randomlv Weieeted

I I I I

0 I 0 IBEOSEK1.1 1 Knowledge of the operational implications of I WA Randomly. Rejected.

I 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 /

II

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! (1 G Z Question ?ype

a a 0 I Knowledae of electrical Dower sumlies

..

to the foliowing:(CFR:41.7)

a a

a a

a 7

a 3

a a

7 a

5 B

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

I

45.3 / 45.13)

1 This is a Generic, no stern statement is

I

Knowledge of the purpose and function

l

I

03962.1.26

l l

I I

.2 .3

associated. . svstem

of maior . components and

controls.

I II i

specifications

Tier 2 Group 1

... .

on the following:(CFR: 41.7 145.6)

11 145.5 to45.8)

i l l I

v

' Generator the (gYSTEh4) includiflg:(CFk:41.7 1 compressor

45.5)

I l l I

0 0 1 This is a Generic, no stem statement is Ability to recognize indications for

assmiated. system operatina Darameters which are

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

r"Instrument ir

Containment

Monitoring

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

proceduresto correct, control, or

mitigate the mn?&?quencesof those

abnormal operation:(CFW:41.5143.5I

45.3145.13)

pent Fuel Fool
ooling

+

145.8)

uel Handling

iquipment

based on those predictions. use

procedures to correct, control, or

mitigate the consequences of those

abnormal operation:(CFR: 41.5/ 43.5I

l35K4.0

proceduresto correct, control, or

rpo

Tier 2 Group 2

-. ~

!

Area Radiation

Monitoring

'Station air

the (SYSTEM) including:(CFR:41.7 /

. .~

Re

Tier 2 Group 2

! Controi Rod Drive

Instrumentation

Instrumentation

Incore

Temperatwe

Monitor

I ontainment Iodin

Removal

ased on those predictions, use

ocedures to correct, control. or

itigate the consequences of those

/to

Tier 2 Group 2

I

Qecember17,2003

RQ

Tier 3

Conduct of Operations 1 G2.1.27 1 Knowledge of system purpose and or hnction. 2.8 2.9

..

December 17,200:

Tier 1 Group 1

ppyQFGiaGl

eactor rip-

-.

-

RO

4.1

ktowl6dge of bases in technical 2-r

specifications for limiting conditions for

operations and safely limits.

KIA Randomly Rejected 5.g

PLANT EVBLUTION):(CFW:41.15/ 4 3 . 5 /

h a g s Break LOCA / 2 kiA Randomly Rejected 42

I

1 RCP Malfunctions I 4 When to jog RCPs during ICC 3.4

i

' Loss of Rx Coolant

Makeup / 2

WA Randomly Rejected

__

3.4

I .

45.13)

kizamma WA Randomly Rejected

_

4.6

.

I

I

5 I026AA2.55

I

45.13)

IAbility to determine and interpret the UA Randomly Rejected

__

2.4

I following as they apply to ABNORMAL

PLANTEVOLUTIONI:ICFR:41.10/435/

.

December 17 m3

Pier 1 Group 1

... . .-

II 45.13)

II associated.

45.i3)

II associated

PLANT EVOLUBION):(CFR:41.10 / 43.5 /

I 1...1 I L L

ES-404 Record of Rejected WAS Form ES-404 -4

RO EXAM

Tier I' Randomly Reason for Rejection

Group Selected KIA

T1IG1 029EK3.04 (9) ON§ does not isolate the normal charging header when

emergency borating for an A'WnlS. The new randomly

selected KA is 029EK3.14

032881 .Qi (21) 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.

Tl/G2 068AK3.14 (23) ONS does not have a Safety injection setpoint for main

steam Bine pressure. The new randomly selected KA is

068AK3.12.

PllG2 068AK3.12 (23) 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.

TUG 1 008A4.09 (33) Replace KA. ON§ does not have a CCWS temperature

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

T2/G 7 878K4.03 (48) Could not write a discriminating question on this KA. The

new randomly selected KA is 078K4.02.

026K4.06 (51) ONS does not have Recirculation spray system. The new

randomly selected KA is 026K4.86.

103K4.01 (52) ONS does not have vacuum breakers associated with the

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

TUG1 064A3.04 (55) 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.

TUG2 028K2.01 (56) ONS no longer has Hydrogen recombiners. The new

randomly selected KA is Q29K4.03.

TaG2 055G2.2.22 (61) ON§ has no limiting conditions or safety limit associated

with condenser air removal. The new randomly selected

KA is 056G2.d .32.

TUG2 027A2.01 (65) ONS does not have an Iodine Removal System. The new

randomly selected KA is 016K3.02.

NUREG-I 021 Draft Revision 9

I

T3 ( 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

I T3 I (32.2.23(71) I SRQ only KA. The new randomly selected KA is G2.2.30.

At ONS Reactor Operators are not qualified to serve on

the fire brigade. The new randomly selected #A is

NUREG-1021, Draft Revision 9