ML090710630

007EK2.03

008AG2.4.45

NAME / SAFETY FUNCTION:

IR

Reactor Trip - Stabilization - Recovery

3.5

3.6

1 1

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

D~LJDDlJD[J[JDD

Knowledge of the interrelations between

(EMERGENCY PLANT EVOLUTION) and

the following:(CFR: 41.7 1 45.7 1 45.S)

--......*......*....... ~~~~~~~~~-

Pressurizer Vapor Space Accident 1 3

4.1

4.3 0 0 0 0 II fJ

0

lJ ~

This is a Generic, no stem statement is

associated.

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

-.~.-..

--.--.. -."-~-~.--

--.~--.-~

009EA2.10

Small Break LOCA 1 3

3.1

3.7

[] 0

00

D~ODD

015AA2.0S

RCP Malfunctions I 4

022AK1.02

Loss of Rx Coolant Makeup 1 2

Ability to determine and interpret the

following as they apply to (EMERGENCY

PLANT EVOLUTION):(CFR: 41.10/43.51

45.13)

3.4

3.5 0 [J 0 0 0 0 0 ~ 0 0 0

Ability to determine and interpret the

following as they apply to ABNORMAL

PLANT EVOLUTION):(CFR: 41.101 43.5/

45.13)

2.7

3.1

~ [J [J 0 0 0 0 0 0 0 0

Knowledge of the operational implications

of the following concepts as they apply to

the (ABNORMAL PLANT

EVOLUTION):(CFR: 41.S to 41.10 1 45.3)

~~-::-c--.- -.* .. **.*.***-** ... -*~~~~___=_:____:__:__-c

025AG2.2.36

Loss of RHR System 14

3.1

4.2 0 0 0 0 0 0 0 0 0 0 (ii)

This is a Generic, no stem statement is

associated.

Page 1 of 3

FORM ES-401-2

TOPIC:

Reactor trip status panel

...

..----~

Ability to prioritize and interpret the significance of each

annunciator or alarm.

Airbome activity

When to secure RCPs on high bearing temperature

~

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

Relationship of charging flow to pressure differential

between charging and RCS

Ability to analyze the effect of maintenance activities,

such as degraded power sources, on the status of

limiting conditions of operations

4/1/200S 2:09 PM

ES-401, REV 9

[ !RAFT: J

T1Gl PWR EX='NAfl8N OI~"N

FORM ES-401-2

NAME I SAFETY FUNCTION:

IR

K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G

TOPIC:

026AA2.03

Loss of Component Cooling Water / 8

2.6

2.9 0 0 0 0 0 0 0 ~ 0 0 0

The valve lineups necessary to restart the CCWS while

bypassing the portion of the system causing the

abnormal condition

029EG2.1.31

A TWS /1

040AK1.06

Steam Line Rupture - Excessive Heat

Transfer /4

-_. __ ._--_ ... ------

054AK 1.02

Loss of Main Feedwater / 4

055EK2.04

Station Blackout / 6

_

... -------

056AA 1.11

Loss of Off-site Power 1 6

Ability to determine and interpret the

following as they apply to ABNORMAL

PLANT EVOLUTION):(CFR: 41.10/43.S/

45.13)

4.*6~ --:-4-:::.3---:0=-0'*0--0-[]--[] DOD D ~

This is a Generic, no stem statement is

associated.

Ability to locate control room switches, controls and

indications and to determine that they are correctly

reflecting the desired plant lineup.

-_.-.---_

... _._-

--

_._------_ ... _------

3.7

3.8

~ 0

0

0 0 0

0

High-energy steam line break considerations

Knowledge of the operational implications

of the following concepts as they apply to

the (ABNORMAL PLANT

EVOLUTION):(CFR: 41.8 to 41.10 / 45.3)

3.6

4.2

~ 0

0 0 0 0 0 0 0 0 0

Effects of feedwater introduction on dry SIG

Knowledge of the operational implications

of the follOwing concepts as they apply to

the (ABNORMAL PLANT

EVOLUTION):(CFR: 41.8 t041.10 /45.3)

-

o ~ 0

0

0 0 0 0 0 0 0

Pumps

Knowledge of the interrelations between

(EMERGENCY PLANT EVOLUTION) and

the following:(CFR: 41.7/45.7/45.8)

3.7

3.7 0 0 0

0 0 0

~ 0 0 0

0

Ability to operate and / or monitor the

following as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR: 41.7/45.SI

45.6)

Page 2 of3

HPI system

4/1/2008 2:09 PM

ES-401, REV 9

NAME I SAFETY FUNCTION:

057AK3.01

Loss of Vital AC Inst. Bus 1 6

.

_-----------

058AA1.01

Loss of DC Power 1 6

062AK3.04

Loss of Nuclear Svc Water 1 4

_

... -------_._-----------

065AK3.04

Loss of Instrument Air / 8

077AA1.03

Generator Voltage and Electric Grid

Disturbances I 6

~ ~~

I

T1G1 PWR EXAMINATION OUTLINE

IR

K1 K2 K3 K4 K5 K6 A1 A2~A3'A4 G

4.1

4.4 0 0 ~ 0 0 0 0 0 0 [1 0

Knowledge of the reasons for the following

responses as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR: 41.5/41.101

45.6/45.13)

FORM ES-401-2

TOPIC:

Actions contained in EOP for loss of vital ac electrical

instrument bus

3.4

3.5 0 0- 0 0 0 0 ~ 0 0 0- 0

Cross-tie of the affected dc bus with the alternate supp~

Ability to operate and 1 or monitor the

3.5

3.7

following as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR: 41.7/45.5/

45.6)

_._--------------

o 0 ~ 0 0 0 0 0 0 0 0

Effect on the nuclear service water discharge flow header

Knowiedge of the reasons for the following

responses as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR: 41.5/41.101

45_6/45.13)

of a loss of CCW

---_._._----.

__ .,-----_.-

.-------.-

3

3.2 0 0 ~ [J 0 0 0 0 0 0 0

Cross-over to backup air supplies

Knowledge of the reasons for the following

responses as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR: 41.5/ 41.10 1

45.6 1 45.13)

3.8

3.7 0 0 0 0 0 0 ~ 0 0 0 0

Ability to operate and I or monitor the

following as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR: 41.7 I 45.51

45.6)

Voltatge regulator controls

V\\iE11'EK2.1

Loss of Emergency Coolant Recirc. 14

3.6

3.9 0 ~ 0 0 0 0 0 0 0 0 0

_.:----:-----::----

Components and functions of control and safety systems,

including instrumentation, signals, interlocks, failure

modes and automatic and manual features.

Knowiedge of the interrelations between

(EMERGENCY PLANT EVOLUTION) and

the foliowing:(CFR: 41.7/45.7/45.8)

Page 3 of3

4/1/2008 2:09 PM

ES-401, REV 9

NAME I SAFETY FUNCTION:

001AK3.02

Continuous Rod Withdrawal/1

---- -----:---

005AA 1.01

Inoperable/Stuck Control Rod 11

024AA2.01

Emergency Boration /1

036AK3.0"1---Fuel Handling Accident I 8

059AK1.02

Accidental Liquid RadWaste ReI. 19

.- ---.. --- ----------

067 AG2.1.31

Plant Fire On-site I 9 8

I

DRAFT J

T1G2 PWR EXAMINATION OUTLINE

IR

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

3.2

4.3 0 0 ~ 0 0 0 0 0 0 0 0

Knowledge of the reasons for the following

responses as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR: 41.5/41.10 I

45.6/45.13)

--=----=-=_._-----

3.6

3.4 0 0 0 0 0 0 ~ 0 0 [J 0

Ability to operate and 1 or monitor the

following as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR: 41.7 I 45.51

45.6)

3.8

4.1

0 0 0 0 0 0 0 ~ 0 0 0

Ability to determine and interpret the

following as they apply to ABNORMAL

PLANT EVOLUTION):(CFR: 41.10/43.51

45.13)

3.1

3.7 [J 0 ~ 0 0 0 0 0 0 0 0

Knowledge of the reasons for the following

responses as they apply to (ABNORMAL

PLANT EVOLUTION):(CFR: 41.5/41.101

45.6/45.13)

2.6

3.2

~ 0 0 0 0 0 0 0 0 0 0

Knowledge of the operational implications

of the following concepts as they apply to

the (ABNORMAL PLANT

EVOLUTION):(CFR: 41.8 to 41.10 I 45.3)

4.6

4.3 0 0 0 [J 0 0 0 0 0 0 ~

This is a Generic, no stem statement is

associated.

Page 1 of 2

FORM ES-401-2

TOPIC:

Tech-Spec limits on rod operability

CRDS

-:-:----:7"-----------

Whether boron flow and/or MOVs are malfunctioning

from plant conditions

Different inputs that will cause a reactor building

evacuation

Biological effects on humans of various types of

radiation, exposure levels that are acceptable for nuclear

power plant personnel and the units used for radiation-

intenSity measurements and for radiation exposure levels

----- ----------

Ability to locate control room switches, controls and

indications and to determine that they are correctly

reflecting the desired plant lineup.

411/2008 2:09 PM

[

DRAFT

I

ES-401, REV 9

T1G2 PWR EXAMINATION OUTLINE

NAME I SAFETY FUNCTION:

IR

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

WEOOEA 1.1

RCS Overcooling - PTS I 4

3.8

3.8 DDDDDD~DDDD

Ability to operate and I or monitor the

following as they apply to (EMERGENCY

PLANT EVOLUTION):(CFR: 41.7 I 45.51

45.6)

_._-_._

.... _--

--~-.----

-

WE10EK1.1

Natural Circ. With Seam Voidl4

3.3

3.6

~ 0 0 0 0 0 0 0 0 0 0

Knowledge of the operational implications

of the following concepts as they apply to

the EMERGENCY PLANT

EVOLUTION):(CFR: 41.8 to 41.10 145.3)

-

-_._---_. ---_. --------:--

WE14EK2.1

Loss of CTMT Integrity 15

--_._.

>.4

3.7

D~DDDDDDDOD

Knowledge of the interrelations between

(EMERGENCY PLANT EVOLUTION) and

the following:(CFR: 41.7/45.7/45.8)

Page 2 of 2

FORM ES-401-2

TOPIC:

Components and functions of control and safety systems,

including instrumentation, signals, interlocks, failure

modes and automatic and manual features.

Components, capacity, and function of emergency

systems.

.

-

Components and functions of control and safety systems,

including instrumentation, signals, interlocks, failure

modes and automatic and manual features.

4/1/2008 2:09 PM

ES-401, REV 9

NAME I SAFETY FUNCTION:

003A1.04

Reactor Coolant Pump

_._------ ---

003K4.02

Reactor Coolant Pump

[

DRAFT J

T2Gl PWR EXAMINATION OUTLINE

IR

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

2.6

2.5 0 0 0 0 0 0 ~ 0 0 0 0

Ability to predict and/or monitor changes in

parameters associated with operating the

(SYSTEM) controls including:(CFR: 41.5/

45.5)

FORM ES-401-2

TOPIC:

RCP oil reservoir levels

_.'._-----------_ .* ,----_. __ .--------._----_._---_._---." ..... _._--------

2.5

2.7 0 0 0

~J 0 0 0 [] 0 0 0

Prevention of cold water accidents or transients

Knowledge of (SYSTEM) design feature(s)

and or interlock(s) which provide for the

foliowing:(CFR: 41.7)

004A3:16

ChemlCalimd Volume COntrol

3.8-4.2[]-0-0 0 0-0 0 0 ~- 0 D--Interpretation of emergency borate valve*positio-n--------

Abili; to ~onitor auto~atic operations of

indicating lights

the (SYSTEM) including:(CFR: 41.7/45.5)

.. _-

.---

005K6.03

Residual Heat Removal

- ------_._-----------------._- ---. -----

006A3.06

Emergency Core COOling

007A2.05

Pressurizer Relief/Quench Tank

2.5

2.6 0 DOD 0 ~ 0 0 0 0 0

RHR heat exchanger

Knowledge of the effect that a loss or

malfunction of the following will have on

the (SYSTEM):(CFR: 41.7 f 45.7)

--=----:::---------_._---------------

3.9

4.2

[] D.D 0 0 0 0 [J ~ 0 0

Valve lineups

Ability to monitor automatic operations of

the (SYSTEM) including:(CFR: 41_7/45.5)

---=--------------------------------------------

Exceeding PRT high-pressure limits

3.2

3.6 0 0 0 0 0 0 0 ~ 0 0 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: 41.5/43.5/45.3/45.13)

Page 1 of 5

4/1/2008 2:09 PM

ES-401, REV 9

NAME I SAFETY FUNCTION:

008A3.04

Component Cooling Water

_._._-----_._-- ---.,.--.

008K1.04

Component Cooling Water

010A2.01

Pressurizer Pressure Control

{

DRAFT

,

T2G1 PWR EXAMINATION OUTLINE

IA

K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G

AO

2.9

3.2 0 0 0 0 0 0 0 0 ~ 0 0

Ability to monitor automatic operations of

the (SYSTEM) including:(CFR: 41.7 14S.5)

.

3.3

~ 0 0 0 0 0 0 0 0 0 []

Knowledge of the physical connections

and/or cause-effect relationships between

(SYSTEM) and the following:(CFR: 41.2 to

41.9/4S.7 to 45.8)

3.3

3.6 0 0 0 0 0 0 0 ~ 0 0 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: 41.51 43.51 45.31 45.13)

FORM ES-401-2

TOPIC:

Requirements on and for the CCWS for different condi-

tions of the power plant

RCS, in order to determine source(s) of RCS leakage into

theCCWS

Heater failures

,::--

012K2.01

Reactor Protection

---,:--- ---------_

.. _----_.-----_

.. _.-

-_._-----

3.3

3.7 0 ~ 0 0 0 0 0 0 0 0 0

RPS channels, components and interconnections

Knowledge of electrical power supplies to

the foliowing:(CFR: 41.7)

_

.. _---

013G2.4.46

Engineered Safety Features Actuation

4.2

4.2 0 0 0 0 0 0 0 0 0 0 ~

022K4.03

This is a Generic, no stem statement is

associated.

_._ .. _-_ ..... -.. -

._----------==--==--==

Containment Cooling

3.6

4.0 0 0 0 ~ 0 0 0 0 0 0 0

Knowledge of (SYSTEM) deSign feature(s)

and or interlock(s) which provide for the

following:(CFR: 41.7)

Page20f 5

.----,-.,---,-. _._------

Ability to verify that the alarms are consistent with the

plant conditions.

Automatic containment isolation

4/1/2008 2:09 PM

ES-401, REV 9

NAME / SAFETY FUNCTION:

025K502

Ice Condenser

TlGC::;:=~FlJ

IR

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

2.6

2.8 0 0 0 0 ~ 0 0 0 0 0 0

Knowledge of the operational implications

of the following concepts as they apply to

the (SYSTEM):(CFR: 41.5/45.7)

FORM ES-401-2

TOPIC:

Heat transfer

025K6.01

Ice Condenser-**--*--**--**-------* 3.4

3.6 0 0 0 0 0 ~ 0 0 0 0 0

Upper and lower doors of the ice condenser

026K2.01

Containment Spray

026K3.02

Containment Spray

039K5.05

Main and Reheat Steam

059K3.04

Main Feedwater

061K3.01

Auxiliary/Emergency Feedwater

Knowledge of the effect that a loss or

malfunction of the following will have on

the (SYSTEM):(CFR: 41.7/45.7)

3.4

3.6 0 ~ ODD D D DOD 0

Knowledge of electrical power supplies to

the foliowing:(CFR: 41.7)

Containment spray pumps

.".....-:=-=--==--= .. _-_._ ... _-------_._ .. _._-_._ ..

4.2

4.3 0 0 ~ DOD 0 DOD 0

Recirculation spray system

Knowledge of the effect that a loss or

malfunction of the (SYSTEM) will have on

the foliowing:(CFR: 41.7/45.6)

2.7

3.1 DOD 0 ~ DOD DOD

Knowledge of the operational implications

of the fol/owing concepts as they apply to

the (SYSTEM):(CFR: 41.5/45.7)

3.6

3.8 0 0 ~ 0 0 0 0 0 0 0 0

Knowledge of the effect that a loss or

malfunction of the (SYSTEM) will have on

the fol/owing:(CFR: 41.7/45.6)

4.4

4.6 0 0 ~ 0 0 0 0 0 0 [J D

Knowledge of the effect that a loss or

malfunction of the (SYSTEM) will have on

the foliowing:(CFR: 41.7/45.6)

Page 30t5

Bases for RCS cooldown limits

RCS

411/2008 2:09 PM

ES-401, REV 9

Emergency Diesel Generator

NAME / SAFETY FUNCTION:

061K5.03

AuxiliarylEmergency Feedwater

062K1.02

AC Electrical Distribution

063G2.4.S

DC Electrical Distribution

064A 1.02

_._--_._. __ ._-- -----

064K1.D4

Emergency Diesel Generator

073A4.02

Process Radiation Monitoring

,

DRAFT

]

T2G1 PWR EXAMINATION OUTLINE

IR

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

2.6

2.9 0 0 0 0 ~ 0 0 0 0 0 0

Knowledge of the operational implications

of the following concepts as they apply to

the (SYSTEM):(CFR: 41.5/45.7)

4.1

4.4

~ 0 0 0 0 0 0 0 0 0 0

Knowledge of the physical connections

and/or cause-effect relationships between

(SYSTEM) and the following:(CFR: 41.2 to

41.9/45.7 to 45.S)

3.S

4.5 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is

associated.

2.5

2.S 0 0 0 0 0 0 ~ 0 0 0 0

Ability to predict and/or monitor changes in

parameters associated with operating the

(SYSTEM) controls including:(CFR: 41.5/

45.5)

3.6

3.9

~ 0 0 0 0 0 0 0 0 0 0

Knowledge of the physical connections

and/or cause-effect relationships between

(SYSTEM) and the following:(CFR: 41.2 to

41.9/45.7 to 45.S)

3.7

3.7 0 0 0 0 0 0 0 0 0 ~ 0

Ability to manually operate and/or monitor

in the control room :(CFR: 41.7 1 45.5 to

45.S)

Service Water

.--:--:---,-----

_.

2.9

2.9 0 0 0 0 0 0 0 0 0 ~ 0

076A4.01

Ability to manually operate and/or monitor

in the control room:(CFR: 41.7/45.5 to

45.S)

Page 40f 5

FORM ES-401-2

TOPIC:

Pump head effects when control valve is shut

ED/G

~---.--~.~-

Knowledge of how abnormal operating procedures are

used in conjunction with EOPs.

Fuel consumption rate with load

DC distribution system

Radiation monitoring system control panel

SWSpumps

4I1/2OOS 2;09 PM

ES-401, REV 9

NAME / SAFETY FUNCTION:

078K2.02

Instrument Air

--_._._-----_

.. _- ----

103A1.01

Containment

I

D~FT J

T2G1 PWR EXAMINATION OUTLINE

IR

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

AO

SAO

3.3

3.5 0 ~ 0 0 0 0 0 0 0 0 0

Knowledge of electrical power supplies to

the foliowing:(CFA: 41.7)

FORM ES-401-2

TOPIC:

Emergency air compressor

--=:---_._-----_._----------_.

3.7

4.1

0 0 0 0 0 0 ~ 0 [J 0 0

Containment pressure, temperature and humidity

Ability to predict andlor monitor changes in

parameters associated with operating the

(SYSTEM) controls including:(CFA: 41.5/

45.5)

Page 50f 5

4/1/2008 2:09 PM

ES-401, REV 9

NAME I SAFETY FUNCTION:

011Kl.02

Pressurizer Level Control

014KS.02

Rod Position Indication

01SK3.04

Nuclear Instrumentation

_._ .. _----_ .. - ... ------

016K4.01

Non-nuclear Instrumentation

-::----,--_._----------:----

017 A3.02

In-core Temperature Monitor

[

DRAFT

I

T2G2 PWR EXAMINATION OUTLINE

IR

Kl K2 K3 K4 KS K6 Al A2 A3 A4 G

3.7

3.8

~ 0 0 0 0 0 0 0 0 0 0

Knowledge of the physical connections

and/or cause-effect relationships between

(SYSTEM) and the following:(CFR: 41.2 to

41.9/ 4S.7 to 45.8)

2.8

3.3 0 0 0 0 ~ 0 0 0 0 0 0

Knowledge of the operational implications

of the following concepts as they apply to

the (SYSTEM):(CFR: 41.5/45.7)

3.4

4.0 0 0 ~ 0 0 0 0 0 0 0 0

Knowledge of the effect that a loss or

malfunction of the (SYSTEM) will have on

the foliowing:(CFR: 41.7/45.6)

2.8

2.9 0 0 0 ~ 0 0 [J 0 0 0 0

Knowledge of (SYSTEM) design feature(s)

and or interlock(s) which provide for the

followlng:(CFR: 41.7)

FORM ES-401-2

TOPIC:

RCS

RPIS independent of demand position

ICS.

--:-~-:-=--C-'--------'"

--.. -.---

Reading of NNIS channel values outside control room

3.4

3.1

[J 0 0 0 0 0 0 0 ~ [j-O--M-easurement of in-core thermocouple temperatures at --

Ab'I'ty to*

.

f

panel outside control room

II

momtor automatIc operatIons 0

the (SYSTEM) including:(CFR: 41.7/ 4S.5)

:-------:c-,.--=--=---::~-==--:=_=:-.. ----.-

.

Containment Iodine Removal

3.1

3.4 0 ~ 0 0 0 0 0 0 0 0 0

Fans

027K2.01

.:c:-::-...,.-:---,---.--------.... -----

03SK6.02

Steam Generator

Knowledge of electrical power supplies to

the foliowing:(CFR: 41.7)

R

______

- _

_ ** _ _ _ _ _ _ _ _ _ _

__ ~ _______ ._._

3.1

3.S DOD 0 0 ~ 0 0 DOD

SecondaryPORV

Knowledge of the effect that a loss or

malfunction of the following will have on

the (SYSTEM):(CFR: 41.7/45.7)

Page 1 of 2

4/1/2008 2:09 PM

[

DRAFT

]

ES-401, REV 9

T2G2 PWR EXAMINATION OUTLINE

NAME I SAFETY FUNCTION:

IR

K1 K2 K3 K4 KS K6 A 1 A2 A3 A4 G

041A1.02

Steam DumpfTurbine Bypass Control

3.1

3.2 0 0 0 0 0 0 ~ 0 0 0 0

Ability to predict and/or monitor changes in

parameters associated with operating the

(SYSTEM) controls including:(CFR: 41.51

45.5)

FORM ES-401-2

TOPIC:

Steam pressure

045G2.1.25 ---Main Turbine Generator

-i94.2D Dod 0 0-0 0 0 -0 ~ . Ability to-interpret refe-renee materials* such as gra:p~--

Th..

G

.

monographs and tables which contain performance data.

IS IS a enenc, no stem statement IS

associated.

071A4.16 ---Waste GaS-Disposal ---2:52.2-*0000 0 0 0 0 D--~~-*-Waste gas decay tariksh~--------'--"'--"

Ability to manually operate and/or monitor

in the control room:(CFR: 41.7 1 45.5 to

45.8)

Page 2 of 2

411/2008 2:09 PM

r DRAFT

I

ES-401, REV 9

T3 PWR EXAMINATION OUTLINE

NAME I SAFETY FUNCTION:

IR

Kl K2 K3 K4 K5 K6 A1 A2 A3 A4 G

G2.1.14

Conduct of operations

3.1

0 0 0 0 0 0 0 0 0 0 ~

-=-=--c-c-----::::-~ .. -

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

G2.1.3

Conduct of operations

3.7

3.9 [J 0 0 [J 0 0 0 0 0 0 ~

M __

"~ ______

' ___

' __

' _____ **

G2.1.37

Conduct of operations

4.3

4.6 0 0 0 0 0 0 0 0 0 0 ~

G2.2.13

Equipment Control

4.1

4.3 0 0 0 0 0 0 0 0 0 0

l~

-,,_.---_ .. _--

" -

G2.2.37

Equipment Control

3.6

4.6 0 0 0 0 0 0 [J 0 0 0 ~

G2.3.11

Radiation Control

3.8

4.3 0 0 0 0 0 0 0 0 0 Cl ~

3

~

FORM ES-401;t' IO/1.'iloS

>>

TOPIC:

Knowledge of criteria or conditions that require plant-wide

announcements, such as pump starts, reactor trip, mode

changes, etc.

._ .... _

....... -_._._---

Knowledge of shift or short term relief tumover practices.

---...... _""-_ ... - .. _--

_._ .. _-._-_._. , .. _- ----~

Knowledge of procedures, guidelines or limitations

associated with reactivity management

,-_

.... -.-.. - .*. -.~----- .... --.-..

Knowledge of tagging and clearance procedures.

Ability to determine operability andlor availability of safety

related equipment

..,.-:---::--::---: *. __ ._._ ... _-----

Ability to control radiation releases.

.. - .... _

.... __ ... _-_ ... _. __ .... _--_.-,-----_.

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

_ .. _--_.-._._--_.

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

G2.3.4

Radiation Control

3.2

3.7 0 0 0 0 0 0 0 0 0 0 ~

Knowledge of radiation exposure limits under normal and

-

.

emergency conditions

Page 1 of 2

411/2008 2:09 PM

\\

DRAFT

I

ES-401, REV 9

T3 PWR EXAMINATION OUTLINE

NAME / SAFETY FUNCTION:

IR

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

G2.4.13

Emergency Procedures/Plans

4.0

4.6 DOD

0

DDDD~

G2.4.23

Emergency Procedures/Plans

3.4

4.4 0 0 [J 0 0 0 0 0 0 0 ~

G2.4.38

Emergency Procedures/Plans

2.4

4.4 0 0 0 0 0 0 []

DD~

Page 2 of 2

TOPIC:

3

FORM ES-401! ~

IO/'2.f:\\ /tJS

Knowledge of crew roles and responsibilities during EOP

usage.

Knowledge of the bases for prioritizing emergency

procedure implementation during emergency operations.

Ability to take actions called for in the tacillty emergency

plan, including supporting or acting as emergency

coordinator.

4/1/2008 2:09 PM

(

DRAFT

1

ES-401, REV 9

SRO T1Gl PWR EXAMINATION OUTLINE

FORM ES-401-2

NAME I SAFETY FUNCTION:

IR

Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G

TOPIC:

008AG2.4.2

Pressurizer Vapor Space Accident I 3

4.5

4.6 0 0 0 0 0 0 0 0 0 0 ~

Knowledge of system set points, interlocks and automatic

actions associated with EOP entry conditions.

009EA2.37

Small Break LOCA 13

011EA2.14

Large Break LOCA 13

015AA2.01

RCP Malfunctions I 4

_

.... _------ ---'

022AG2.1.28

Loss of Rx Coolant Makeup I 2

077AG2.4.45

Generator Voltage and Electric Grid

Disturbances I 6

This is a Generic, no stem statement is

associated.

-=,-----:==---c: ---.-------------

4.2

4.5 0 0 0 0 0 0 0 ~ 0 0 0

Existence of adequate natural circulation

Ability to determine and interpret the

following as they apply to (EMERGENCY

PLANT EVOLUTION):(CFR: 41.10/43.51

45.13)

_._---

---_ .. _---_.-

3.6

4

o 0 0 0 0 0 0 ~ 0 [J 0

Actions to be taken if limits for PTS are violated

Ability to determine and interpret the

following as they apply to (EMERGENCY

PLANT EVOLUTION):(CFR: 41.10 I 43.51

45.13)

3

3.5 0 0 0 0 0 0 0 ~ 0 0 0

C:'-a-u-se-o--:f-=R=-=C-=P 'failure---'---

.. _ ..... --_ .. _-.-

4.1

4.3

Ability to determine and interpret the

following as they apply to ABNORMAL

PLANT EVOLUTION):(CFR: 41.10/43.51

45.13)

--~-

---

DDDDDDDD[JD~

This is a Generic, no stem statement is

associated.

_

.. _- ... _-----._--.-----------

Knowledge of the purpose and function of major system

components and controls.

o 0 0 0 0 0 0 0 0 0 ~ -'--Ability to prioritize and interpretihe significanceo{each

-

annunciator or alarm.

This is a Generic, no stem statement is

associated.

Page 1 of 1

4/1/2008 2:10 PM

ES-401, REV 9

NAME I SAFETY FUNCTION:

OG8AG2.4.47

Control Room Evac. 18

I

DRAFT

I

SRO T1G2 PWR EXAMINATION OUTLINE

IR

K1 K2 K3 K4 K5 KG A1 A2 A3 A4 G

4.2

4.2 [J 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is

associated.

FORM ES-401-2

TOPIC:

Ability to diagnose and recognize trends in an accurate

and timely manner utilizing the appropriate control room

reference material.

_ .... ---_

...... _---_ ... -

.-

-

-:-::---_ .. __ ._----_.-.-------_ .. --_._-

076AA2.04

High Reactor Coolant Activity 19

2.6

3

0 [J 0 0 [] 0 0

~J DOD

Process effluent radiation chart recorder

_____

~~q~~, 0 ~ __________ _

weOl EG2.4.1 , Rediagnosis 13

4.0

4.2

Ability to determine and interpret the

following as they apply to ABNORMAL

PLANT EVOLUTION):(CFR: 41.10/43.51

45.13)

--_._-_

.. _--_._-_._----------

o 0 DOD 0 0 0 lJ 0 ~

Knowledge of abnormal condition procedures.

This is a Generic, no stem statement is

associated.

WE16EA2THigh ContainmeOt--Radiationi9

2~9-*--3.3 0-0' 0 0 -0 0 D-~ DOD

Facility cond~ions and-selection ofappropriate----*----

-

procedures during abnormal and emergency operations.

Ability to determine and interpret the

following as they apply to (EMERGENCY

PLANT EVOLUTION):(CFR: 41.10143.51

45.13)

Page 1 of 1

4/1/2008 2:10 PM

ES-401, REV 9

NAME I SAFETY FUNCTION:

003A2_03

Reactor Coolant Pump

026G2.4.20

Containment Spray

_ .... __ ... _.,.- .

._.---------_.

039A2.01

Main and Reheat Steam

l

DRAFT

I

SRO T2G1 PWR EXAMINATION OUTLINE

IR

Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G

2.7

3.1

0 0 0 0 0 0 0 ~ 0 0 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: 41.51 43.51 45_3145.13)

3.8

4.3 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is

associated .

.. _----------_

.. -=-=--

3.1

3.2 0 0 0 D' 0 0 0 ~ 0 0 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: 41.5/43.5/45.3/45.13)

_._._------._

... _-------

062G2.4.16

AC Electrical Distribution

3.3

4.0 0 0 0 0 0 0 0 0 0 [J ~

This is a Generic, no stem statement is

associated.

FORM ES-401-2

TOPIC:

Problems associated with RCP motors, including faulty

motors and current, winding and bearing temperature

problems

---,-,---:-:---------------

Knowledge of operational implications of EOP warnings,

cautions and notes.

Flow paths of steam during a LOCA

Knowledge of the specific bases for EOPs.

-_. __ .. _---

_._._----_ ... _---------------_ .. _----

076A2.02

Service Water

2.7

3.1

0 0 0 0 0 0 0 ~ 0 0 0

Service water header pressure

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: 41.5/43.5/45.3/45.13)

Page 1 of 1

4/1/2006 2:10 PM

ES-401, REV 9

NAME I SAFETY FUNCTION:

05002.4.49

Condenser Air Removal

071A2.05

Waste Gas Disposal

072A2.02

Area Radiation Monitoring

DRAFT

I

SRO T2G2 PWR EXAMINATION OUTLINE

IR

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

4.6

4.4 0 D DOD 0 DOD D ~

This is a Generic, no stem statement is

associated.

.---

--.-.... ---------_.

2.5

2.6 0 D D D D [] 0 ~ D D D

Ability to (a) predict the impacts of the

following on the (SYSTEM) and (b) based

on those predic1ions, use procedures to

correct, control, or mitigate the

consequences of those abnormal

operation:(CFR: 41.5/43.5/45.3/45.13)

2.8

2.9 DOD D D D 0 ~ D D D

Ability to (a) predict the impacts of the

following on the (SYSTEM) and (b) based

on those predic1ions, use procedures to

correct, control, or mitigate the

consequences of those abnormal

operation:(CFR: 41.5/43.5/45.3/45.13)

Page 1 of 1

FORM ES-401-2

TOPIC:

Ability to perform without reference to procedures those

actions that require immediate operation of system

components and controls.

Power failure to the ARM and PRM Systems

Detector failure

411/2008 2:10 PM

DRAFT

I

ES-401, REV 9

SRO T3 PWR EXAMINATION OUTLINE

3

FORM ES-4011 ~

IOI'2.~/o"

NAME / SAFETY FUNCTION:

IR

K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G

TOPIC:

G2.1.25

Conduct of operations

3.9

4.2 0 0 0 0 0 0 0 0 0 0 ~

Ability to interpret reference materials such as graphs,

monographs and tables which contain performance data.

G2:2~21----- EquipmentCOntrol----------*-

2.9

4.1

0 0 0 0 0 0 0 0 0 0 ~

Knowledge of pre- and post-maintenance operability

requirements.

G2.2.6

G2.3.13

G2.3.14

G2.4.27

Equipment Control

Radiation Control

3.0

3.6

[] 0 0 0 0 0 0 [J 0 0 ~

-

._---_ .... __ .. __ .-

Knowledge of the process for making changes to

procedures

.. _--_._-------

- -- _

.. -

_ .. _. -.,-----:---,.-

3.4

3.8 0 0 0 0 0 0 0 0 0 0 ~

Knowledge of radiological safety procedures pertaining to

...

.

licensed operator duties

3.4

3.8 0 0 0 0 0 0 0 0 0 0 ~

Knowledge of radiation or contamination hazards that

may arise during normal, abnormal, or emergency

conditions or activities

Emergency'Proc;;i;iures/Plans

3.4

3.9 [J 0 0 0 0 0 0 0 0 0 -~--KnOWledge of -fire in the-picint- procedures.

G2A-:-28---~ergency Procedures/Plans

3.2

4.1

0 0 0 [1 [1 0 0 0 D-Ei-~Knowledgeoi proCedures relating to emergency

response to sabotage.

Page 1 of 1

411/2008 2:10 PM

ES-401

Record of Rejected KI As

Form ES-401-4

Sequoyah 2009 RO exam

Tier /

Randomly

Reason for Rejection

Group

Selected KIA

111

062 AK3.04

Service water discharge header flow effected by loss of CCW.

Difficulty in writing a quality question because losing CCW would

only cause less heat transfer to the ERCW and the discharge header

flow would be the same.

Replaced by Chief Examiner on 09/02/08 with KA 062 AK3.03

211

004 A3.16

This KJA is similar to 024 AA2.01 which was also selected for the

exam.

Replaced by Chief Examiner on 09/02/08 with KA 004 A3.11

2/2

017 A3.02

Measurement ofIncore thermocouples outside MCR ..

Thermocouples can be read outside MCR via the PEDS programs

on desktop computers. Difficult to write a quality question.

Replaced by Chief Examiner on 09/02/08 with KA 017 A3.01

3

G2.4.38

The KJA importance rating is 2.4 (less than 2.5)

Replaced by Chief Examiner on 09/02/08 with KA G2.4.39

DRAFT

]

ES-401

Record of Rejected KlAs

Form ES-401*4

Sequoyah 2009 SRO exam

Tier /

Randomly

Reason for Rejection

Group

Selected K/ A

112

076AA2.04

No process effluent radiation chart recorder for RCS activity

Replaced by Chief examiner on 09/02/08 with KA 076 AA2.02

2/2

055 G2.4.9

No immediate operator actions for condenser air removal system

unless can write question relating to turbine trip criteria.

Replaced by Chief examiner on 09/02/08 with KA 055 G2.4.3

I

DRAFT

I

Outline Development Methodology

Outlines for the Sequoyah Nuclear Plant - Reactor and Senior Reactor Operator Initial

Examinations- 0500032712009301 and 0500032812009301 written examinations were

developed by the NRC.

I

DRAFT

J

Administrative Topics Outline

Form ES-301-1

Facility:

Sequovah 1 & 2

Date of Examination:

1/2009

Examination Level: RO 0

SRO 0

Operating Test Number:

NRC

Administrative Topic

Type

Describe activity to be performed

(see Note)

Code*

2.1.5 Ability to use procedures related to shift staffing,

Conduct of Operations

M,R

such as minimum crew complement, overtime

limitations, etc. 2.9* 13.9

JPM: Evaluate Overtime Requirements

2.1.23 Ability to perform specific system and integrated

Conduct of Operations

D,R

plant procedures during all modes of plant

operation. 4.3/4.4

JPM: Calculate Manual Makeup to the Volume

Control Tank (JPM 005)

2.2.12 Knowledge of surveillance procedures.

Equipment Control

N,S

3.7/4.1

JPM: Perform Monthly Shift Log 0-SI-OPS-000-003.M

2.3.7 Ability to comply with radiation work permit

Radiation Control

M,R

requirements during normal or abnormal

conditions. 3.5/3.6

JPM: 2A RHR Heat Exchanger Radiological Work

Permit and Survey Map Usage (JPM 180)

Emergency Procedures/Plan

N/A

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

retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom

(D)irect from bank (::; 3 for ROs; ::; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2: 1)

(P)revious 2 exams (::; 1; randomly selected)

f = ;~--l

-RO Admin JPM Summary

A1a

Determine when conditions exist that requires approval to exceed work hour restrictions.

Modified JPM

A 1 b

Perform calculation of the correct amount of water and boric acid required to manually

raise the level in the VeT. Bank JPM

A2

Perform a portion of Monthly Shift Log surveillance instruction 1-SI-OPS-OOO-003.M and

recognize inoperable instruments. New JPM

A3

Using a survey map and radiological work permit, determine conditions in the room and

the required dose monitoring and protective clothing required while inside the room.

Modified JPM

A4

Not Applicable

Administrative Topics Outline

Form ES-301-1

Facility:

Seguotah 1 & 2

Date of Examination:

1/2009

Examination Level: RO D

SRO 0

Operating Test Number:

NRC

Administrative Topic

Type

Describe activity to be performed

(see Note)

Code*

2.1.5 Ability to use procedures related to shift staffing,

Conduct of Operations

M,R

such as minimum crew complement, overtime

limitations, etc. 2.9* 1 3.9

JPM: Evaluate Overtime Requirements

2.1.23 Ability to perform specific system and integrated

Conduct of Operations

D,R

plant procedures during all modes of plant

operation. 4.3/4.4

JPM: Calculate Manual Makeup to the Volume

Control Tank. (JPM 005)

2.2.12 Knowledge of surveillance procedures.

Equipment Control

D,R

3.7/4.1

JPM: Review a completed surveillance for accuracy.

(JPM 175 AP)

2.3.11

Ability to Approve Release Permits.

3.8/4.3

Radiation Control

N,R

JPM: Approval of a Waste Gas Decay Tank Release.

2.4.38

Ability to take actions called for in the facility

Emergency Procedures/Plan

emergency plan, including supporting or acting

D,S

as emergency coordinator if required. 2.4/4.4

JPM: Classify the Event per the REP (Primary

System Leakage with Potential Loss of Cntmt).

(JPM #18)

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

retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom

(D)irect from bank (S 3 for ROs; S 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (<:: 1)

(P)revious 2 exams (s 1; randomly selected)

]

SRO Admin JPM Summary

A 1 a

Determine when conditions exist that requires approval to exceed work hour restrictions.

Modified JPM.

A1 b

Perform calculation to manually raise the level in the VCT. Bank JPM

A2

Review a surveillance instruction for Shutdown margin and identify the incorrect Tavg

was entered into the calculation. Bank JPM #175-AP.

A3

Determine requirements for releasing a Waste Gas Decay Tank including hold-up time

requirements, approval required in outside normal release hours, requirements with

radiation monitor out of service and requirement if monitor is not repaired in identified

ODCM time. New JPM

A4

Evaluate plant conditions for E-Plan entry, classification, and required notifications in

accordance with Radiological Emergency Plan procedures. Bank JPM #18.

[= DRA~ J

Control Room/In-Plant Systems Outline

Form ES-301-2

Facility:

Seguoyah 1 & 2

Date of Examination:

1/2009

Exam Level: RO 0

SRO-ID

SRO-U 0

Operating Test No.:

NRC

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System 1 JPM Title

Type Code*

Safety

Function

a.

001 Control Rod Drive System (A2.11 4.4/4.7)

Perform 0-SI-OPS-085-011.0

N,A,S

1

b.

003 Reactor Coolant Pump System (A2.03 2.7/3.1)

Start #1 RCP in Mode 3 (182-AP)

D,A,L,S

4P

c.

E02 SI Termination (EA1.1 4.0/3.9)

Terminate SI and Re-establish Charging Flow

M,A,S

3

(JPM 027)

d.

040 Steam Line Rupture (AA2.01 4.2/4.7)

Faulted SG Isolation with MSIV Stuck Open (JPM 058-AP2)

M,A,S

4S

e.

064 Emergency Diesel Generators (A1.08 3.1/3.4)

Perform DIG Load Test on 1 B-B DIG (JPM 077)

D,S

6

f.

028 Hydrogen Recombiner and Purge Control System (A4.03 3.1/3.3)

Place 1 B H2 Analyzer in Service

D,S

5

g.

008 Component Cooling Water System (A3.02 3.2/3.2)

D,S

8

Swap Thermal Barrier Booster Pumps (JPM 073)

h.

015 Nuclear Instrumentation System (A4.02 3.9/3.9)

Reinstate Source Range Detectors (JPM 119-AP)

D,A,L,S

7

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

i.

004 Chemical and Volume Control System (A2.14 3.8/3.9)

Perform Boration of RCS from Outside MCR (JPM 006)

D,E,R

1

j.

062 Loss of Nuclear Service Water (AK3.03 4.0/4.2)

D,E,R

4S

Installation of Temporary Cooling (HPFP) to CCP 1 A-A or 1 B-B Oil

Coolers

k.

064 Emergency Diesel Generators (K1.05 3.4/3.9)

Align Starting Air for Service on 2A-A DIG (JPM 023-2)

D

6

@

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety

functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may

overlap those tested in the control room.

DRAFT ]

Type Codes

Criteria for RO / SRO-I / SRO-U

(A)lternate path

4-6/4-6/2-3

(C)ontrol room

(D)irect from bank

59/:58/:54

(E)mergency or abnormal in-plant

1/;

:1/;::1

(EN)gineered safety feature

- / - / ;::1 (control room system)

(L)ow-Power / Shutdown

1/;

:1/;::1

(N)ew or (M)odified from bank including 1 (A)

2/;

:2/;::1

(P)revious 2 exams

5 3 / :5 3 / :5 2 (randomly selected)

(R)CA

1/;

:1/;::1

(S)imulator

JPM Summary

A. The rod exercise surveillance instruction will be performed for 2 banks of control rods. During

the second bank movement, the rod will being moving without a demand and result in a trip of

the reactor being required. New alternate path JPM

B. With the plant in Mode 3 and the other RCPs already running, RCP #1 will be placed in service.

After starting RCP #1 will experience high stator winding temperatures which will require the

pump to be stopped. Bank alternate path low power JPM.

C. With the shutdown boards being powered from the diesel generator, the steps to terminate

ECCS flow and to re-establish charging flow in accordance with ES-1 .1 , SI Term ination will be

required. JPM will require using procedure RNOs to lock out a charging pump and to address

the failure of the normal charging valve to open. Bank modified alternate path JPM.

D. Response to a faulted SG with a stuck open MSIV will require completing steps to identify and

isolate the faulted SG in accordance with E-2, Faulted Steam Generator Isolation. Bank

modified alternate path JPM.

E.

An operability test of DIG 1 B-B will require manually starting and loading the DIG in accordance

with 1-SI-OPS-082-007.B, Electrical Power System Diesel Generator 1 B-B. Bank JPM.

F.

1 B Hydrogen analyzer will be restored to service following maintenance in accordance with the

system operating instruction. Bank JPM

G. Swapping thermal barrier booster pumps will require starting the 1 A-A pump and securing the

1 B-B pump in accordance with 1-S0-70-1, Component Cooling Water System "A" Train. Bank

H. A failed Intermediate Range channel will require manually reinstating Source Range detectors

following a reactor trip in accordance with ES-0.1, Reactor Trip Response. Bank alternate path

I.

Evacuation of the Main Control Room will require manually borating the RCS using the

emergency boration valve in accordance with AOP-C.04, Control Room Inaccessibility. Bank

J.

The locations, connections, and alignment required to establish temporary cooling to CCP-1A-A

in accordance with AOP-M.01 due to a loss of ERCW. Bank JPM

K.

Completion of maintenance work on the 2A-A DIG starting air system will require aligning the

system for service in accordance with 0-SO-82-7, Diesel Generator 2A-A Support Systems.

Bank JPM.

Control Room/In-Plant Systems Outline

Form ES-301-2

Facility:

Seguoyah 1 & 2

Date of Examination:

1/2009

Exam Level: RO D

SRO-I 0

SRO-U D

Operating Test No.:

NRC

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title

Type Code*

Safety

Function

a.

001 Control Rod Drive System (A2.11 4.4/4.7)

Perform 0-SI-OPS-085-011.0

N,A,S

1

b.

003 Reactor Coolant Pump System (A2.03 2.7/3.1)

Start #1 RCP in Mode 3 (182-AP)

D,A,S

4P

c.

E02 SI Termination (EA1.1 4.0/3.9)

Terminate SI and Re-establish Charging Flow

M,A,S

3

(JPM 027)

d.

040 Steam Line Rupture (AA2.01 4.2/4.7)

Faulted SG Isolation with MSIV Stuck Open (JPM 058-AP2)

M,A,S

4S

e.

064 Emergency Diesel Generators (A1.08 3.1/3.4)

Perform D/G Load Test on 1 B-B D/G (JPM 077)

D,S

6

f.

028 Hydrogen Recombiner and Purge Control System (A4.03 3.1/3.3)

Place 1 B H2 Analyzer in Service

D,S

5

g.

NOT USED for SRO-I

h.

015 Nuclear Instrumentation System (A4.02 3.9/3.9)

Reinstate Source Range Detectors (JPM 119-AP)

D,A,L,S

7

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

i.

004 Chemical and Volume Control System (A2.14 3.8/3.9)

Perform Boration of RCS from Outside MCR (JPM 006)

D,E,R

1

j.

062 Loss of Nuclear Service Water (AK3.03 4.0/4.2)

D,E,R

4S

Installation of Temporary Cooling (HPFP) to CCP 1 A-A or 1 B-B Oil

Coolers

k.

064 Emergency Diesel Generators (K1.05 3.4/3.9)

Align Starting Air for Service on 2A-A D/G (JPM 023-2)

D

6

@

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety

functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may

overlap those tested in the control room.

I

Type Codes

I

Criteria for RO / SRO-I / SRO-U

I

DRAFT

(A)lternate path

(C)ontrol room

(D)irect from bank

(E)mergency or abnormal in-plant

(EN)gineered safety feature

(L)ow-Power 1 Shutdown

]

(N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams

(R)CA

(S)imulator

JPM Summary

4-6 1 4-6 1 2-3

S9/s8/s4

~1/~1/~1

- 1 - 1 ~1 (control room system)

~1/~1/~1

~2/~2/~1

s 3 1 s 3 1 s 2 (randomly selected)

~1/~1/~1

A. The rod exercise surveillance instruction will be performed for 2 banks of control rods. During

the second bank movement, the rod will being moving without a demand and result in a trip of

the reactor being required. New alternate path JPM

B. With the plant in Mode 3 and the other RCPs already running, RCP #1 will be placed in service.

After starting RCP #1 will experience high stator winding temperatures which will require the

pump to be stopped. Bank alternate path low power JPM.

C. With the shutdown boards being powered from the diesel generator, the steps to terminate

ECCS flow and to re-establish charging flow in accordance with ES-1.1, SI Termination will be

required. JPM will require using procedure RNOs to lock out a charging pump and to address

the failure of the normal charging valve to open. Bank modified alternate path JPM.

D. Response to a faulted SG with a stuck open MSIV will require completing steps to identify and

isolate the faulted SG in accordance with E-2, Faulted Steam Generator Isolation. Bank

modified alternate path JPM.

E. An operability test of DIG 1 B-B will require manually starting and loading the DIG in accordance

with 1-SI-OPS-082-007.B, Electrical Power System Diesel Generator 1 B-B. Bank JPM.

F.

1 B Hydrogen analyzer will be restored to service following maintenance in accordance with the

system operating instruction. Bank JPM

G. not used

H. A failed Intermediate Range channel will require manually reinstating Source Range detectors

following a reactor trip in accordance with ES-0.1, Reactor Trip Response. Bank alternate path

I.

Evacuation of the Main Control Room will require manually borating the RCS using the

emergency boration valve in accordance with AOP-C.04, Control Room Inaccessibility. Bank