ML090710630
| ML090710630 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/04/2009 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-327/09-301, 50-328/09-301 IR-09-301 | |
| Download: ML090710630 (31) | |
See also: IR 05000327/2009301
Text
I DRAFT I
E8-401, Rev. 9 PWR examination Outline
Facility: Oate of Exam:
i
I
I RO KIA Category Points SRO-Only Points
I
Tier Group II
I
K
1
K
2
K
3
K
4
K
5
K
6
A
1
A
2
A
3
A
4
G
- Total
A2 G* Total
II
1. 1 3 3 3 3 3 3 18 3 3 6
Emergency & 2 2 2 4
2 2 1 2 1 1 9
Abnormal Plant N/A N/A
Evolutions Tier Totals 5 4 5 5 4 4 27 5 5 10
1 3 3 3 2 3 2 3 2 3 2 2 28 3 2 5
2.
2 1 1 1 1 1 1 1 0 1 1 1" 10 2 1 3
Plant
Systems Tier Totals 4 4 4 3 4 3 4 2 4 3 3 38 5 3 8
I
3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7
Categories
3 2 2 3 1 2 2 2
1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO
and SRO-only outlines (i.e., except for one category In Tier 3 of the SRO-only outline, the "Tier Totals"
I
in each KIA category shall not be less than two).
2. 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 +/- 1 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.
3. Systems/evolutions within each group are Identified on the associated outline; systems or evolutions that do
not apply at the facility should be deleted and justified; operationally important, site-specific systems that are
not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding
the elimination of inappropriate KIA statements.
I
! 4. Select topics from as many systems and evolutions as possible; sample every system or evolution
I in the group before selecting a second topic for any system or evolution.
II 5. Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be
selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively. I
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7. *The generic (G) K/As In Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics
must-be relevant to the applicable evolution or system.
8. On the following pages, enter the KIA numbers, a brief deSCription of each topic, the topics' importance
ratings (IRs) for the applicable license level, and the point totals (tI) for each system and category. Enter
the group and tier totals for each category in the table above; If fuel handling equipment is sampled in other
I than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note
I tI 1 does not apply). Use duplicate pages for RO and SRO-only exams.
II
I
9. For Tier 3, select topiCS from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs,
and point totals (tI) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43. i
J
r-- DIIAFT I
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2
KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
007EK2.03 Reactor Trip - Stabilization - Recovery 3.5 3.6 D~LJDDlJD[J[JDD Reactor trip status panel
11
Knowledge of the interrelations between
(EMERGENCY PLANT EVOLUTION) and
the following:(CFR: 41.7 1 45.7 1 45.S)
--......*......*....... ~~~~~~~~~-
... ..----~
008AG2.4.45 Pressurizer Vapor Space Accident 1 3 4.1 4.3 0 0 0 0 II fJ 0 lJ ~ Ability to prioritize and interpret the significance of each
annunciator or alarm.
This is a Generic, no stem statement is
associated.
-~---.--~- ....- - -.~.-.. --.--.. -."-~-~.-- --.~--.-~
009EA2.10 Small Break LOCA 1 3 3.1 3.7 [] 0 00 D~ODD Airbome activity
Ability to determine and interpret the
following as they apply to (EMERGENCY
PLANT EVOLUTION):(CFR: 41.10/43.51
45.13)
015AA2.0S RCP Malfunctions I 4 3.4 3.5 0 [J 0 0 0 0 0 ~ 0 0 0 When to secure RCPs on high bearing temperature
Ability to determine and interpret the
following as they apply to ABNORMAL
PLANT EVOLUTION):(CFR: 41.101 43.5/
45.13)
~ ............. - ...- - . - -...----.......... ~~-
022AK1.02 Loss of Rx Coolant Makeup 1 2 2.7 3.1 ~ [J [J 0 0 0 0 0 0 0 0 Relationship of charging flow to pressure differential
between charging and RCS
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) Ability to analyze the effect of maintenance activities,
such as degraded power sources, on the status of
This is a Generic, no stem statement is limiting conditions of operations
associated.
Page 1 of 3 4/1/200S 2:09 PM
ES-401, REV 9
KA NAME I SAFETY FUNCTION: IR
[ !RAFT:
T1Gl PWR EX='NAfl8N
K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G
OI~"NJ TOPIC:
FORM ES-401-2
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
Ability to determine and interpret the abnormal condition
following as they apply to ABNORMAL
PLANT EVOLUTION):(CFR: 41.10/43.S/
45.13)
029EG2.1.31 ATWS /1 4.*6~--:-4-:::.3---:0=-0'*0--0-[]--[] DOD D ~ Ability to locate control room switches, controls and
indications and to determine that they are correctly
This is a Generic, no stem statement is reflecting the desired plant lineup.
associated.
- _ . - . - - - _... _._- -- _._------_... _------
040AK1.06 Steam Line Rupture - Excessive Heat 3.7 3.8 ~ 0 0 0 0 0 0 0 0 0 0 High-energy steam line break considerations
Transfer /4
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)
-_. __._--_Loss
... ------
054AK 1.02 of Main Feedwater / 4 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)
- -----
055EK2.04 Station Blackout / 6 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)
- - - - - _... - - - - - - -
056AA 1.11 Loss of Off-site Power 1 6 3.7 3.7 0 0 0 0 0 0 ~ 0 0 0 0 HPI system
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 4/1/2008 2:09 PM
ES-401, REV 9
~ ~~
T1G1 PWR EXAMINATION OUTLINE
I
FORM ES-401-2
KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2~A3'A4 G TOPIC:
057AK3.01 Loss of Vital AC Inst. Bus 16 4.1 4.4 0 0 ~ 0 0 0 0 0 0 [1 0 Actions contained in EOP for loss of vital ac electrical
instrument bus
Knowledge of the reasons for the following
responses as they apply to (ABNORMAL
PLANT EVOLUTION):(CFR: 41.5/41.101
45.6/45.13)
. . *_-----------
058AA1.01 Loss of DC Power 1 6 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
following as they apply to (ABNORMAL
PLANT EVOLUTION):(CFR: 41.7/45.5/
45.6)
_._--------------
062AK3.04 Loss of Nuclear Svc Water 1 4 3.5 3.7 o 0 ~ 0 0 0 0 0 0 0 0 Effect on the nuclear service water discharge flow header
of a loss of CCW
Knowiedge of the reasons for the following
responses as they apply to (ABNORMAL
PLANT EVOLUTION):(CFR: 41.5/41.101
45_6/45.13)
_065AK3.04
... -------_._-----------
Loss of Instrument Air / 8 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)
077AA1.03 Generator Voltage and Electric Grid 3.8 3.7 0 0 0 0 0 0 ~ 0 0 0 0 Voltatge regulator controls
Disturbances I 6
Ability to operate and I or monitor the
following as they apply to (ABNORMAL
PLANT EVOLUTION):(CFR: 41.7 I 45.51
45.6)
_.:----:-----::----
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
Knowiedge of the interrelations between modes and automatic and manual features.
(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
I DRAFT
T1G2 PWR EXAMINATION OUTLINE
J FORM ES-401-2
KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
001AK3.02 Continuous Rod Withdrawal/1 3.2 4.3 0 0 ~ 0 0 0 0 0 0 0 0 Tech-Spec limits on rod operability
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)
---- -----:--- --=----=-=_._-----
005AA 1.01 Inoperable/Stuck Control Rod 11 3.6 3.4 0 0 0 0 0 0 ~ 0 0 [J 0 CRDS
Ability to operate and 1 or monitor the
following as they apply to (ABNORMAL
PLANT EVOLUTION):(CFR: 41.7 I 45.51
45.6)
- -:-:----:7"-----------
024AA2.01 Emergency Boration /1 3.8 4.1 0 0 0 0 0 0 0 ~ 0 0 0 Whether boron flow and/or MOVs are malfunctioning
from plant conditions
Ability to determine and interpret the
following as they apply to ABNORMAL
PLANT EVOLUTION):(CFR: 41.10/43.51
45.13)
036AK3.0"1---Fuel Handling Accident I 8 3.1 3.7 [J 0 ~ 0 0 0 0 0 0 0 0 Different inputs that will cause a reactor building
evacuation
Knowledge of the reasons for the following
responses as they apply to (ABNORMAL
PLANT EVOLUTION):(CFR: 41.5/41.101
45.6/45.13)
059AK1.02 Accidental Liquid RadWaste ReI. 19 2.6 3.2 ~ 0 0 0 0 0 0 0 0 0 0 Biological effects on humans of various types of
radiation, exposure levels that are acceptable for nuclear
Knowledge of the operational implications power plant personnel and the units used for radiation-
of the following concepts as they apply to intenSity measurements and for radiation exposure levels
the (ABNORMAL PLANT
EVOLUTION):(CFR: 41.8 to 41.10 I 45.3)
.- ---.. --- - - - - - - - - - - --------- ----- ----------
067AG2.1.31 Plant Fire On-site I 9 8 4.6 4.3 0 0 0 [J 0 0 0 0 0 0 ~ Ability to locate control room switches, controls and
indications and to determine that they are correctly
This is a Generic, no stem statement is reflecting the desired plant lineup.
associated.
Page 1 of 2 411/2008 2:09 PM
[ DRAFT I
ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2
KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
WEOOEA 1.1 RCS Overcooling - PTS I 4 3.8 3.8 DDDDDD~DDDD Components and functions of control and safety systems,
including instrumentation, signals, interlocks, failure
Ability to operate and I or monitor the modes and automatic and manual features.
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 Components, capacity, and function of emergency
systems.
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 Components and functions of control and safety systems,
including instrumentation, signals, interlocks, failure
Knowledge of the interrelations between modes and automatic and manual features.
(EMERGENCY PLANT EVOLUTION) and
the following:(CFR: 41.7/45.7/45.8)
Page 2 of 2 4/1/2008 2:09 PM
ES-401, REV 9
[ DRAFT
T2Gl PWR EXAMINATION OUTLINE
J FORM ES-401-2
KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
003A1.04 Reactor Coolant Pump 2.6 2.5 0 0 0 0 0 0 ~ 0 0 0 0 RCP oil reservoir levels
Ability to predict and/or monitor changes in
parameters associated with operating the
(SYSTEM) controls including:(CFR: 41.5/
45.5)
_._------ --- _.'._-----------_ .*,----_.__.--------._----_._---_._---." ....._._--------
003K4.02 Reactor Coolant Pump 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 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)
- ------_._-----------------._- ---. - - - - - --=----:::---------_._--------------- -----------------------
006A3.06 Emergency Core COOling 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)
---=---- ----------------------------------------
007A2.05 Pressurizer Relief/Quench Tank 3.2 3.6 0 0 0 0 0 0 0 ~ 0 0 0 Exceeding PRT high-pressure limits
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
{ DRAFT ,
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2
KA NAME I SAFETY FUNCTION: IA K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC:
008A3.04 Component Cooling Water 2.9 3.2 0 0 0 0 0 0 0 0 ~ 0 0 Requirements on and for the CCWS for different condi-
tions of the power plant
Ability to monitor automatic operations of
the (SYSTEM) including:(CFR: 41.7 14S.5)
_._._-----_._-- - - - . , . - - . . ------------ .
008K1.04 Component Cooling Water 3.3 3.3 ~ 0 0 0 0 0 0 0 0 0 [] RCS, in order to determine source(s) of RCS leakage into
theCCWS
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)
010A2.01 Pressurizer Pressure Control 3.3 3.6 0 0 0 0 0 0 0 ~ 0 0 0 Heater failures
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)
,::-- ---,:--- ---------_.._----_.-----_.._.- -_._-----
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 ~ Ability to verify that the alarms are consistent with the
plant conditions.
This is a Generic, no stem statement is
associated.
_._. _-_. . .-..- ._- ---------==--==--==
022K4.03 Containment Cooling 3.6 4.0 0 0 0 ~ 0 0 0 0 0 0 0 Automatic containment isolation
Knowledge of (SYSTEM) deSign feature(s)
and or interlock(s) which provide for the
following:(CFR: 41.7)
Page20f 5 4/1/2008 2:09 PM
ES-401, REV 9
KA NAME / SAFETY FUNCTION: IR
TlGC::;:=~FlJ
K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401-2
025K502 Ice Condenser 2.6 2.8 0 0 0 0 ~ 0 0 0 0 0 0 Heat transfer
Knowledge of the operational implications
of the following concepts as they apply to
the (SYSTEM):(CFR: 41.5/45.7)
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
Knowledge of the effect that a loss or
malfunction of the following will have on
the (SYSTEM):(CFR: 41.7/45.7)
026K2.01 Containment Spray 3.4 3.6 0 ~ ODD D D DOD 0 Containment spray pumps
Knowledge of electrical power supplies to
the foliowing:(CFR: 41.7)
.".....-:=-=--==--=. _-_._. ._-------_._.._._-_._..
026K3.02 Containment Spray 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)
039K5.05 Main and Reheat Steam 2.7 3.1 DOD 0 ~ DOD DOD Bases for RCS cooldown limits
Knowledge of the operational implications
of the fol/owing concepts as they apply to
the (SYSTEM):(CFR: 41.5/45.7)
059K3.04 Main Feedwater 3.6 3.8 0 0 ~ 0 0 0 0 0 0 0 0 RCS
Knowledge of the effect that a loss or
malfunction of the (SYSTEM) will have on
the fol/owing:(CFR: 41.7/45.6)
061K3.01 Auxiliary/Emergency Feedwater 4.4 4.6 0 0 ~ 0 0 0 0 0 0 [J D RCS
Knowledge of the effect that a loss or
malfunction of the (SYSTEM) will have on
the foliowing:(CFR: 41.7/45.6)
Page 30t5 411/2008 2:09 PM
, DRAFT ]
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2
KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
061K5.03 AuxiliarylEmergency Feedwater 2.6 2.9 0 0 0 0 ~ 0 0 0 0 0 0 Pump head effects when control valve is shut
Knowledge of the operational implications
of the following concepts as they apply to
the (SYSTEM):(CFR: 41.5/45.7)
062K1.02 AC Electrical Distribution 4.1 4.4 ~ 0 0 0 0 0 0 0 0 0 0 ED/G
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)
~---.--~.~-
063G2.4.S DC Electrical Distribution 3.S 4.5 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of how abnormal operating procedures are
used in conjunction with EOPs.
This is a Generic, no stem statement is
associated.
064A 1.02 Emergency Diesel Generator 2.5 2.S 0 0 0 0 0 0 ~ 0 0 0 0 Fuel consumption rate with load
Ability to predict and/or monitor changes in
parameters associated with operating the
(SYSTEM) controls including:(CFR: 41.5/
45.5)
_._--_._. __._--Emergency Diesel Generator
064K1.D4 3.6 3.9 ~ 0 0 0 0 0 0 0 0 0 0 DC distribution system
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)
073A4.02 Process Radiation Monitoring 3.7 3.7 0 0 0 0 0 0 0 0 0 ~ 0 Radiation monitoring system control panel
Ability to manually operate and/or monitor
in the control room :(CFR: 41.7 1 45.5 to
45.S)
.--:--:---,----- _.
076A4.01 Service Water 2.9 2.9 0 0 0 0 0 0 0 0 0 ~ 0 SWSpumps
Ability to manually operate and/or monitor
in the control room:(CFR: 41.7/45.5 to
45.S)
Page 40f 5 4I1/2OOS 2;09 PM
ES-401, REV 9
I D~FT
T2G1 PWR EXAMINATION OUTLINE
J FORM ES-401-2
KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
078K2.02 Instrument Air 3.3 3.5 0 ~ 0 0 0 0 0 0 0 0 0 Emergency air compressor
Knowledge of electrical power supplies to
the foliowing:(CFA: 41.7)
--_._._-----_.._- - - - - --=:---_._-----_._----------_.
103A1.01 Containment 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)
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[ DRAFT I
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2
KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:
011Kl.02 Pressurizer Level Control 3.7 3.8 ~ 0 0 0 0 0 0 0 0 0 0 RCS
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)
014KS.02 Rod Position Indication 2.8 3.3 0 0 0 0 ~ 0 0 0 0 0 0 RPIS independent of demand position
Knowledge of the operational implications
of the following concepts as they apply to
the (SYSTEM):(CFR: 41.5/45.7)
01SK3.04 Nuclear Instrumentation 3.4 4.0 0 0 ~ 0 0 0 0 0 0 0 0 ICS.
Knowledge of the effect that a loss or
malfunction of the (SYSTEM) will have on
the foliowing:(CFR: 41.7/45.6)
_._ .. _----_ ..- ... - - - - - - --:-~-:-=--C-'--------'" --.. - . - - -
016K4.01 Non-nuclear Instrumentation 2.8 2.9 0 0 0 ~ 0 0 [J 0 0 0 0 Reading of NNIS channel values outside control room
Knowledge of (SYSTEM) design feature(s)
and or interlock(s) which provide for the
followlng:(CFR: 41.7)
017A3.02
-::----,--_._----------:----
In-core Temperature Monitor 3.4 3.1 [J 0 0 0 0 0 0 0 ~ [j-O--M-easurement of in-core thermocouple temperatures at - -
AbII'I'ty t o * . . f panel outside control room
momtor automatIc operatIons 0
the (SYSTEM) including:(CFR: 41.7/ 4S.5)
:-------:c-,.--=--=---::~-==--:=_=:- ..- - - - . - ------.
027K2.01 Containment Iodine Removal 3.1 3.4 0 ~ 0 0 0 0 0 0 0 0 0 Fans
Knowledge of electrical power supplies to
the foliowing:(CFR: 41.7)
- R _ _ _ _ _ _ ** _ _ ** _ _ _ _ _ _ _ _ _ _ * _ _ ~ _ _ _ _ _ _ _ . _ . _
- .:c:-::-...,.-:---,---.--------.... - - - - -
03SK6.02 Steam Generator 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 FORM ES-401-2
KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A 1 A2 A3 A4 G TOPIC:
041A1.02 Steam DumpfTurbine Bypass Control 3.1 3.2 0 0 0 0 0 0 ~ 0 0 0 0 Steam pressure
Ability to predict and/or monitor changes in
parameters associated with operating the
(SYSTEM) controls including:(CFR: 41.51
45.5)
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 .
IS IS a enenc, no stem statement IS
. monographs and tables which contain performance data.
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
ES-401, REV 9
KA NAME I SAFETY FUNCTION: IR
r DRAFT
T3 PWR EXAMINATION OUTLINE
I
Kl K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
FORM ES-401;t'
>>
3 ~
IO/1.'iloS
G2.1.14 Conduct of operations 3.1 3.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of criteria or conditions that require plant-wide
announcements, such as pump starts, reactor trip, mode
changes, etc.
-=-=--c-c-----::::-~ ..- ............ - .... --.-.--.. -.~ .. - - - - - - - ._...._.......-_._._---
G2.1.3 Conduct of operations 3.7 3.9 [J 0 0 [J 0 0 0 0 0 0 ~ Knowledge of shift or short term relief tumover practices.
M _ _ "~ _ _ _ _ _ _ ' _ _ _ ' _ _ ' _____ **
--- ...... _""-_... - .._-- _._.._-._-_._. .. _-
, ----~
G2.1.37 Conduct of operations 4.3 4.6 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of procedures, guidelines or limitations
associated with reactivity management
- - - - - - , - _.... -.-..- .*. -.~----- ....--.-..
G2.2.13 Equipment Control 4.1 4.3 0 0 0 0 0 0 0 0 0 0 l~ Knowledge of tagging and clearance procedures.
-,,_.---_.. _-- " -
G2.2.37 Equipment Control 3.6 4.6 0 0 0 0 0 0 [J 0 0 0 ~ Ability to determine operability andlor availability of safety
related equipment
..,.-:---::--::---:*. __._._..._ - - - - -
G2.3.11 Radiation Control 3.8 4.3 0 0 0 0 0 0 0 0 0 Cl ~ Ability to control radiation releases.
_
..- .... .... __ ... _-_...Radiation
_. __.... _--_.-,-----_. -.~-------.. _.._--_.-._._--_. --.---... -- .. -----~
G2.3.4 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
ES-401, REV 9
\ DRAFT
T3 PWR EXAMINATION OUTLINE
I FORM ES-401! ~
3
KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
IO/'2.f:\ /tJS
G2.4.13 Emergency Procedures/Plans 4.0 4.6 DOD 0 DDDD~ Knowledge of crew roles and responsibilities during EOP
usage.
G2.4.23 Emergency Procedures/Plans 3.4 4.4 0 0 [J 0 0 0 0 0 0 0 ~ Knowledge of the bases for prioritizing emergency
procedure implementation during emergency operations.
G2.4.38 Emergency Procedures/Plans 2.4 4.4 0 0 0 0 0 0 [] DD~ Ability to take actions called for in the tacillty emergency
plan, including supporting or acting as emergency
coordinator.
Page 2 of 2 4/1/2008 2:09 PM
( DRAFT 1
ES-401, REV 9 SRO T1Gl PWR EXAMINATION OUTLINE FORM ES-401-2
KA 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.
This is a Generic, no stem statement is
associated.
-=,-----:==---c: - - - . - - - - - - - - - - - - -
009EA2.37 Small Break LOCA 13 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)
_._--- ---_.._ - - - _ . -
011EA2.14 Large Break LOCA 13 3.6 4 o0 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)
C:'-a-u-se-o--:f-=R=-=C-=P 'failure---'--- .._ ..... --_.. _-.-
015AA2.01 RCP Malfunctions I 4 3 3.5 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)
- - - - _.... _ - - - - - - ---' --~- --- --------_.. _- ... _-----._--.-----------
022AG2.1.28 Loss of Rx Coolant Makeup I 2 4.1 4.1 DDDDDDDD[JD~ Knowledge of the purpose and function of major system
components and controls.
This is a Generic, no stem statement is
associated.
077AG2.4.45 Generator Voltage and Electric Grid 4.1 4.3 o 0 0 0 0 0 0 0 0 0 ~ -'--Ability to prioritize and interpretihe significanceo{each -
Disturbances I 6 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
I DRAFT
SRO T1G2 PWR EXAMINATION OUTLINE
I FORM ES-401-2
KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 KG A1 A2 A3 A4 G TOPIC:
OG8AG2.4.47 Control Room Evac. 18 4.2 4.2 [J 0 0 0 0 0 0 0 0 0 ~ Ability to diagnose and recognize trends in an accurate
and timely manner utilizing the appropriate control room
This is a Generic, no stem statement is reference material.
associated.
_....- - - _......_---_ ... - .- - -:-::---_ . __._----_.-.-------_..- - _ . _ -
076AA2.04 High Reactor Coolant Activity 19 2.6 3 0 [J 0 0 [] 0 0 ~J DOD Process effluent radiation chart recorder
Ability to determine and interpret the
following as they apply to ABNORMAL
PLANT EVOLUTION):(CFR: 41.10/43.51
45.13)
_____ ~~q~~, 0 ~ __________ _
weOl EG2.4.1 , Rediagnosis 13 4.0 4.2 o0 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
l DRAFT
SRO T2G1 PWR EXAMINATION OUTLINE
I FORM ES-401-2
KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
003A2_03 Reactor Coolant Pump 2.7 3.1 0 0 0 0 0 0 0 ~ 0 0 0 Problems associated with RCP motors, including faulty
motors and current, winding and bearing temperature
Ability to (a) predict the impacts of the problems
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)
---,-,---:-:---------------
026G2.4.20 Containment Spray 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of operational implications of EOP warnings,
cautions and notes.
This is a Generic, no stem statement is
associated .
_ ....__ ... _.,.- . ._.---------_. . _- - - - - - - - - - _. -=-=--
039A2.01 Main and Reheat Steam 3.1 3.2 0 0 0 D' 0 0 0 ~ 0 0 0 Flow paths of steam during a LOCA
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 ~ Knowledge of the specific bases for EOPs.
This is a Generic, no stem statement is
associated.
-_. __ _ - -Service
. - ------_._._----_..._---------------_.. _ - - - -
076A2.02 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
DRAFT
SRO T2G2 PWR EXAMINATION OUTLINE
I FORM ES-401-2
KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 05002.4.49 Condenser Air Removal 4.6 4.4 0 D DOD 0 DOD D ~ Ability to perform without reference to procedures those
actions that require immediate operation of system
This is a Generic, no stem statement is components and controls.
associated.
.--- --.- ....---------_.
071A2.05 Waste Gas Disposal 2.5 2.6 0 D D D D [] 0 ~ D D D Power failure to the ARM and PRM Systems
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)
072A2.02 Area Radiation Monitoring 2.8 2.9 DOD D D D 0 ~ D D D Detector failure
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 1 411/2008 2:10 PM
ES-401, REV 9
DRAFT
SRO T3 PWR EXAMINATION OUTLINE
I FORM ES-4011 ~
3
KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G TOPIC: IOI'2.~/o"
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 Equipment Control 3.0 3.6 [] 0 0 0 0 0 0 [J 0 0 ~ Knowledge of the process for making changes to
procedures
.._--_._------- - -- _.. - _.._. -.,-----:---,.-
G2.3.13 Radiation Control 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiological safety procedures pertaining to
... . licensed operator duties
G2.3.14 Radiation Control 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
G2.4.27 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 KIAs 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
plant procedures during all modes of plant
Conduct of Operations D,R
operation. 4.3/4.4
JPM: Calculate Manual Makeup to the Volume
Control Tank (JPM 005)
2.2.12 Knowledge of surveillance procedures.
3.7/4.1
Equipment Control N,S
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 1b 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
ES-301 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
plant procedures during all modes of plant
Conduct of Operations D,R
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.
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 plan, including supporting or acting
Emergency Procedures/Plan
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)
]
A 1a 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
A4 Evaluate plant conditions for E-Plan entry, classification, and required notifications in
accordance with Radiological Emergency Plan procedures. Bank JPM #18.
[= DRA~ J
ES-301 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)
N,A,S 1
Perform 0-SI-OPS-085-011.0
b. 003 Reactor Coolant Pump System (A2.03 2.7/3.1)
D,A,L,S 4P
Start #1 RCP in Mode 3 (182-AP)
c. E02 SI Termination (EA1.1 4.0/3.9)
M,A,S 3
Terminate SI and Re-establish Charging Flow
(JPM 027)
d. 040 Steam Line Rupture (AA2.01 4.2/4.7)
M,A,S 4S
Faulted SG Isolation with MSIV Stuck Open (JPM 058-AP2)
e. 064 Emergency Diesel Generators (A1.08 3.1/3.4)
D,S 6
Perform DIG Load Test on 1B-B DIG (JPM 077)
f. 028 Hydrogen Recombiner and Purge Control System (A4.03 3.1/3.3)
D,S 5
Place 1 B H2 Analyzer in Service
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)
D,A,L,S 7
Reinstate Source Range Detectors (JPM 119-AP)
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)
D,E,R 1
Perform Boration of RCS from Outside MCR (JPM 006)
j. 062 Loss of Nuclear Service Water (AK3.03 4.0/4.2)
D,E,R 4S
Installation of Temporary Cooling (HPFP) to CCP 1A-A or 1 B-B Oil
Coolers
k. 064 Emergency Diesel Generators (K1.05 3.4/3.9)
D 6
Align Starting Air for Service on 2A-A DIG (JPM 023-2)
@ 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 1B-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 1A-A pump and securing the
1B-B pump in accordance with 1-S0-70-1, Component Cooling Water System "A" Train. Bank
JPM.
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
JPM.
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
JPM.
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.
ES-301 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)
N,A,S 1
Perform 0-SI-OPS-085-011.0
b. 003 Reactor Coolant Pump System (A2.03 2.7/3.1)
D,A,S 4P
Start #1 RCP in Mode 3 (182-AP)
c. E02 SI Termination (EA1.1 4.0/3.9)
M,A,S 3
Terminate SI and Re-establish Charging Flow
(JPM 027)
d. 040 Steam Line Rupture (AA2.01 4.2/4.7)
M,A,S 4S
Faulted SG Isolation with MSIV Stuck Open (JPM 058-AP2)
e. 064 Emergency Diesel Generators (A1.08 3.1/3.4)
D,S 6
Perform D/G Load Test on 1B-B D/G (JPM 077)
f. 028 Hydrogen Recombiner and Purge Control System (A4.03 3.1/3.3)
D,S 5
Place 1 B H2 Analyzer in Service
g. NOT USED for SRO-I
h. 015 Nuclear Instrumentation System (A4.02 3.9/3.9)
D,A,L,S 7
Reinstate Source Range Detectors (JPM 119-AP)
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)
D,E,R 1
Perform Boration of RCS from Outside MCR (JPM 006)
j. 062 Loss of Nuclear Service Water (AK3.03 4.0/4.2)
D,E,R 4S
Installation of Temporary Cooling (HPFP) to CCP 1A-A or 1 B-B Oil
Coolers
k. 064 Emergency Diesel Generators (K1.05 3.4/3.9)
D 6
Align Starting Air for Service on 2A-A D/G (JPM 023-2)
@ 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
I DRAFT ]
(A)lternate path 4-6 1 4-6 1 2-3
(C)ontrol room
(D)irect from bank S9/s8/s4
(E)mergency or abnormal in-plant ~1/~1/~1
(EN)gineered safety feature - 1- 1 ~1 (control room system)
(L)ow-Power 1 Shutdown ~1/~1/~1
(N)ew or (M)odified from bank including 1(A) ~2/~2/~1
(P)revious 2 exams s 3 1 s 3 1s 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 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 1B-B will require manually starting and loading the DIG in accordance
with 1-SI-OPS-082-007.B, Electrical Power System Diesel Generator 1B-B. Bank JPM.
F. 1B 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
JPM.
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
JPM.
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.