ML050950495
| ML050950495 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/26/2004 |
| From: | Division of Nuclear Materials Safety II |
| To: | |
| References | |
| 50-261/04-301 | |
| Download: ML050950495 (13) | |
See also: IR 05000261/2004301
Text
Final Submittal
ROBINSON AUG/SEPT 2004
EXAM NO. 05000261/2004-301
AUG. 27 - SEPT. 3, 2004
FINAL SAMPLE PLANS / OUTLINES
ES-401 PWR Examination Outline Form ES-401-2
Final
Facility: HB Robinson Date of Exam: 8/27/2004
RO K/A Category Points I I
Tier Group K K K K K K 7 A A A G Total
1 2 3 4 5 6 1 2 3 4 *
1. 1 0 0 4 7 16 1 18
Emergency
& 2 2 2 2 1 2 1 9
Abnormal
Plant Tier 2 2 6 8 8 2 28
Evolutions Totals
2. 1 3 4 4 1 1 1 5 3 0 4 2 28
Plant 2 1 0 0 1 1 1 1 2 2 1 0 10
Systems Tier 4 4 4 2 2 2 6 5 2 5 2 38
Totals
3. Generic Knowledge and 1 2 3 4 9
Abilities Categories 2 3 2 2
Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier of
the RO outline (i.e., the "Tier Totals" in each K/A category shall not be less than two).
Refer to Section D.1.c for additional guidance regarding SRO sampling.
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. Select topics from many systems and evolutions; avoid selecting more than two K/A
topics from a given system or evolution unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.
6.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A
Catalog, but the topics must be relevant to the applicable evolution or system. The SRO
K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
7. On the following pages, enter the K/A numbers, a brief description of each topic, the
topics' importance ratings (IR) for the applicable license level, and the point totals for
each system and category. Enter the group and tier totals for each category in the table
above; summarize all the SRO-only knowledge and non-A2 ability categories in the
columns labeled "K"and "A". Use duplicate pages for RO and SRO-only exams.
8. For Tier 3, enter the K/A 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
K/A statements.
NUREG-1021, Draft Revision 9 1
ES-401 HB Robinson Form ES-401-2
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier I Group 1
EIAPE #/ Name Safety Function IG K1 K2 K3 A1 IA21 NumberT K/A Topic(s) Imp. 1Q#1
0 Ability to determine or interpret the following as they apply 40 76
009 / Small Break LOCA X EA2.04 to a small break LOCA: PZR level
Emergency Procedures / Plan Ability to perform without
027 / Pressurizer Pressure Control System Malfunction X 24.49 reference to procedures those actions that require 40 77
3 immediate operation of system components and controls.
ATWS 11 EA2 09 Ability to determine or interpret the following as they apply 45
029 i ATWS / 1 to a ATWS: Occurrence of a main turbine/reactor trip
Emergency Procedures / Plan Ability to verify system
X 2,450 alarm setpoints and operate controls identified in the 33 79
056 / Loss of Off-site Power / 6 alarm response manual.
Ability to determine and interpret the following as they
X AA2.02 apply to the Loss of Nuclear Service Water: The cause of 3.6 80
062 / Loss of Nuclear Svc. Water / 4
possible CCW loss
E04 / LOCA Outside Containment / 3 2A2.128 Conduct of Operations: Knowledge of the purpose and 33 81
nX 1 function of major system components and controls.
E05 / Inadequate Heat Transfer - Loss of Secondary X 2 1.27 Conduct of Operations: Knowledge of system purpose 29 82
Heat Sink / 4 and or function.
X 2.1.20 Conduct of operations: Ability to execute procedure steps. 4.3 39
007 / Reactor Trip - Stabilization - Recovery/ 1
Ability to determine and interpret the following as they
X AA2.23 apply to the Pressuizer Vapor Space Accident: Criteria 3.6 40
008 / Pressurizer Vapor Space Accident /3
for throttling high-pressure injection after a small LOCA
009 1 Small Break LOCA / 3 009 Smll rea LOC / XA1.17 EA.17 Ability
to to operate
a small break LOCA: PRT the following as they apply
and monitor 34 41
Knowledge of the reasons for the following responses as
X EK3.03 the apply to the Large Break LOCA: Starting auxiliary feed 4.1 42
oil / Large Break LOCA / 3 pumps and flow, ED/G, and service water pumps
Ability to operate and / or monitor the following as they
XAM .22 apply to the Reactor Coolant Pump Malfunctions (Loss of 4.0 43
015 / 17 / RCP Malfunctions / 4 RC Flow): RCP seal failure/malfunction
Ability to operate and / or monitor the following as they
025 / Loss of RHR System/4 x AAI.20 apply to the Loss of Residual Heat Removal System: HPI 2.6
pump control switch, indicators, ammeter running lights,
and flow meter
Ability to determine and interpret the following as they
026 / Loss of Component Cooling Water / 8 X AA2.02 apply to the Loss of Component Cooling Water: The 2.9 45
cause of possible CCW loss I I
NUREG Draft Revision 9
ES-401 HB Robinson Form ES-401-2
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions- Tier 1 Group 1
- /
I/PEName Safety Function GKA1 A2 Number K/A Topic(s) Imp. Q#
Ability to determine and interpret the following as they
7 /Pressurizer X AA2.10 apply to the Pressurizer Pressure Control Malfunctions: 3.3 46
heater energizedldeenergized condition
029/ ARNS/ 1X X E1.0
EAl to a ATWS:
Ability to operate androd
Manual controlthe following as they apply
monitor 4.0 47
029 / ATWS / 1
038/Steam Gen. Tube Rupture / 3
038 3Stam en. ubeRupure X EA.19
EAl.19 to a SGTR:
Ability MFWand
to operate System
monitor the indicator
status following as they apply 3.4 48
Ability to operate and / or monitor the following as they
040 / Steam Line Rupture - Excessive Heat Transfer /4 X AA1.13 apply to the Steam Line Rupture: Steam line isolation 4.2 49
valve indications
Ability to determine and interpret the following as they
054/ Loss of Main Feedwater / 4 X AA2.08 apply to the Loss of Main Feedwater (MFW): Steam flow- 2.9 50
feed trend recorder
056/ Loss of Oft-site Power/S6 AA2.56 Ability to determine and interpret the following as they 3B 51
A 5
06Looff-tPw/ apply to the Loss of Offsite Power: RCS T-ave
Ability to determine and interpret the following as they
0571 Loss of Vital AC Inst. Bus / 6 X AA2.17 apply to the Loss of Vital AC Instrument Bus: System and 3.1 52
component status, using local or remote controls
Knowledge of the reasons for the following responses as
058 / Loss of DC Power / 6 X AK3.02 they apply to the Loss of DC Power: Actions contained in 4.0 53
EOP for loss of do power
Ability to operate and / or monitor the following as they
the to 2.9
X A .07 apply to the Loss of Nuclear Service by rates
Water: Flow
Nclear Svc. Water /4 the components and systems that are serviced
CCWS; interactions among the components
Knowledge of the reasons for the following responses as
effects
Knowingfrom 2.9 55
065 / Loss of Instrument Air / S AK3.03 they apply
on plant to the Loss
operation of isolating certain Air:
of Instrument equipment
instrument air
Knowledge of the reasons for the following responses as
they apply to the (Loss of Secondary Heat Sink) RO or
E05 I Inadequate Heat Transfer - Loss of Secondary X EK3.4 SRO function as a within the control room team as56
Heat Sink / 4 appropriate to the assigned position, in such a way that
procedures are adhered to and the limitations in the
facilities license and amendments are not violated.
KA Category Point Totals: 5 0 0 4 7 9 Group Point Total: 25
NUREG-4 -), Draft Revision 9 )
I ES-401 HB Robinson Form ES-401-2 I
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 2
I
EIAPE # / Name Safety Function IG I K1 IK2 I K3 I Al I A2 Number K/A Topic(s) Imp. Q#
2.46 Emergency Procedures / Plan Knowledge symptom based 40 83
036 /Fuel Handling Accident / 8 -X 2.46 EOP mitigation strategies.
Ability to determine and interpret the following as they
E EA2 apply to the (Degraded Core Cooling) Facility conditions 42 84
E06 rinad Core Cooling 4 Eand selection of appropriate procedures during abnormal
and emergency operations.
Emergency Procedures / Plan Knowledge of EOP
E03 I Post-LOCA Cooldown/Depressurization. 4 x 24 16 implementation hierarchy and coordination with other 40 85
support procedures
Ability to determine and interpret the following as they
El44! Loss of CTMT Integrity / 5 X EA21 apply to the (High Containment Pressure) Facility 38 86
conditions and selection of appropriate procedures during
abnormal and emergency operations.
Ability to determine and interpret the following as they
apply to the (High Containment Radiation) Facility 2.9 73
E16 I High Containment Radiation 9 Econditions and selection of appropriate procedures during
abnormal and emergency operations.
Knowledge of the interrelations between the Continuous
001 / Continuous Rod Withdrawal /1 X AK2.01 Rod Withdrawal and the following: Rod bank step 2.9 57
counters
Knowledge of the operational implications of the following
003 / Dropped Control Rod / 1 x AK1.21 concepts as they apply to Dropped Control Rod: Delta 2.7 58
flux (Al)
Knowledge of the reasons for the following responses as
005 / Inoperable/Stuck Control Rod / 1 x AK3.02 they apply to the Inoperable / Stuck Control Rod: Rod 3.6 59
insertion limits
024/ Emergency Boration I I x AA2.04 Ability to determine and interpret the following as they 3.4 60
apply to the Emergency Boration: Availability of BWST
Conduct of Operations: Ability to perform specific system
028 / Pressurizer Level Malfunction / 2 x 2.1.23 and integrated plant procedures during all modes of plant 3.9 61
operation.
Ability to operate and / or monitor the following as they
X AA1.02 apply to the Control Room Evacuation: AFW emergency 4.3 62
068 / Control Room Evac. / 8
pump
iI!!M
Knowledge of the operational implications or the following
concepts as they apply to the (SI Termination) Normal,
x EK1.2 abnormal and emergency operating procedures 3.4 63
E02 / Rediagnosis & SI Termination / 3
associated with (SI Termination).
I ................ )......~
NUREGSý, Draft Revision 9
ES-401 HB Robinson Form ES-401-2
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 2
E/ # / Narne Safety Function G K1K3A1 A2 Number K/A Topic(s) Imp. Q#
Knowledge of the interrelations between the (Degraded
Core Cooling) and the following: Components, and
E06 / Inad. Core Cooling /4 x EK21 functions of control and safety systems, including 3.6 64
instrumentation, signals, interlocks, failure modes, and
automatic and manual features.
Knowledge of the reasons for the following responses as
they apply to the (Steam Generator Overpressure)
Facility operating characteristics during transient
E13 / Steam Generator Over-pressure /4 X EK3.1 conditions, including coolant chemistry and the effects of 2.9 65
temperature, pressure, and reactivity changes and
operating limitations and reasons for these operating
characteristics.
K/A Category Point Total: 2 2 2 1 14
NUREG-' Draft Revision 9 5
ES-401 HB Robinson Form ES-401-2
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 2 Group 1
G KI K2 K3 I K4 I K5 K6 Al A2 A3 A4 Number K/A Topics Imp. Q# I
FSystem #/Name
Ability to (a) predict the impacts of the following
malfunctions or operations on the ECCS: and (b) based
X A2 12 on those predictions, use procedures to correct, control. 48 86
006 Emergency Core Cooling
or mitigate the consequences of those malfunctions or
operations: Conditions requiring actuation of ECCS
Emergency Procedures ! Plan Knowledge of
x 2.431 annunciators alarms and indications, and use of the 3.4 89
012 Reactor Protection
response instructions.
Ability to (a) predict the impacts of the following
malfunctions or operations on the CCS: and (b) based
on those predictions, use procedures to correct, control.
022 Containment Cooling
l A2 03
A2 03 or mitigate the consequences of those malfunctions or 10 90
operations: Fan motor thermal overload/high-speed
operation
Emergency Procedures/Plan: Ability to verify system
2 450 alarm setpoints and operate controls identified in the 33 91
010 Pressurizer Pressure Control X
alarm response manual.
Knowledge of the effect that a loss or malfunction of the
K3.03 RCPS will have on the following: Feedwater and 2.8 1
003 Reactor Coolant Pump emergency feedwater
manually operate and/or monitor in the control 2.6 2
3Reator Coolant Pump
0 A407 room: to
Ability RCP seal bypass
K Knowledge of bus power supplies to the following: 33 3
004 Chemical and Volume Charging Pumps
Control X
Ability to (a) predict the impacts of the following
malfunctions or operations on the RHRS, and (b) based
X A2.04 on those predictions, use procedures to correct, control, 2.9 4
005 Residual Heat Removal or mitigate the consequences of those malfunctions or
operations: RHR valve malfunction
Knowledge of the physical connections and/or cause-
K1.01 effect relationships between the RHRS and the following 3.2 5
005 Residual Heat Removal X
systems: CCWS
Ability to predict and/or monitor changes in parameters
006 Emergency Core Cooling Al 6 (to prevent exceeding design limits) associated with 3.6 6
operating the ECCS controls including: Subcooling
margin
007 Pressurizer Relief/Quenich X A4.1 0 Ability to manually operate and/or
room: Recognition of leaking PORV/code in the control
monitor safety 3.6 7
Tan
Tank __________________________
K2.02 Knowledge of bus power supplies to the following: cOW 3.0 8
008 Component Cooling Water 1W X pump, including emergency backup
- - - - - - - - - - - - - - - -
NUREG , Draft Revision 9
ES-401 HB Robinson Form ES-401-2
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 2 Group 1
system #/Name IIK14
K5 K6 I A I A-2 I A3 A4u -Number KIA Topics Imp Q#
Ability to (a) predict the impacts of the following
malfunctions or operations on the CCWS, and (b) based
008 Component Cooling Water X A2.03 on those predictions, use procedures to correct, control, 3.0 9
or mitigate the consequences of those malfunctions or
operations: HigMow CCW temperature
Ability to predict and/or monitor changes in parameters
010 Pressurizer Pressure Control XAl.04 (to prevent exceeding design limits) associated with
operating the PZR PCS controls including: Effects of 36 10
temperature change during solid operation
31 11
012 Reactor Protection x K3.02 I Knowledge
RPS will have of the effect
on the following: T/Gor malfunction of the
that a loss
013 Engineered Safety Features xKnowledge of the effect that a loss or malfunction of the
K3,03 ESFAS will have on the following: Containment 4.3 12
Actuation X
Ability to predict and/or monitor changes in parameters
022 Containment Cooling X A1 04 (to prevent exceeding design limits) associated with 32 13
operating the CCS controls including: Cooling water flow
Ability to predict and/or monitor changes in parameters
026 Containment Spray X Al.011 (to prevent exceeding design limits) associated with 3.9 14
operating the CSS controls including: Containment
pressure
Ability to predict and/or monitor changes in parameters
039 Main and Reheat Steam X A1.06 (to preventtheexceeding design limits) associated with 3.0 15
operating MRSS controls including: Main steam
pressure
Knowledge of the physical connections and/or cause-
039 Main and Reheat Steam X K1.09 effect relationships between the MRSS and the following 2.7 16
systems: RMS
Knowledge of the physical connections and/or cause-
056 Condensate X K1.03 effect relationships between the Condensate System 2.6 17
and the following systems: MFW
059 ain eedwter 3.04 Knowledge
MFW will have on effect
of the that a loss
the following: RCSor malfunction of the 3.6 16
Knowledge of the effect of a loss or malfunction of the
061 Auxildary/Emergency X K6.02 following will have on the AFW components: Pumps 2.6 19
FeedwaterI I [
Knowledge of ac distribution system design feature(s)
062 AC Electrical Distribution x K4.02 and/or interlock(s) which provide for the following: Circuit 2.5 20
breaker automatic trips
03DC ElcrclDistribution X201 dc loads29 29 1
21
063 DCElectrical Dist n K.01 Knowledge of bus power supplies to the following: Major
NUREG-' -'1, Draft Revision 9 7
ES-401 HB Robinson Form ES-401-2
NRC Written Examination Outline
Tier 2 Group 1
Emergency and Abnormal Plant Evolutions -
iSystem * KA Topics
Ability to (a) predict the impacts of the following
malfunctions or operations on the ED/G system; and (b)
06 based on those predictions, use procedures to correct, 2.6 22
Emergency Diesel Generator X A2.13 control, or mitigate the consequences of those
malfunctions or operations: Consequences of opening
auxiliary feeder bus (ED/G sub supply)
Knowledge of the operational implications as they apply
073 Process Radiation Monitoring X K5.02 to concepts as they apply to the PRM system: Radiation 2.5 23
intensity changes with source distance
073 Process Radiation Monitoring x A4,02 Ability to manually operate and/or monitor in the control 37 24
room Radiation monitoring system control panel
Conduct of Operations: Ability to recognize indications
076 Service Water X 2.1.33 for system operating parameters which are entry-level 3.4 25
conditions for technical specifications.
078 Instrument Air X K202 Knowledge of bus power supplies to the following 3.3 26
Emergency air compressor
078 Instrument Air X A4.01 room: to
Ability manually
Pressure operate and/or monitor in the control
gauges 3.1 27
103 Containment X 2.1.2 Conduct of Operations: Knowledge of operator 3.0 28
responsibilities during all modes of plant operation.
K/A Category Point Totals: 4 4 1 1 1 5 5 0 4 Group Point Tal 32
NUREG- 4 'I1, Draft Revision 9 8
ES-401 HB Robinson Form ES-401-2
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 2 Group 2
System #/Name G KI 1K2 K3 K4 K5 I K6 I Al 172 A3 A4 Number I KATopics Imp. Q#
Equipment Control Knowledge of bases in technical
029 Containment Purge X 2 2 25 specifications for limiting conditions for operations and 37 92
safety limits.
Conduct of Operations: Ability to perform specific
034 Fuel Handling Equipment X 21 23 system and integrated plant procedures during all 4.0 93
modes of plant operation
Knowledge of the operational Implications of the
002 Reactor Coolant K5 following concepts as they apply to the RCS:
Relationship of pressure and temperature for water 37 29
saturation and subcooling conditions
Ability to predict and/or monitor changes in parameters
X A1.04 (to exceeding
preventthe design limits) associated with 3.5 30
014 Rod position nIndication operating RPIS controls, including: Axial and radial
power distribution
015 Nuclear Instrumentation X A4.03 Ability to manually operate and/or monitor in the control 3.8 31
Ability to monitor automatic operation of the NNIS,
016 Non-nuclear Instirumentation X A3.01 including: Automatic selection of NNIS inputs to control 2.9 32
systems I
Knowledge of design feature(s) and/or interlock(s)
029 Containment Purge K4.03 which provide for the following: Automatic purge 3.2 33
isolation
Ability to (a) predict the impacts of the following
malfunctions or operations on the Fuel Handling
034 Fuel Handling Equipment 2.01 System ; and (b) based on those predictions, use 3.6 34
procedures to correct, control, or mitigate the
consequences of those malfunctions or operations:
Dropped fuel element
Knowledge of the physical connections and/or cause-
035 Steam Generator K1.01 effect relationships between the S/GS and the following 4.2 35
systems: MFW/AFW systems
Knowledge of the effect of a loss or malfunction on the
041 Steam Dump/Turbine Bypass X K6.03 following will have on the SDS: Controller and 2.7 36
Control positioners, including ICS, S/G, CRDS
monitor automatic operation of the MT/G
045 Main Turbine Generator 0G A3.0
A3F05 system,toincluding:
Ability Electrohydraulic control 2.6 37
NUREG-S,, Draft Revision 9
ES-401 HB Robinson Form ES-401-2
NRC Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 2 Group 2
System #/Name K1
K K2 K3 K4 K5 K6 Al A2 A3 A4 Number K/A Topics Imp. Q#
Ability to (a) predict the impacts of the following
malfunctions or operations on the Fire Protection
086 Fire Protection X A2.01 System; and (b) based on those predictions, use 2,9 3
procedures to correct, control, or mitigate the
consequences of those malfunctions or operations:
Manual shutdown of the FPS
KJA Category Point Totals: 2 1 0 0 1 1 1 1 2 2 1 Group Point Total: 12
NUREG-1n'01, Draft Revision 9 10
ES-401 Generic Knowledge and Abilities Outline ('ier3) Form ES-401-3]
Facility: HB Robinson Date of Exam: 8/27/2004
RO SRO-Only
Category K/A # Topic
IR Q# IR Q#
2.1.11 Knowledge of less than one hour technical 38 94
specification action statements for systems.
2.1.3 Knowledge of shift turnover practices. 34 95
Conduct of 2.1.28 Knowledge of the purpose and function of major 3.2 66
Operations system components and controls.
2.1.1 Knowledge of conduct of operations 3.7 67
1 requirements.
Subtotal 2 2
Knowledge of the process for making changes in
2.2.6 procedures as described in the safety analysis 33 96
report.
2.212 Knowledge of surveillance procedures 3.4 97
Knowledge of bases in technical specifications
2.225 for limiting conditions for operations and safety 37 98
2. limits
Equipment Control 2.2.14 Knowledge of the process for making 2.9 68
configuration changes.
2.2.13 Knowledge of tagging and clearance 3.6 69
procedures.
2.2.28 Knowledge of new and spent fuel movement 2.6 70
procedures.
Subtotal 3 3
2.3.9 Knowledge of the process for performing a 34 99
containment purge.
3. 2.3.2 Knowledge of facility ALARA program. 2.5 71
Radiation Control 2.3.1 Knowledge of 10 CFR: 20 and related facility 2.6 72
radiation control requirements
Subtotal 2 1
2.4.16 Knowledge of EOP implementation hierarchy 4.0 100
and coordination with other support procedures
2.4.37 Knowledge of the lines of authority during an 35 87
emergency.
Knowledge of facility protection requirements
4. 2.4.26 including fire brigade and portable fire fighting 2.9 74
Emergency equipment usage.
Procedures / Plan Ability to recognize abnormal indications for
2.4.4 system operating parameters which are entry- 4.0 75
level conditions for emergency and abnormal
I operating procedures.
Subtotal 3 1
Tier 3 Point Total 9 8
NUREG-1021, Draft Revision 9 11
ES-401 Record of Rejected K/As Form ES-401-4
Tier / Randomly Reason for Rejection
Group Selected K/A
2/1 007 A2.03 Double Jeopardy with question #8. Replaced with 008 A2.03
1/2 E10 G2.4. 30 It isn't possible to prepare a psychometrically sound question related to the
subject K/A. Replaced with E03 G2.4.31
It isn't possible to prepare a psychometrically sound question related to the
1/2 051 G2.1.27 subject K/A. Topic was randomly generated as part of random search for
replacement of El0 Generic
search for
1/2 E06 G2.1 .14 3 items in one topic, this item was generated as part of a random
replacement of El0 Generic.
with Generic
2/2 034 A2.02 Replaced due to double jeopardy with 034 A2.01. Replaced
2A1.23
to the
1/1 007 G2.2.22 It isn't possible to prepare a psychometrically sound question related
subject K/A. Replaced with 007 G2.1.20
Does not apply and could not prepare a psychometrically sound question
related to the topic. Replaced with 027 AA2.10
to the
2/1 061 G2.1.14 It isn't possible to prepare a psychometrically sound question related
subject K/A. Replaced with 010 G2.4.50
2/1 006 A2.05 psychometrically sound question related to the
It isn't possible to prepare a 006
subject K/A. Replaced with A2.12
1/2 E03 G2.4.31 KA rejected and replaced with E03 G2.4.16 as directed by Chief Examiner
!/2___ E 4 8/17/2004
NUREG-1021, Draft Revision 9 12