ML13142A544
| ML13142A544 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/15/2013 |
| From: | NRC/RGN-III |
| To: | Exelon Generation Co |
| Zoia C | |
| Shared Package | |
| ML11354A332 | List: |
| References | |
| ES-401-2, ES-401-3 | |
| Download: ML13142A544 (10) | |
Text
ES-401 PWR Examination Outline FORM ES-401 -2 Facility Name: i>rc, ;tl(...>~ ~A Date of Exam:
3/2<;"/1 3 RO KIA Category Points SRO-Only Points Tier Group K
K K
K K
K A
A A
A G
A2 G*
1 2
3 4
5 6
1 2
3 4
Total Total
- 1. Emergency 1
3 3
3 3
3 3
18 3
3 6
Abnormal 2
1 2
1 N/A 2
2 N/A 1
9 2
2 4
Plant Evolutions Tier Totals 4
5 4
5 5
4 27 5
5 10 1
2 2
3 3
3 2
2 3
2 3
3 28 3
2 5
- 2.
2 1
1 1
1 1
1 1
Plant Systems 0
1 1
1 10 o I 2 1
3 Tier Totals 3
3 4
4 4
3 3
3 3
4 4
38 5
3 8
1 2
3 4
I 1
I 2
I 3
I 4
I I
- 3. Generic Knowledge and Abilities 10 7
Categories 3
2 2
3 2
2 1
2 Note: 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le.. except for one category in Tier 3 of the SRO-only outline. the "Tier Totals" 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 Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority. only those K/As 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.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7."
The generic (G) KlAs 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. Refer to Section D.1.b of ES-401 for the applicable KlAs.
- 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 (#) 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 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 #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3. select topics from Section 2 of the KIA catalog. and enter the KIA numbers. descriptions. IRs.
and point totals (#) on Form ES401 -3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
ES-401. 21 of 33
ES-401 2
Form ES-401-2 ES-401 PWR Exam ination Outline Form ES-401-2 Em ergency and Abnormal Plant E volutions - Tier 1/Group 1 (RO)
Q#
E/APE # I Nam e I Safety Function K
K K
A A
G KIA T opic(s)
IR 1
2 3
1 2
39 000007 Reactor Trip - Stabilization - Recovery I 1 0
3 Reactor trip status panel 3.5 1
40 000008 Pressurizer Vapor Space Accident 1 3 0
1 Valves 2.7 1
r---
41
~00009 Small Break LOCA 1 3 2
4 RCP temperature selpoinls 2.6 1
P00011 Large Break LOCA 13 0
42
~000 15 RCP Malfunctions I 4 2
RCP seal failure/malfunction 4.0 1
000017 RCP Malfunctions (Loss of RC Flow) 1 4 2
43 000022 Loss of Rx Coolant Makeup I 2 0
Actions contained in SOPs and EOPs for RCPs, loss of makeup.
3.5 1
2 loss of charging, and abnormal charging 44 000025 Loss of RHR System I 4 0 1. Knowledge of the purpose and function of major system 4.1 1
28 components and controls.
45 P00026 Loss of Component Cooling Water I 8 0
Effect on the CCW flow header of a loss of CCW 3.5 1
4 46 P00027 Pressurizer Pressure Control System 0
2.8 Malfunction 1 3 2
Expansion of liquids as temperature increases 1
~00029 A TWS 11 0
47 000038 Steam Gen. Tube Rupture 1 3 0
4 Reflux bailing 3.1 1
000040 Steam Line Rupture - Excessive Heat Transfer 4
1 48 WE 12 Uncontrolled Depressurization of all Steam 0
Facility conditions and selection of appropriate procedures 3.2 Generators 1 4 1
during abnormal and emergency operations 4 9 P00054 (CE/E06) Loss of Main Feedwater I 4 0
2 Matching of feedwater and steam flows 3.4 1
50
~00055 Station Blackout 1 6
- 04.
18 Knowledge of the specific bases for EOPs.
3.3 1
51 p00056 Loss of Off-site Power I 6 0
4 Definition of saturation conditions, implication for the systems
- 3. 1 1
52 000057 Loss of Vital AC Inst. Bus 1 6 0
2 Manual control of PZR level 3.8 1
53 000058 Loss of DC Power 1 6 0 1. Ability to use plant computers to evaluate system or component 3.9 1
19 status.
54 000062 Loss of Nuclear Svc Water 1 4 0
Control of flow rates 10 components cooled by the SWS 2.9 1
6 55 p00065 Loss of Instrument Air 18 0
8 Failure modes of air-operated equipmenl 2.9 1
\\tv/E04 LOCA Outside Containment I 3 0
Itv/E11 Loss of Emergency Coolant Recirc. 14 0
BW/E04; W/E05 Inadequate Heat Transfer - Loss of 0
Secondary Heat Sink 1 4 56 000077 Generator Voltage and Electric 0
3.0 Controllers, positioners 1
Grid Disturbances 1 6 4
KIA Category T otalS:
3 3
3 3
3 3
G roup P oint Total:
18 ES-401, 22 of 33
ES-401 3
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
Q#
E/APE # I Name I Safety Function K
K K
A A
G KIA Topic(s)
IR 1
2 3
1 2
57 000001 Continuous Rod Withdrawal I 1 05 Rod motion lights 2.9 1
fJ00003 Dropped Control Rod I 1 0
58 000005 Inoperable/Stuck Control Rod 11 03 Xenon transient 3.2 1
000024 Emergency Boration I 1 0
000028 Pressurizer Level Malfunction I 2 0
~00032 Loss of Source Range NI /7 0
59 000033 Loss of Intermediate Range NI / 7 01 Equivalency between source-range, Intermediate*range. and 3.0 1
power-range channel readings 60 000036 Fuel Handling Accident I 8 01 Fuet handling equipment 2.9 1
~000 37 Steam Generator Tube Leak I 3 0
000051 Loss of Condenser Vacuum I 4 0
61 000059 Accidental Liquid RadWaste ReI. 19 01 Radioactrve-liquid monitor 3.5 1
000060 Accidental Gaseous Radwaste ReI. 19 0
01. Knowledge of the purpose and function of major system 62 000061 ARM System Alarms 17 28 components and controls.
4.1 1
~00067 Plant Fire On-site I 8 0
000068 Control Room Evac. I 8 0
000069 Loss of CTMT I ntegrity I 5 1
63 W/E14 High Containment Pressure I 5 03 Desired operating results during abnormal and emergency 3.3 situations 000074 Inad. Core Cooling 14
~"'E06 Degraded Core Cooling 14 0
~/E 07 Saturated Core Cooling I 4 000076 High Reactor Coolant Activity I 9 0
W/EOl Rediagnosis I 3 0
W/E02 SI Termination I 3
~/E 13 Steam Generator Over-pressure I 4 0
~/E15 Containment Flooding I 5 0
~/E16 High Containment Radiation 19 0
W/E03 LOCA Cooldown - Depress. 14 0
W/E09 Natural Circulation Operations I 4 W/E1 0 Natural Circulation with Steam Voide in
'u v. ~"u 'u,,_"u" w."'" *. "0 w""v,.VV". 'Od'" d> dW'V~"d'O 1
64 Vessel with/without RVLlS. 14 04 to the assigned posItion. In such a way that procedures are 3.4 "h
65
~v/E08 RCS Overcooling - PTS I 4 01 Facility conditions and selection of appropriate procedures dunng 3.4 1
abnormal and emergency operations KIA Category Totals:
1 2
1 2
2 1 Group Point Total:
9 ES-401, 23 of 33
ES-401 4
Form ES-401-2 IES-401 PWR Examination Outline Form ES-401 -<
Plant Systems - Tier 2/Group 1 (RO)
Q# ISystem # / Name
~ ~ ~ ~ ~ ~
.~ ~ ~ I~ G KIA Topic(s)
IR 11,1 1003 Reactor Coolant Pump 1
0 Icews; Motor current 3; 2.6 2
2 2
l' 1004 Chemical and Volume Control 0
IControl instrumentation: 80ron concentration 2.6; 2
6 5
3.6 15 1005 Residual Heat Removal
~
IEees 3.7 1
16 1006 Emergency Core Cooling 0
Effects of temperatures on water level Indications 2.8 1
1 17 1007 Pressurizer Relief/Quench Tank
~
Maintaining quench tank water level within limits 2.9 1
18 1008 Component Cooling Water
~
Loss of eew pump 3.3 1
19 1010 Pressurizer Pressure Control
~
IESFAS 4.0 1
20 012 Reactor Protection 0
!TriP logic when one channel OOC or in test 3.7 1
1 21 01 ineered Safety Features
~
o~ ' "u. equipment control 3.6 1
IArh,,,tir)n 22 1022 Containment Cooling
~
Loss of ecs pump 2.8 1
1025 Ice Condenser 23,2' 026 Containment Spray 0
- 04. Pump starts and correct MOV positioning; Knowledge of 4.3; 1
35
'Ioca'-
during an emergency and the 3.8 2
resultant oD~rationa l effects.
25 039 Main and Reheat Steam 0
Bases for ReS cooldown limits 2.7 1
5 26 059 Main Feedwater
~
Power level restrictions for operation of MFW pumps and 2.7 1
valves 27 1061 Auxiliary/Emergency Feedwater 0
Controllers and posltioners 2.5 1
1 28 1062 AC Electrical Distribution 0
ED/G 4.1 1
2 129,3( 1063 DC Electrical Distribution 0
- 04. ISreakerrnteiiOcks-:-P~'" '..
'v~~=ses aiidCrOss-lies; 2.9; 2
30
- tha 2.7 2
Imust be reoorted to internal i
5 or external 131,3: 1064 Emergency Diesel Generator
~
01. IFuel tanks; Ability to interpret reference 3.2; 2
25 Imaterials.
graphs, curves, tables, etc.
3.9 133,3' 1073 Process Radiation Monitoring 0
0 Radiation intensity changes with source distance; Radiation 2.5; 2
2 2
momtonng system control panel 3.7 35 1076 Service Water 0
1 Loss of 8WS 3.5 1
1 36, 3~ 1078 Instrument Air 0
0 transfers of control; Pressure gauges 2.7; 2
1 1
3.1 38 1103 Containment
~
I SIS. Including action of safety injection reset 3.6 1
0 IKiA Category Totals:
2 2
3 1 3 1 2 3
1 3 3 IGroup Point Total:
28 ES-401, Page 24 of 33
ES-401 5
Form ES-401-2 E8-401 PWR Examination Outline Form E8-401-2 Plant Systems - Tier 2/Group 2 (RO)
Q# System # / Name K
K K
K K
K A A A
~ *C KIA Topic(s)
IR 1
2 3
4 5
6 1 3 3
0 Ii I:
1 001 Control Rod Drive 8
>_,_ Prevention of excessive rod movement 3.2 1
2 1002 Reactor Coolant 1
- . Relationship between effocts of the primary coolant system 4.0 1
1 ii and the secondary coolant system 3
011 Pressurizer Level Control 0
3.1 1
?
PZR heaters 1014 Rod Position Indication 0
015 Nuclear Instrumentation
.i' 0
016 Non-nuclear Instrumentation 0
4 017 In-core Temperature Monitor I
0
,r"::,: Indications of normal, natural, and intf;)rrupted circulation of 3.6 1
1 ReS 027 Containment Iodine Removal 0
028 Hydrogen Recombiner and Purge 0
Control 029 Containment Purge 0
04 Ability to recognize abnormal indications for system operating 5
033 Spent Fuel Pool Cooling 04 parameters that are entry-level conditions for emergency and 4.5 1
abnormal op_eratinI[PJ:ocedures 034 Fuel Handling Equipment 0
6 1035 Steam Generator a
S/G pressure 3.5 1
2 041 Steam Dump/Turbine Bypass Control 0
045 Main Turbine Generator 0
055 Condenser Air Removal I>
0 7
056 Condensate 0
MPN 2.6 1
3 1
8 068 liquid Radwaste a
Radiation monitors 2.5 1
9 071 Waste Gas Disposal 0
5 10 072 Area Radiation Monitoring 0
Major components 2.5 1 2
075 Circulating Water 0
079 Statton Air 0
086 Fire Prote,;tion G
EEl 11 I 11EI 'JI 11 I IGroun Poini Total*
[
KIA Category Totals:
1 1
I 1
~
.=,
ES-401, Page 25 of 33
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
Q#
E/APE # I Name I Safety Function K
K K
A A
G KIA Topic(s)
IR 1
2 3
1 2
p00007 Reactor Trip - Stabilization - Recovery 11 0
POD008 Pressurizer Vapor Space Accident I 3 0
000009 Small Break LOCA I 3 0
84 000011 Large Break LOCA I 3 0
CondItions necessary for recovery when accident reaches stable 3.9 8
phase 1
000015 RCP Malfunctions 14 0
000017 RCP Malfunctions (Loss of RC Flow) 14 P00022 Loss of Rx Coolant Makeup I 2 0
P00025 Loss of RHR System I 4 0
P00026 Loss of Component Cooling Water I 8 0
000027 Pressurizer Pressure Control System 0
Malfunction I 3
- 04. Ability to recognize abnormal indications for system operating 85 000029 A TWS I 1 04 parameters that are entry.level condItions for emergency and 4.7 1
abnormal Qru!ralinJI.Jl(ocedures.
p 00038 Steam Gen. Tube Rupture I 3 0
86 P00040 Steam Line Rupture - Excessive Heat Transfer
- 04. Ability 10 verify Ihallhe alarms are consistent with the planl 4.2 4
46 conditions.
1
~
12 Uncontrolled Depressurization of all Steam Generators I 4 b00054 (CE/E06) Loss of Main Feedwater I 4 0
000055 Station Blackout I 6 0
000056 Loss of Off-site Power I 6 0
I--
p00057 Loss of Vital AC Inst. Bus 16 0
P00058 Loss of DC Power I 6 0
000062 Loss of Nuclear Svc Water I 4 0
000065 Loss of Instrument Air I 8 0
87 tw/E04 LOCA Outside Containment I 3 0
Adherence 10 appropnale procedures and opera lion within the 4.2 1
2 limitations in the faCIlity's license and amendments I--
138 tw/E 11 Loss of Emergency Coolant Recirc. I 4 0
Adherence to appropriate procedures and operation within Ihe 4.2 1
2 limitations in the facility's license and amendments 89 BW/E04; W/E05 Inadequate Heat Transfer - Loss of
- 02. Knowledge of Ihe bases in Technical SpeCifications for limiting 4.2 1
Secondary Heat Sink I 4 25 conditions for operations and safety limits.
000077 Generator Voltage and Electric 0
Grid Disturbances I 6 KIA Category Totals:
0 0
0 0
3 3 Group Point Total:
6 ES-401, 22 of 33
ES-401 3
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401 -2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
Q#
E/APE # I Name I Safety Function K
K K
A A
G KIA Topic(s)
IR 1
2 3
1 2
000001 Continuous Rod Withdrawal I 1 0
000003 Dropped Control Rod I 1 0
000005 Inoperable/Stuck Control Rod 11 0
P00024 Emergency Boration I 1 0
P00028 Pressurizer Level Malfunction I 2 0
p00032 Loss of Source Range Ni l 7 0
p00033 Loss of Intenmediate Range Nil 7 0
000036 Fuel Handling Accident I 8 0
000037 Steam Generator Tube Leak I 3 0
000051 Loss of Condenser Vacuum I 4 0
p00059 Accidental Liquid RadWaste ReI. 19 0
P00060 Accidental Gaseous Radwaste ReI. I 9 0
boo061 ARM System Alarms 17 0
91 000067 Plant Fire On-site I 8 13 Need for emergency plant shutdown 4.4 1
92 000068 Control Room Evac. I 8 01. Ability to interpret and execute procedure steps.
4.6 1
20 000069 Loss of CTMT Integrity I 5 0
~/E 14 High Containment Pressure 15 f--
P00074 Inad. Core Cooling 14
~/E06 Degraded Core Cooling I 4 0
W/E07 Saturated Core Cooling I 4 000076 High Reactor Coolant Activity I 9 0
W/E01 Rediagnosis I 3 0
W/E02 SI Termination I 3 93
~/E13 Steam Generator Over-pressure 14 01. Ability to exptaln and appty system limits and precautions.
4.0 1
32 W/E 15 Containment Flooding I 5 0
W/E16 High Containment Radiation 19 0
90 W/E03 LOCA Cooldown - Depress. I 4 02 Adherence to appropriate procedures and operatIon Within the 4.1 1
limitations in the facllity's license and amendments W/E09 Natural Circulation Operations 14
~/ElO Natural Circulation with Steam Voide in 0
1---. lVessel wijhlwithout RVLlS. I 4
~/E08 RCS Overcooling - PTS I 4 0
KIA. Category Totals:
0 0
0 0
2 2 Group Point Total:
4 ES-401, 23 of 33
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)
Q# System # I Name I<
K K K K K A A A A G
KIA Topic(s)
IR 1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 0
004 Chemical and Volume Control I
I, 0
005 Residual Heat Removal I'
0 76 006 Emergency Core Cooling 0
- .---- High bearing temperature 3.1 1
1 007 Pressurizer Relief/Quench Tank 0
I~!
Ability to interpret control room indications to verify the 78 008 Component Cooling Water status and operatIon of a system, and understand how 4.4 1
operator actIOns and directives affect plant and system 0
80 010 Pressurizer Pressure Control
'.2, I
Spray valve failures 3.9 1
79 012 Reactor Protection 0
Faulty or erratic opemtion of detectors and function 3.2 1
5 genomtCJrs 013 Engineered Safety Features 0
IActuation
- 02. Ability to analyze the effect of maintenance activities, such 77 022 Containment Cooling 36 as degraded power sources, on the status of limiting 4.2 1
conditions for operations.
025 Ice Condenser 0
026 Containment Spray 0
039 Main and Reheat Steam 0
059 Main Feedwater 0
061 Auxiliary/Emergency Feedwater 0
062 AC Electrical Distribution 0
063 DC Electrical Distribution I
0 064 Emergency Diesel Gener'alor 0
073 Process Radiation Monitoring 0
076 Service Water 0
1<
078 Instrument Air 0
103 Containment 0
.. - -- r'-
0 IKfA Category Totals'
~o[oloI0Iol~1310101 I I 2 Group Point Total:
5 ES-401, Page 24 of 33
ES-401 5
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)
Q# System # I Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1
2 3
4 5
6 1
2 3
4 001 Control Rod Drive 0
002 Reactor Coolant 0
011 Pressurizer Level Control 0
014 Rod Position Indication 0
~15 Nuclear Instrumentation 0
016 Non-nuclear Instrumentation 0
017 In-core Temperature MOllitor 0
83 027 Containment Iodine Removal
- 02. Knowledge of the bases tn Technical Specff!cation~ tor limiting 4.2 1
25 conditions: for operations and safety lImits.
028 Hydrogen Recombiner and Purge 0
Control 81 029 Containment Purge 0
Startl~p operations Find the assocIated required valve lineups 3.1 1
3 033 Spent Fuel Pool Cooling 0
034 Fuel Handling Equipment 0
035 Steam Generator 0
041 Steam Dump/Turbine Bypass Control 0
045 Main Turbine Generator 0
055 Condenser Air Removal 0
056 Condensate 0
OC8 liquid Radwaste a
~71 Waste Gas Disposal IJ 072 Area Radiation Monitoring 0
0"15 Circul£lling Water 0
82 079 Station AII' 0
(:mS2,-connedlon wittllA~;
3.2 1
i f-- ---
086 Fire Protection I
0 I
FA Category Totals:
--GJ 0 1 0 1 0 1 0 [oED 0 1 0 I 1 IGroup f'oint Tot",!*
I'3]
=, -'
ES*401, Page 25 of 33
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 IFacility Name:
Date of Exam:
I Category KJA#
Topic RO SRO-Only
'Q#
IR IR 66 2.1. 13 Knowledge of facility requirements for controlling vital/controlled access.
2.5 1
I--
67 2.1. 05 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime 2.9 1
limitations, etc.
68
- 1.
2.1. 28 Knowledge of the purpose and function of major system components and controls.
4.1 1
Conduct of Operations 2.1.
I--
94 2.1. 36 Knowledge of procedures and limitations involved in core alterations.
4.1 1
I--
95 2.1. 42 Knowledge of new and spent fuel movement procedures.
3.4 1
Subtotal 3
2 69 2.2. 25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits 3.2 1
70 2.2. 39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.
3.9 1
- 2.
2.2.
I--
Equipment 96 Control 2.2. 19 Knowledge of maintenance work order requirements.
3.4 1
I--
97 2.2.42 Ability to recognize system parameters that are entry*level conditions for Technical Specifications.
4.6 1
I--
2.2.
Subtotal 2
2 71 2.3. 05 Ability to use radiation monitoring systems. such as fixed radiation monilors and alarms, portable survey 2.9 1
instruments, personnel monitoring equipment, etc.
I--
72 2.3. 14 Knowledge of radiation or contamination hazards that may arise during normal. abnormal, or emergency 3.4 1
conditions or activities.
I--
- 3.
2.3.
98 Radiation 2.3. 06 Ability to approve release permits.
3.8 1
Control 2.3.
2.3.
Subtotal 2
1 73 2.4. 28 Knowledge of procedures relating to a security event.
3.2 1
now eage o
- IOU' Imp emen a Ion lerarc y ana cooralna Ion wlln Omer suppa proceuures or 74 2.4. 16 guidelines slich as, operating procedures, abnormal operating procedures, and severe accident 3.5 1
. n";rt,,linp<
75
- 4.
2.4. 06 Knowledge of EOP mitigation strategies.
3.7 1
Emergency Procedures / 2.4.
I--
Plan 99 2.4. 04 Ability to recognize abnormal indIcations for system operating parameters that are entry-level condItions 4.7 1
for emergency and abnormal operating procedures.
r--
100 2.4. 23 Knowledge of the bases for priontizing emergency procedure implementation during emergency 4.4 1
operations.
Subtotal 3
2 Tier 3 Point Total 10 7
ES-401, Page 26 of 33