ML050890250
| ML050890250 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/21/2005 |
| From: | - No Known Affiliation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-275/05-301, 50-323/05-301, ES-401, ES-401-2 50-275/05-301, 50-323/05-301 | |
| Download: ML050890250 (27) | |
Text
~
ES-401 PWR Examination Outline Form ES-401-2 Facilitv: DCPP Printed: 01/21/2005 Date Of Exam: 02/07/2005 I I RO wA Category Point! I SRO-Only Points Note:
- 1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the 'Tier Totals" in each WA category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the 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 +fromI 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 WA topics from a given system 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) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
- 7. On the following pages, enter the WA 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 columns labeled " K f and "A".
Use duplicate pages for RO and SRO-only exams.
- 8. Far Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
- 9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
1
~
PWR RO Examination Outline Printed: 01/21/2005 Facility: DCPP ES - 401 -
Emergency and Abnormal Plant Evolutions Tier 1/ Group 1 Form ES-401-2
' TJAPE # / Name I Safety Function
~
I K1 KA Topic EK2.03 - Reactor trip status panel I 000007 Reactor Trip - Stabilization -
Recovery / 1 I 000008 Pressurizer Vapor Space Accident /
II AA2.20 - The effect of an open PORV on code safety, based on observation of 13 plant parameters 0000 11 Large Break LOCA I 3 X EK1.O1 - Natural circulation and cooling, including reflux boiling 000015/000017 RCP Malfunctions / 4 AA 1.10 - RCP ammeter and trip alarm 2.7 I 000022 Loss of Rx Coolant Makeup / 2 2.1.25 - Ability to obtain and interpret 2.8 1 station reference materials such as graphs, monographs, and tables which contain performance data.
000026 Loss of Component Cooling Water I AA2.04 - The normal values and upper 2.5 1 limits for the temperatures of the components cooled by CCW
)000029 ATWS I 1 EA1.O1 - Charging pumps 3.4* 1 000038 Steam Gen. Tube Rupture 1 3 EA2.06 - Shutdown margins and 3.8 1 required boron concentrations AA1.02 - Manual startup of electric and 4.4 1 steam-driven AFW pumps 10055 Station Blackout / 6 EK3.01 - Length of time for which 2.7 1 battery capacity is designed AK1 .O 1 - Principle of cooling by natura 3.7 1 convection 2.1.32 - Ability to explain and apply all 3.4 1 system limits and precautions.
AK3.02 - Actions contained in EOP for 4.0 1 loss of dc power I
000065 Loss of Instrument Air I 8 2.1.32 - Ability to explain and apply all 3.4 1 system limits and precautions.
WE04 LOCA Outside Containment / 3 EK2.1 - Components, and functions of 3.5 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features EK3.1 - Facility operating 3.4 1 characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics 1
PWR RO Examination Outline Printed: 0 1/2 1/2005 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2
' "/APE # / Name / Safety Function K1
- 41 A2 G KATopic EK2.2 - Facility's heat removal systems, mp.
3.9 Points 1
WE1 1 Loss of Emergency Coolant Recirc. /
4 including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility WE12 - Steam Line Rupture - Excessive X EK1.2 - Normal, abnormal and 3.5 1 Heat Transfer / 4 emergency operating procedures associated with Uncontrolled Depressurization of all Steam Generators K/A Category Totals: 3 3 3 31 Group Point Total: 18 2
PWR RO Examination Outline Printed: 01/21/2005 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 KA Topic 000001 Continuous Rod Withdrawal I 1 I AK2.05 - Rod motion lights 000003 Dropped Control Rod I 1 AK1.21 - Delta flux (I)
I X 000033 Loss of Intermediate Range NI I 7 X AK1.01 - Effects of voltage changes on performance 000036 Fuel Handling Accident I 8 AK3.02 - Interlocks associated with fuel handling equipment 000060 Accidental Gaseous Radwaste Rel. / AA1.02 - Ventilation system 9
000061 ARM System Alarms 17 I AA2.04 - Whether an alarm channel is functioning properly W E 0 1 Rediagnosis I 3 EK3.3 - Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations WE03 LOCA Cooldown - Depress. 1 4 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.
W E 16 High Containment Radiation / 9 2.4.19 - Knowledge of EOP layout, symbols, and icons.
KIA Category Totals: 2 Group Point Total: 9 1
PWR RO Examination Outline Printed: 01/21/2005 Facility: DCPP ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 I
Cys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. Points 003 Reactor Coolant Pump X K4.07 - Minimizing RCS 3.2 1 leakage (mechanical seals) 004 Chemical and Volume Control X K2.01 - Boric acid makeup 2.9 1 Pumps 004 Chemical and Volume Control X A4.17 - Deborating 2.7 1 demineralizer ~
005 Residual Heat Removal X K6.03 - RHR heat 2.5 1 exchanger 006 Emergency Core Cooling X K1.02 - ESFAS 4.3 1 006 Emergency Core Cooling X K6.03 - Safety Injection 3.6 1 Pumps 007 Pressurizer RelieUQuench X A2.03 - Overpressurization 3.6 1 Tank of the PZR 008 Component Cooling Water X K3.03 - RCP 4.1 1 008 Component Cooling Water X 2.2.13 - Knowledge of 3.6 1 tagging and clearance procedures.
010 Pressurizer Pressure Control X K6.02 - PZR 3.2 1 0 12 Reactor Protection X K5.01 - DNB 3.3* 1 013 Engineered Safety Features X K5.01 - Definitions of safety 2.8 1 Actuation train and ESF channel 022 Containment Cooling X A 1.02 - Containment 3.6 1 pressure 022 Containment Cooling X 2.4.34 - Knowledge of RO 3.8 1 tasks performed outside the main control room during emergency operations including system geography and system implications.
026 Containment Spray X K4.01 - Source of water for 4.2 1 CSS, including recirculation phase after LOCA 039 Main and Reheat Steam X Al.05 - RCS T-ave 3.2* 1 039 Main and Reheat Steam X A4.03 - MFW pump 2.8* 1 turbines 059 Main Feedwater X K3.04 - RCS 3.6 1 06 1 AuxiliaryBmergency X K5.05 - Feed line voiding 2.7 1 Feedwater and water hammer 062 AC Electrical Distribution X K2.01 - Major system loads 3.3 1 063 DC Electrical Distribution X K3.01 - ED/G 3.7* 1 064 Emergency Diesel Generator X A3.10 - Function of ED/G 2.8 1 megawatt load controller 064 Emergency Diesel Generator X A3.03 - Indicating lights, 3.4 1
~
~ ~
meters, and recorders 073 Process Radiation Monitoring x K1.O1 - Those systems 3.6 1 1
PWR RO Examination Outline Printed: 01/21/2005 Facility: DCPP ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 I I I 3ys/Evol# / Name K1 K2 K3 K 4 073 Process Radiation Monitoring A4.02 - Radiation monitoring system control panel 076 Service Water X K3.05 - RHR components, 3.0* 1 controls, sensors, indicators, and alarms, including rad monitors 078 Instrument Air X K4.01 - ManuaVautomatic 2.7 1 transfers of control 103 Containment A2.03 - Phase A and B 3.5* 1 isolation K/A Category Totals: 2 4 3 2 Group Point Total: 28 2
ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 I
Cys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. Points 00 1 Control Rod Drive X K6.13 - Location and 3.6 1 operation of RPIS 014 Rod Position Indication X A4.04 - Re-zeroing of rod 2.7 1 position prior to startup 016 Non-nuclear Instrumentation X K3.01- RCS 3.4* 1 028 Hydrogen Recombiner and X K2.01 - Hydrogen 2.5* 1 Purge Control recombiners 029 Containment Purge X A1.03 - Containment 3.0* 1 pressure, temperature, and humidity 034 Fuel Handling Equipment X 2.4.12 - Knowledge of 3.4 1 general operating crew responsibilities during emergency operations.
041 Steam Dump/Turbine Bypass X A2.02 - Steam valve stuck 3.6 1 Control open 068 Liquid Radwaste X K4.01 - Safety and 3.4 1 environmental precautions for handling hot, acidic, and radioactive liquids 072 Area Radiation Monitoring X K5.02 - Radiation intensity 2.5 1 changes with source distance I 075 Circulating Water X K1.08 - Emergency/essential 3.2* 1 sws WACategoryTotals: 1 1 1 1 1 1 1 1 0 1 1 Group Point Total: 10 1
Generic Knowledge and Abilities Outline (Tier 3)
PWR RO Examination Outline Printed: 01/21/2005 Facility: DCPP Form ES-401-3 Generic CatePorv -
~~ ~~~
Conduct of Operations 2.1.10 Knowledge of conditions and limitations in the 2.7 1 facility license.
2.1.21 Ability to obtain and verify controlled procedure 3.1 1 COPY.
2.1.29 Knowledge of how to conduct and verify valve 3.4 1 lineups.
I Category Total: 3 Equipment Control 2.2.28 Knowledge of new and spent fuel movement 2.6 1 procedures.
2.2.33 Knowledge of control rod programming. 2.5 1 Category Total: 2 4
Radiation Control 2.3.1 Knowledge of 10 CFR: 20 and related facility I 2.6 I 1 I I radiation control requirements.
I I I 2.3.2 I
Knowledge of facility ALARA program.
I I
2*5 I I
I I
2.3.4 Knowledge of radiation exposure limits and 2.5 1 contamination control, including permissible levels in excess of those authorized.
I I I I Emergency ProceduresRlan 2.4.12 Knowledge of general operating crew responsibilities during emergency operations.
2.4.45 Ability to prioritize and interpret the significance 3.3 1 of each annunciator or alarm.
Generic Total: 10 1
\
rl L
a3 FI 3
?
3 d
\o m u 8 L 1 cd 3 ;
5 -8a, s F4 .+
ua, e
.3 3 8M ia, cu 0
rcr 0
M v1 M 2
c) 3 3 4 4 3
3 0
0 z
0
\o 10 0
0 0 0 0 0 0 0 0
3 m
Y 8
E a,
8E 3;
3 m
ru 0
13 0
.4 Y
cd N
.4 k
2 m
2 B
L3
'1
?
2c 3 3
00
.b
--.d W
Y a
u 95 a U 4
3 rr 0
rr 0 ru 0
a m B
m m cl 00 3
m cl 3
vl \D 3 0 0 0 0 @
0 0
0 0 s
c
.a.
3
-2 u
g M 4
3 pi Ea M
0 0
0 0
0
3 4
3\
n 3
u
.C C
d 7
?
d 2
3 3
U 0 m c1 rc, c1 c!
3 c! I
.. n
..a I
.. I m
i Y
m Y Y 0 Y 0
.. ;1 ;1 ;I 0
e 0
F 0
F 0
Y t! M a,
Y t!
Y
!?
Y Y
3 3 d 3 E
a, E
2 u
V
.C a
2 i4 F
0 Y
t!
3u
. I L
a, c3
~~
ES-401 PWR Examination Outline Form ES-401-2 Facilitv: DCPP Printed: 01/21/2005 Date Of Exam: 02/07/2005 I I I RO wA Category Point! I SRO-Only Points Note:
- 1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the 'Tier Totals" in each WA category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the 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 +from I 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 WA topics from a given system 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) WAS in Tiers Iand 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
- 7. On the following pages, enter the WA 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 columns labeled "K" and "A".
Use duplicate pages for RO and SROanly exams.
- 8. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
- 9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
1
PWR SRO Examination Outline Printed: 0112112005 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2
' VJAPE # I Name I Safety Function K1 KA Topic [mp. Points 0000 11 Large Break LOCA I 3 2.2.25 - Knowledge of bases in 3.7 technical specifications for limiting conditions for operations and safety limits.
000022 Loss of Rx Coolant Makeup 1 2 2.1.33 - Ability to recognize indications 4.0 for system operating parameters which are entry-level conditions for technical specifications.
000025 Loss of RHR System 1 4 AA2.02 - Leakage of reactor coolant 3.8 from RHR into closed cooling water system or into reactor building atmosphere 000026 Loss of Component Cooling Water I AA2.06 - The length of time after the 3.1*
8 loss of CCW flow to a component before that component may be damagec 000054 Loss of Main Feedwater 1 4 AA2.01 - Occurrence of reactor and/or 4.4 turbine trip 000057 Loss of Vital AC Inst. Bus 1 6 AA2.14 - That substitute power sources 3.6 have come on line on a loss of initial ac KIA Category Totals: 0 Group Point Total: 6 1
PWR SRO Examination Outline Printed: 01/21/2005 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2
' v,/APE # / Name / Safety Function K3 A1 42 G KA Topic u00061 ARM System Alarms / 7 X AA2.05 - Need for area check against existing limits WE02 SI Termination / 3 X EA2.1 - Facility conditions and 4.2 1 selection of appropriate procedures during abnormal and emergency operations I I EA2.1 - Facility conditions and WE09 Natural Circ. 1 4 X 3.8 1 selection of appropriate procedures during abnormal and emergency operations W E 13 Steam Generator Over-pressure / 4 X 2.4.30 - Knowledge of which events 3.6 I related to system operations/status should be reported to outside agencies.
0 0 3 1 Group Point Total: 4 1
PWR SRO Examination Outline Printed: 01/21/2005 Facility: DCPP ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2
' Yys/Evol # / Name K1 A3 A4 KA Topic I Imp. Points I
003 Reactor Coolant Pump A2.05 - Effects of VCT pressure on RCP seal leakoff flows 2.8 005 Residual Heat Removal 2.4.45 - Ability to prioritize 3.6 1 and interpret the significance of each annunciator or alarm.
0 10 Pressurizer Pressure Control A2.03 - PORV failures 4.2 I 1 I 022 Containment cooling I A2.04 - Loss of service water 076 Service Water 2.2.22 - Knowledge of limiting conditions for operations and safety limits.
K/A Category Totals: 0 0 0 Group Point Total: 5 1
PWR SRO Examination Outline Printed: 01/21/2005 Facility: DCPP
' Cys/Evol # / Name 01 1 Pressurizer Level Control K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic X
Imp. Points A2.05 - Loss of PZR heaters 3.7 1 0 14 Rod Position Indication X 2.4.10 - Knowledge of 3.1 1 annunciator response procedures.
034 Fuel Handling Equipment X A2.0 1 - Dropped fuel 4.4 1 element K/A Category Totals: I O 1 O 1 O1 O 1 O 1 O I O 1 21 O 1 O I 1 1 Group Point Total:
3 1 1
Generic Knowledge and Abilities Outline (Tier 3)
PWR SRO Examination Outline Printed: 0 1/21/2005 Facilitv: DCPP Form ES401-3 Conduct of Operations 2.1.10 Knowledge of conditions and limitations in the 3.9 1 facility license.
2.1.22 Ability to determine Mode of Operation. 3.3 1 Equipment Control 2.2.27 Knowledge of the refueling process.
I 3.5 I I I Category Total: 1 Radiation Control 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
2.3.8 Knowledge of the process for performing a planned gaseous radioactive release.
Category Total: 2 Emergency Proceduresfflan 1 2.4.41 1 Knowledge of the emergency action level thresholds and classifications.
1 1 4.1 1 2.4.45 Ability to prioritize and interpret the significance 3.6 1 of each annunciator or alarm.
Generic Total: 7 1
- I
\
d2
. I H
rl
?
3 4
cu a
i?
-3 Ew E:
3 l
d s 0 2
- 0 m
B cl 3
0 0
0 0
rn
IC C
c Q
3 c!
3 0
x..
i n
3
'3 3 i
0 e4 1 e4 e4 t-jw: I
.. n
.. n.. n I
3 Q Q Q Q Q 0 U U U U U g ;I g g gu h
L 0
2.
0 2.
0 2.
0 L
I a2 4 4 4 4 U
4 Y
4 U
4 U
4 9 a
a x
q..
u cr