ML050890254
| ML050890254 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 10/19/2004 |
| From: | - No Known Affiliation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-275/05-301, 50-323/05-301, ES-401, ES-401-4 50-275/05-301, 50-323/05-301 | |
| Download: ML050890254 (28) | |
Text
ES-401 Record of Rejected K/As Form ES-401-4 Tier I Group RO TlGl RO T2G1 SRO TlGl SRO TlGl SRO TlGl SRO T1 G2 SRO T1G2 RO Randomly Selected WA APE 057 G2.4.10 076 K3.05 EPE 01 1 G2.4.36 APE 022 G2.2.18 APE 057 AA2.10 WE13 G2.2.7 APE 061 AA2.05 014 A4.03 Reason for Rejection Deleted in accordance with guidance in ES-40 1, Attachment 2, WA Elimination Guidelines At DCPP, there is no tie between Service Water (Aux Saltwater) and secondary plant cooling.
Deleted in accordance with guidance in ES-401, Attachment 2, WA Elimination Guidelines Deleted in accordance with guidance in ES-40 1, Attachment
- 2. WA Elimination Guidelines At DCPP there is no tie from Vital AC to Turbine Load Limiter Deleted in accordance with guidance in ES-401, Attachment
- 2. WA Elimination Guidelines Not testable at the SRO level Resampled, KA (Primary Coil Voltage Measurement) does not amlv to utilitv. Randomlv selected A4.04 as redacement.
ES-401 PWR Examination Outline Form ES-401-2 Facilitv:
DCPP Printed: 12/02/2004 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 (Le., the 'Tier Totals" in each WAcategory 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 +I 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 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" and "A".
Use duplicate pages for RO and SRO-only exams.
- 8. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form
- 9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
ES-401 -3.
1
PWR RO Examination Outline Printed: 12/02/2004 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 mp.
3.5 3.4 4.1 2.7 2.8 2.5 3.4*
3.8 4.4 2.7 3.7 3.4 4.0 3.4 3.5
3.4 Facility
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 i
EK2.03 - Reactor trip status panel
, &/APE # /Name / Safety Function K1 -
000007 Reactor Trip - Stabilization -
Recovery / 1 I 000008 Pressurizer Vapor Space Accident I AA2.20 - The effect of an open PORV on code safety, based on observation of plant parameters cooling, including reflux boiling 1 3 X
0000 1 1 Large Break LOCA I 3 000015/000017 RCP Malfunctions I 4 000022 Loss of Rx Coolant Makeup 12 000026 Loss of Component Cooling Water /
1 AA 1.10 - RCP ammeter and trip alarm 2.1.25 - Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.
AA2.04 - The normal values and upper limits for the temperatures of the components cooled by CCW I 000029 ATWS I 1 I EA 1.O 1 - Charging pumps EA2.06 - Shutdown margins and required boron concentrations 000038 Steam Gen. Tube Rupture / 3
' 900054 Loss of Main Feedwater / 4 AA 1.02 - Manual startup of electric and I steam-driven AFW pumps 000055 Station Blackout 1 6 EK3.O 1 - Length of time for which battery capacity is designed AK1.O1 - Principle of cooling by natural convection 000056 Loss of Off-site Power 16 000057 Loss of Vital AC Inst. Bus / 6 X 2.1.32 - Ability to explain and apply all system limits and precautions.
AK3.02 - Actions contained in EOP for loss of dc power 000058 Loss of DC Power 16 X 2.1.32 - Ability to explain and apply all I system limits and precautions.
EK2.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features WE04 LOCA Outside Containment / 3 EK3.1 - Facility operating 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 W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink 14 1
Facility:
DCPP ES - 401 KA Topic PWR RO Examination Outline Printed: 12/02/2004 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 Imp.
Points
~~
JAPE # / Name / Safety Function WE1 1 Loss of Emergency Coolant Recirc. /
4 WE12 - Steam Line Rupture - Excessive Heat Transfer / 4 K/A Category Totals:
EK2.2 - Facility's heat removal systems, 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 EK1.2 - Normal, abnormal and emergency operating procedures associated with Uncontrolled Depressurization of all Steam Generators 3.9 3.5 1
1 Group Point Total:
18 2
PWR RO Examination Outline Facility:
DCPP K1 X
X Printed: 12/02/2004 K2 X
2 1
ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2
.JAPE # I Name I Safety Function 000001 Continuous Rod Withdrawal I 1 000003 Dropped Control Rod I 1 000033 Loss of Intermediate Range NI I 7 000036 Fuel Handling Accident / 8 000060 Accidental Gaseous Radwaste Rel. I 9
00006 1 ARM System Alarms I 7 W/EOl Rediagnosis / 3 WE03 LOCA Cooldown - Depress. 14 W E 16 High Containment Radiation I 9 KIA Category Totals:
G I KATopic I Imp. 1 Points I AK2.05 - Rod motion lights I 2.9* I 1
I AK1.2 1 - Delta flux (I)
I 2.7 I 1
I 2*7 I AK1.O1 - Effects of voltage changes on performance AK3.02 - Interlocks associated with fuel 2.9 1
handling equipment AA1.02 - Ventilation system 2.9 1
AA2.04 - Whether an alarm channel is 3.1 1
functioning properly EK3.3 - Manipulation of controls 3.5 1
required to obtain desired operating results during abnormal, and emergency situations to perform specific 3.9 1
system and integrated plant procedures during all modes of plant operation.
X 2.4.19 - Knowledge of EOP layout, 2.7 1
symbols, and icons.
2 Group Point Total:
9 1
PWR RO Examination Outline Facility:
DCPP KA Topic K4.07 - Minimizing RCS A4.17 - Deborating demineralizer Imp. Points 3.2 1
Printed: 12/02/2004 leakage (mechanical seals)
JS2.01 - Boric acid makeup DUmDS Form ES-401-2 I
I 2.9 1
K6.03 - RHR heat I 2.5 I 1
2.7 I operator response to loss of all annunciators.
A2.03 - Overpressurization of the PZR K3.03 - RCP 2.2.13 -Knowledge of tagging and clearance I
3.6 4.1 3.6 I
exchanger 2.4.32 - Knowledge of K1.02 - ESFAS procedures.
K6.02 - PZR K5.01-DNB K5.01 - Definitions of safety train and ESF channel A 1.02 - Containment Dressure 3.3 3.2 1
3.3*
1 2.8 1
3.6 1
K2.0 1 - Major system loads A2.01 - Grounds 1
3.3 1
2.5 1
1 1 -
A3.10 - Function of ED/G I megawatt load controller 2.8 1
2.4.34 - Knowledge of RO tasks performed outside the main control room during emergency operations including system geography and system implications.
K4.0 1 - Source of water for CSS, including recirculation Dhase after LOCA 3.8 4.2 Al.05 - RCS T-ave I 3.2* I 1
~
A4.03 - MFW pump turbines 2.8* I 1 K3.04 - RCS I 3.6 I 1 K5.05 - Feed line voiding 2.7 and water hammer I
1 A3.03 - Indicating lights, meters, and recorders 3*4 I I
1
PWR RO Examination Outline K4 X
Facility:
DCPP K5 K6 3
3 2
FS - 401 Sys/Evol # / Name K1 K2 k1 073 Process Radiation Monitoring A2 A3 X
2 3
2 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air I
I I 103 Containment K/A Category Totals: 212 Plant Systems - Tier 2 / Group 1 Printed: 12/02/2004 Form ES-401-2 KA Topic Imp. Point 3.6 1
K1.O1 - Those systems served by PRMs A4.02 - Radiation 3.7 1
monitoring system control Dane1 K3.05 - RHR components, 3.0*
1 controls, sensors, indicators, and alarms, including rad monitors K4.01 -ManuaVautomatic 1 32.J7" I transfers of control A2.03 - Phase A and B isolation Group Point Total:
28 2
Facility: DCPP PWR RO Examination Outline Printed: 12/02/2004 Form ES-401-2 KA Topic Imp. Points K6.13 - Location and operation of RPIS position prior to startup K3.01-RCS 3.4*
1 K2.01 - Hydrogen 2.5*
1 recombiners Al.03 - Containment 3.0*
1 pressure, temperature, and humidity general operating crew responsibilities during emergency operations.
A2.02 - Steam valve stuck 3.6 1
open K4.01 - Safety and 3.4 1
environmental precautions for handling hot, acidic, and radioactive liquids changes with source distance K1.08 - Emergency/essential 3.2*
1 sws 2.4.12 - Knowledge of 3.4 1
K5.02 - Radiation intensity 2.5 1
Group Point Total:
10 1
Generic Knowledge and Abilities Outline (Tier 3)
PWR RO Examination Outline 2.1.10 Facilitv:
DCPP Knowledge of conditions and limitations in the 2.7 1
facility license.
Printed: 12/02/2004 Form ES-401-3 2.1.29 KA KA ToDic ImD. Points Generic Category I
I I
I Knowledge of how to conduct and verify valve 3.4 1
lineups.
Conduct of Operations Equipment Control 2.2.28 Knowledge of new and spent fuel movement procedures.
2.2.33 Knowledge of control rod programming.
2.6 1
2.5 1
1 2.1.2 1 I Ability to obtain and verify controlled procedure cow.
Radiation Control I 2.3.1 1 Knowledge of 10 CFR: 20 and related facility 1
2.6 radiation control reauirements.
1 I 2.3.2 I Knowledge of facility ALARA program.
I 2.5 I
2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Category Total:
2.5 1
3 Emergency Proceduresh'lan 2.4.12 Knowledge of general operating crew responsibilities during emergency operations.
Ability to prioritize and interpret the significance of each annunciator or alarm.
2.4.45 Category Total:
2 Generic Total:
10 1
d 0
0 (u
0 Q?
2 -.
x U
0
.I I
.I 2
.1
?
d 2
\\o k3 CL 0
n cu 0
v) 8 c;l 00 Vl 0
0 0
0 00 --.
.h 4
EI Y
a 5 2 8
U cu 0
v) cl Vl v) 0 0
0 0
3
.e m
cd Y
P il 6
8 E $
W cu 0
cn 8 cl 3
E
3 i?
s 2 g
I
.3 Y
cd N
.3 -
3; c=
8 I a
.e Y
0 2
P 0
0 0
0 0
m.
Y E 9 Y
8 &
ki 5
3 0
- 0) a m
N
.3 v) v)
W 00 0
0 0
0 0
i 3
0 0
8 d
.e z 2
3 2
ti 0
PI 2
0 0
0 0
m 0
0 0
0
\\
3 hl a
s.
4 E
B s
2 Y -
0 44 0
m B
8 Ll N
N 0
0 00 b
W Y s s
E 8 00 0
.fr 3
ti a
u cu 0
m r; Ll
\\o rJ 0
0 0
0
\\o --.
ti 3 -
a g
3; ti cd rg m
0 0
0 0
\\o.
ki PI
.s 0
P) v)
rc, 0
m B
8 Ll
\\D m
0 0
e 3
a 2
8 8
3 u
B a
E m
0 0
0 0
0 m -.
3 I
c-
?
3 4 8 Y
G cd 0
3 3
8 c.'
0 l n
3 3
I
CJ n
.w I u
m
c I
c L
s I
+
3 s
+
S Q
B n
3 1
0 d
CA w 2,
a
.H W
cI1 0 a
.I 2
0 e
m Y
g F
gJ d
0 Y
ea..
I m
Y g
k gJ 3
0 Y
1 e
c) e 8
2 E
0 m
.I Y
.I E
ES-401 PWR Examination Outline Form ES-401-2 Facilitv:
DCPP Date Of Exam:
02/07/2005 Printed: 12/02/2004 I
I I
RO K/A 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 *I 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 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" 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
- 9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
1
PWR SRO Examination Outline Printed: 12/02/2004 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 K/A Category Totals:
Facility:
KA Topic E/APE # / Name / Safety Function I K1 Imp.
3.7 Points 00001 1 Large Break LOCA 1 3 2.2.25 - Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
1 000022 Loss of Rx Coolant Makeup I 2 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
4.0 1
000025 Loss of RHR System I 4 AA2.02 - Leakage of reactor coolant fiom RHR into closed cooling water system or into reactor building atmosphere 3.8 1
000026 Loss of Component Cooling Water / I 8
AA2.06 - The length of time after the loss of CCW flow to a component before that component may be damaged 3.1*
1 000054 Loss of Main Feedwater / 4 AA2.01 - Occurrence of reactor andor turbine trip 4.4 3.6 000057 Loss of Vital AC Inst. Bus I 6 AA2.14 - That substitute power sources have come on line on a loss of initial ac Group Point Total:
6 1
Facility: DCPP ES - 401 K1 PWR SRO Examination Outline Printed: 12/02/2004 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 K2 K3 0
0 0
EIAPE # I Name I Safety Function A1 000061 ARM System Alarms / 7 A2 X
X X
0 3
WE02 SI Termination / 3 WE09 Natural Circ. / 4 WE13 Steam Generator Over-pressure / 4 KIA Category Totals:
G KATopic Imp.
Points AA2.05 - Need for area evacuation; check against existing limits EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations should be reported to outside agencies.
Group Point Total:
1
Facility:
DCPP ES - 401 Sys/Evol # / Name K1 A2 A3 X
X X
3 0
0 003 Reactor Coolant Pump A4 005 Residual Heat Removal I G
X X
2 010 Pressurizer Pressure Control I
KATopic Imp.
A2.05 - Effects of VCT 2.8 pressure on RCP seal leakoff flows 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.
A2.03 - PORV failures 4.2 A2.04 - Loss of service 3.2 water 2.2.22 - Knowledge of 4.1 limiting conditions for operations and safety limits.
3.6 Group Point Total:
022 Containment Cooling 076 Service Water WA Category Totals: -
0 PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Printed: 12/02/2004 Form ES-401-2
PWR SRO Examination Outline Facility:
DCPP Sys/Evol# I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp.
01 1 Pressurizer Level Control X
A2.05 - Loss of PZR heaters 3.7 014 Rod Position Indication X 2.4.10 - Knowledge of 3.1 034 Fuel Handling Equipment X
A2.01 - Dropped fuel 4.4 annunciator response procedures.
element Printed: 12/02/2004 Points 1
1 1
WACategory Totals:
0 0
1 0
0 0
0 0
2 0
0 1
Group Point Total:
3
Generic Knowledge and Abilities Outline (Tier 3)
PWR SRO Examination Outline Conduct of Operations Equipment Control Printed: 12/02/2004 2.1.10 Knowledge of conditions and limitations in the 3.9 1
2.1.22 Ability to determine Mode of Operation.
3.3 1
Category Total:
2 2.2.27 Knowledge of the refueling process.
3.5 1
Category Total:
1 facility license.
Facilitv:
DCPP Form ES-401-3 2.3.4 I 3*1 I Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Radiation Control 2.3.8 Emergency ProceduresL'lan Knowledge of the process for performing a 3.2 1
planned gaseous radioactive release.
I I
I 2.4.41 2.4.45 Knowledge of the emergency action level thresholds and classifications.
Ability to prioritize and interpret the significance of each annunciator or alarm.
Category Total:
2 Generic Total:
7 1
r c
a E
c:
\\
r L
.C c 0
P
.I c1
?
u' 3
3 3
0 3 2
ru 0
rn B
8 c) cu cu 0
0 d
3 00 -.
4 a,
Y 0 3 rn B
c)
\\o cu 0
0 8
e 0
.I 2
m --.
Y cd c
3 c-
a2 3
0
n ccr b
- 9) am e N
c1 m
CI' d
P c
rl I
m c) z k
P d
0 c,
N I
m c) z k
P s
0 c) b m
c, 0
L a2
.I d
3