ML021070350
| ML021070350 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/18/2002 |
| From: | Diane Jackson NRC/RGN-I/DRS/OSB |
| To: | Conte R Public Service Enterprise Group |
| Conte R | |
| References | |
| 05000354/2002-301 05000354/2002-301 | |
| Download: ML021070350 (33) | |
Text
Outline Changes Original Exam New Exam Original KA Level New KA Level Reason 201006G449 S
201006G1 12 S
KA 201006G2.4.49 (Rod Worth Minimizer - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls) is too similar to KA 295015 K3.01 (Knowledge of the reason for the following responses as they apply to INCOMPLETE SCRAM. - Bypassing rod insertion blocks).
Both would test bypassing of the Rod Worth Minimizer during an ATWS.
Random selected generic 2.1.12 to replace.
226001A107 R
226001A106 R
Original KA 226001 A1.07 Ability to predict and or monitor changes in parameters associated with operating the RHRJLPCI Containment Spray System Mode controls including: System pressure.
Hope Creek does not have RHR containment Spray System pressure indications; only flow indications.
KA changed to A1.06 System flow as plant priority 226001A302 B
226001A305 B
Original KA 226001 A3.02 Ability to monitor automatic operations of the RHRJLPCI Containment Spray System Mode including: System pressure.
Hope Creek does not have RHR containment Spray System pressure indications; only flow indications.
Use A3.05 Containment pressure instead as plant priority 295015G206 S
295015G304 S
Original KA 295015 G2.2.6 (INCOMPLETE SCRAM Knowledge of the process for making changes in procedures as described in the safety analysis report) is too similar to 215004 G2.2.6 (SOURCE RANGE MONITORING SYSTEM Knowledge of the process for making changes in procedures as described in the safety analysis report)
Random picked generic category 2.3.4 for 215004.
290001Gill S
264000G111 5
No one hour Tech Specs for secondary containment other than 3.0.3. Change to Emergency Diesel Generators 264000 as plant priority.
Friday, January 11, 2002 Page I of I
ES-401 BWR RO Examination Outline Facility:
Hope Creek Generating Station Exam Date: 03/12/2002 Printed: 01/08/2002 Form ES-401-2 Exam Level: RO Group K/A Category Points KI K2 K3 K4 K5 K6 Al 1
2 3
4
- 1.
Emergency 2
5 3
3 Abnormal Plant 3
0 1
1 Evolutions Totals 7
7 8
Tier
- 2.
Plant Systems 2
2 3
2 3
2 4
1 7
3 A2 A3 A4 1
3 1
5 2
2 G
0 2
Point Point Total 13 19 4
36 28 2
1 2
2 2
2 3
2 2
2 1
0 19 3
1 0
1 0
0 0
1 1
0 0
0 4
Tier Totals 5
4 5
5 4
6 6
5 5
3 51 Cat I Cat 2 Cat 3 Cat 4
- 3. Generic Knowledge And Abilities 3
3 4
313 Note:
- 1. Attempt to distribute topics among all K/A Categories; select at least one topic from every K/A category within each tier.
- 2. Actual point totals must match those specified in the table.
- 3. Select topics from many systems; avoid selecting more than two or three K/A 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.
Tier I
(
Hope Creek Generating Station BWRR4
.ýamination Outline Emergency and Abnormal Plant Evolutions - Tier I / Group 1
/P Printed:
01/0(.
)2 Form ES-401-2 E/APE #
E/APE Name / Safety Function Ki K2 K3 Al A2 G KA Topic Imp.
Points 295006 SCRAM / I X
AK1.01 - Decay heat generation and removal.
3.7 1
295006 SCRAM / I X 2.1.28 - Knowledge of the purpose and function of 3.2 1
major system components and controls.
295007 High Reactor Pressure / 3 X
AK3.04 - Safety/relief valve operation: Plant-Specific 4.0 1
295007 High Reactor Pressure / 3 X
AK2.05 - Shutdown cooling: Plant-Specific 2.9 1
295010 High Drywell Pressure / 5 X
AAI.02 - Drywell floor and equipment drain sumps 3.6 1
295014 Inadvertent Reactivity Addition / 1 X
AK3.01 - Reactor SCRAM 4.1*
1 295014 Inadvertent Reactivity Addition / 1 X
AK2.04 - Void concentration 3.2 1
295015 Incomplete SCRAM / 1 X
AK3.01 - Bypassing rod insertion blocks 3.4 1
295024 High Drywell Pressure / 5 X
EAL.10 - A.C. distribution 3.4 1
295025 High Reactor Pressure / 3 X
EA2.06 - Reactor water level 3.7 1
295025 High Reactor Pressure / 3 X
EKI.05 - tExceeding safety limits 4.4*
1 295031 Reactor Low Water Level / 2 X
EK2.13 - ARI/RPT/ATWS: Plant-Specific 4.1 1
500000 High Containment Hydrogen Concentration / 5 X
EK3.03 - Operation of hydrogen and oxygen 3.0 1
recombiners KIA Category Totals:
2 3
4 2
1 1
Facility:
ES - 401 Group Point Total:
13 I
h Hope Creek Generating Station BWR k, camination Outline Printed:
0 l/d!
32 Emergency and Abnormal Plant Evolutions - Tier I / Group 2 E/APE #
E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.
Points 295001 Partial or Complete Loss of Forced Core Flow X
AA1.02 - RPS 3.3 1
Circulation / 1 295002 Loss of Main Condenser Vacuum / 3 X
AK1.04 - Increased offgas flow 3.0 1
295003 Partial or Complete Loss of A.C. Power / 6 X 2.4.9 - Knowledge of low power / shutdown 3.3 1
implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
295003 Partial or Complete Loss of A.C. Power / 6 X
AA2.02 - Reactor power, pressure, and level 4.2*
1 295004 Partial or Complete Loss of D.C. Power / 6 X
AK3.03 - Reactor SCRAM: Plant-Specific 3.1 1
295008 High Reactor Water Level / 2 X
AK3.04 - Reactor feed pump trip: Plant-Specific 3.3 1
295008 High Reactor Water Level / 2 X
AA1.01 - Reactor water level control: Plant-Specific 3.7 1
295012 High Drywell Temperature / 5 X
AK1.01 - Pressure/temperature relationship 3.3 1
295013 High Suppression Pool Temperature / 5 X
AK2.01 - Suppression pool cooling 3.6 1
295016 Control Room Abandonment / 7 X
AAl1.02 - Reactor/turbine pressure regulating system 2.9*
1 295019 Partial or Complete Loss of Instrument Air / 8 X
AA2.01 - Instrument air system pressure 3.5 1
295019 Partial or Complete Loss of Instrument Air / 8 X
AA 1.02 - Instrument air system valves: Plant-Specific 3.3 1
295022 Loss of CRD Pumps / 1 X
AK2.03 - Accumulator pressures.
3.4 1
295026 Suppression Pool High Water Temperature / 5 X
EKI.02 - Steam condensation 3.5 1
295028 High Drywell Temperature / 5 X
EK1.02 - Equipment environmental qualification 2.9 1
Facility:
Facility:
hope Creek Generating Station ES - 401 BWR Rk ramination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 K/A Category Totals:
5 3
3 4
3 1
Group Point Total:
19 2
Form ES-401-2 E/APE #
E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.
Points 295030 Low Suppression Pool Water Level / 5 X
EK2.03 - LPCS 3.8 1
295038 High Off-Site Release Rate / 9 X
EA2.03 - tRadiation levels 3.5*
1 295038 High Off-Site Release Rate / 9 X
EK1.02 - tProtection of the general public 4.2*
1 600000 Plant Fire On Site / 8 X
AK3.04 - Actions contained in the abnormal procedure 2.8 1
1__1_,___
for plant fire on site I
Printed:
0140
)2
(
Facility:
lhoupe Creek Generating Station ES - 401 BWR R(*'
amination Outline Emergency and Abnormal Plant Evolutions - Tier I / Group 3 K/A Category Totals:
0 1
1 1
1 0
Printed:
01/1(
)2 Form ES-401-2 Group Point Total:
4 E/APE #
E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.
Points 295023 Refueling Accidents / 8 X
AA2.05 - tEntry conditions of emergency plan 3.2 1
295023 Refueling Accidents / 8 X
AA1.02 - Fuel pool cooling and cleanup system 2.9 1
295036 Secondary Containment High Sump/Area Water X
EK3.01 - Emergency depressurization 2.6 1
Level / 5 1
295036 Secondary Containment High Sump/Area Water X
EK2.01 - Secondary containment equipment and floor 3.1 1
Level / 5 drain system I
I
mination Outline Printed:
0 1i
'002 Hope Creek Generating Station Plant Systems - Tier 2 / GrouD 1 Sys/Ev #
System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.
Points 201001 Control Rod Drive Hydraulic System /
X A3.05 - Reactor water level 2.8 1
201002 Reactor Manual Control System / I X 2.4.21 - Knowledge of the parameters and logic 3.7 1
used to assess the status of safety functions including:
1.Reactivity control 2.Core cooling and heat removal 3.Reactor coolant system integrity 4.Containment conditions 5.Radioactivity release control.
201002 Reactor Manual Control System / 1 X
K4.08 - Continuous In rod insertion 3.2 1
202002 Recirculation Flow Control System / 1 X
K6.04 - Feedwater flow inputs: BWR-3, 4, 5,6 3.5 1
203000 RHR/LPCI: Injection Mode (Plant X
K1.14 - Shutdown cooling system:
3.6 1
Specific) / 2 Plant-Specific 203000 RHR/LPCI: Injection Mode (Plant X
A4.07 - Reactor water level 4.5*
1 Specific) / 2 206000 High Pressure Coolant Injection X
A3.07 - Lights and alarms: BWR-2, 3, 4 3.9 1
System / 2 206000 High Pressure Coolant Injection X
A1.06 - System flow: BWR-2, 3, 4 3.8 1
System / 2 209001 Low Pressure Core Spray System / 2 X
K2.02 - Valve power 2.5*
1 209001 Low Pressure Core Spray System / 2 X
K 1.10 - Emergency generator 3.7 1
I Facility:
BWR RO in rination Outline Facility:
Hope Creek Generating Station Plant Systems - Tier 2 / Group I Form ES-401-2 Sys/Ev #
System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.
Points 211000 Standby Liquid Control System / I X 2.4.10 - Knowledge of annunciator response 3.0 1
procedures.
211000 Standby Liquid Control System / 1 X
K1.05 - RWCU 3.4 1
212000 Reactor Protection System / 7 X 2.1.23 - Ability to perform specific system and 3.9 1
integrated plant procedures during different modes of plant operation.
212000 Reactor Protection System / 7 X
K5.02 - Specific logic arrangements 3.3 1
215004 Source Range Monitor (SRM) System X
A3.03 - RPS status 3.6 1
/7 215005 Average Power Range Monitor/Local X
K5.05 - Core flow effects on APRM trip 3.6 1
Power Range Monitor System / 7 setpoints 215005 Average Power Range Monitor/Local X
K3.05 - Reactor power indication 3.8 1
Power Range Monitor System / 7 216000 Nuclear Boiler Instrumentation / 7 X
K2.01 - Analog trip system: Plant-Specific 2.8 1
216000 Nuclear Boiler Instrumentation / 7 X
A2.08 - Elevated containment temperature 3.2 1
217000 Reactor Core Isolation Cooling X
K4.05 - Prevents radioactivity release to 3.2 1
System (RCIC) /2 auxiliary/reactor building 217000 Reactor Core Isolation Cooling X
A2.01 - System initiation signal 3.8 1
System (RCIC) / 2 223001 Primary Containment System and X
K6.13 - Applicable plant air system! nitrogen 3.2 1
Auxiliaries / 5 make-up system.
2 ES - 401 Printed:
01(
002
mination Outline Hope Creek Generating Station Plant Systems - Tier 2 / Group I K/A Category Totals:
3 2
2 3
2 3
3 2
3 2
3 Form ES-401-2 Group Point Total:
28 3
Facility:
ES - 401 Sys/Ev #
System /Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.
Points 223002 Primary Containment Isolation X
K3.16 - Shutdown cooling system/RHR 3.2 1
System/Nuclear Steam Supply Shut-Off/ 5 223002 Primary Containment Isolation X
K4.01 - Redundancy 3.0 1
System/Nuclear Steam Supply Shut-Off/ 5 239002 Relief/Safety Valves / 3 X
A1.02 - Acoustical monitor noise:
3.7 1
Plant-Specific 239002 Relief/Safety Valves / 3 X
A 1.05 - Reactor water level 3.7 1
261000 Standby Gas Treatment System / 9 X
K6.03 - Emergency diesel generator system 3.0 1
261000 Standby Gas Treatment System / 9 X
A4.07 - System flow 3.1 1
Printed:
01(
'.002 i
mrination Outline Printed:
01(
!002 Hope Creek Generating Station Plant Systems - Tier 2 / Group 2 Sys/Ev #
System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.
Points 201003 Control Rod and Drive Mechanism / I X
K4.05 - Rod position indication 3.2 1
201006 Rod Worth Minimizer System (RWM)
X K3.01 - Reactor manual control system:
3.2 1
(Plant Specific) / 7 P-Spec(Not-BWR6) 202001 Recirculation System / 1 X
K3.07 - Vessel bottom head drain temperature 2.9 1
202001 Recirculation System / 1 X
A4.04 - System flow 3.7 1
204000 Reactor Water Cleanup System / 2 X
A2.14 - System high temperature 3.2 1
219000 RHR/LPCI: Torus/Suppression Pool X
A3.01 - Valve operation 3.3 1
Cooling Mode / 5 226001 RHR/LPCI: Containment Spray X
A 1.06 - System flow 3.2 1
System Mode / 5 226001 RHR/LPCI: Containment Spray X
A3.05 - Containment pressure 4.0*
1 System Mode / 5 230000 RHR/LPCI: Torus/Suppression Pool X
K6.01 - A.C. electrical 3.3 1
Spray Mode / 5 245000 Main Turbine Generator and Auxiliary X
K5.02 - Turbine operation and limitations 2.8 1
Systems / 4 256000 Reactor Condensate System / 2 X
K4.06 - Control of extraction steam 2.8 1
256000 Reactor Condensate System / 2 X
A2.13 - Loss of applicable plant air systems 2.9 1
Facility:
Hope Creek Generating Station K/A Category Totals:
1 2
2 2
ruination Outline Plant Systems - Tier 2 / Group 2 2
3 2
2 2
1 0
Printed:
01(
002 Sys/Ev #
System/ Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 262001 A.C. Electrical Distribution / 6 X
K2.01 - Off-site sources of power 3.3 1
262001 A.C. Electrical Distribution / 6 X
K6.01 - D.C. power 3.1 1
263000 D.C. Electrical Distribution / 6 X
A1.01 - Battery charging/discharging rate 2.5 1
263000 D.C. Electrical Distribution / 6 X
K2.01 - Major D.C. loads 3.1 1
271000 Offgas System / 9 X
K1.02 - Process radiation monitoring system 3.1 1
272000 Radiation Monitoring System / 7 X
K6.03 - A.C. power 2.8 1
290003 Control Room HVAC / 9 X
K5.01 - Airborne contamination (e.g.,
3.2 1
radiological, toxic gas, smoke) control Group Point Total:
19 2
Facility:
ES - 401 Fnrm FS-4II 1-2
mination Outline Printed:
01(
002 Facility:
Hope Creek Generating Station ES - 401 Plant Systems - Tier 2 / Groun 3 Sys/Ev #
System/ Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 215001 Traversing In-Core Probe / 7 X
K1.05 - Primary containment isolation system:
3.3 1
(Not-BWR1) 268000 Radwaste / 9 X
A1.01 - Radiation level 2.7*
1 290002 Reactor Vessel Internals / 5 X
K3.03 - Reactor power 3.3 1
290002 Reactor Vessel Internals / 5 X
A2.02 - tOverpressurization transient 3.6 1
K/A Category Totals:
1 0
1 0
0 0
1 1
0 0
0 Group Point Total:
4
(
Fnrm Eq-401-2 I
Generic Knowledge -'d Abilities Outline (Tier 3)
(
KA Topic Imp.
Points Conduct of Operations 2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.
2.8 1
2.1.31 Ability to locate control room switches, controls and indications and to determine that 4.2 1
they are correctly reflecting the desired plant lineup.
2.1.33 Ability to recognize indications for system operating parameters which are entry-level 3.4 1
conditions for technical specifications.
Category Total:
3 Equipment Control 2.2.28 Knowledge of new and spent fuel movement procedures.
2.6 1
2.2.22 Knowledge of limiting conditions for operations and safety limits.
3.4 1
2.2.27 Knowledge of the refueling process.
2.6 1
Category Total:
3 Radiation Control 2.3.2 Knowledge of facility ALARA program.
2.5 1
2.3.9 Knowledge of the process for performing a containment purge.
2.5 1
2.3.11 Ability to control radiation releases.
2.7 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control requirements.
2.6 1
Category Total:
4 Emergency Plan 2.4.18 Knowledge of the specific bases for EOPs.
2.7 1
2.4.34 Knowledge of RO tasks performed outside the main control room during emergency 3.8 1
operations including system geography and system implications.
2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, 2.9 1
and emergency evolutions.
Category Total:
Generic Total:
3 13 Printed:
01/09/2G Form ES-401-5 Facility:
Hope Creek Generating Station Generic Category KA I
ES-401 BWR SRO Examination Outline Facility:
Hope Creek Generating Station Exam Date: 03/12/2002 Printed: 01/08/2002 Form ES-401 -1 Exam Level:
SRO Tier
- 1.
Emergency Abnormal Plant Evolutions
- 2.
Plant Systems Group K/A Category Points KI K2 K3 K4 K5 K6
.Y.-Y-r-Y-4 5
4 2
3 2
3 Tier Totals 7
2 7
2 7
2 2
2 2
Al 4
3 7
2 A2 5
3 8
2 A3 A4 2
2 G
4 3
7 Point Total 26 17 43 23 2
1 1
2 1
1 2
1 1
1 0
2 13 3
1 0
0 1
0 0
1 0
0 0
1 4
1 Tier Totals 4
4 4
3 4
4 3
2 6
40 Cat I Cat 2 Cat 3 Cat 4
- 3. Generic Knowledge And Abilities 5
4 4
4 17 Note:
- 1. Attempt to distribute topics among all K/A Categories; select at least one topic from ever)' K/A category within each tier.
- 2. Actual point totals must match those specified in the table.
- 3. Select topics from many systems; avoid selecting more than two or three K/A 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.
I I
i ope Creek Generating Station BWR Sl(
- xamination Outline Printed:
01/4 J02 Emergency and Abnormal Plant Evolutions - Tier 1 / Group I E/APE #
E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.
Points 295003 Partial or Complete Loss of A.C. Power / 6 X
AA2.02 - Reactor power, pressure, and level 4.3*
1 295006 SCRAM / I X 2.1.28 - Knowledge of the purpose and function of 3.3 1
major system components and controls.
295006 SCRAM / 1 X
AK1.01 - Decay heat generation and removal.
3.9 1
295007 High Reactor Pressure / 3 X
AK2.05 - Shutdown cooling: Plant-Specific 3.1 1
295007 High Reactor Pressure / 3 X
AK3.04 - Safety/relief valve operation: Plant-Specific 4.1*
1 295009 Low Reactor Water Level / 2 X 2.4.6 - Knowledge symptom based EOP mitigation 4.0 1
strategies.
295009 Low Reactor Water Level / 2 X
AA2.01 - Reactor water level 4.2 1
295010 High Drywell Pressure / 5 X
AA1.02 - Drywell floor and equipment drain sumps 3.6 1
295013 High Suppression Pool Temperature/ 5 X
AK2.01 - Suppression pool cooling 3.7 1
295014 Inadvertent Reactivity Addition / 1 X
AK2.04 - Void concentration 3.3 1
295014 Inadvertent Reactivity Addition / I X
AK3.01 - Reactor SCRAM 4.1 1
295015 Incomplete SCRAM / 1 X
AK3.01 - Bypassing rod insertion blocks 3.7 1
295015 Incomplete SCRAM / 1 X 2.3.4 - Knowledge of radiation exposure limits and 3.1 1
contamination control, including permissible levels in excess of those authorized.
295016 Control Room Abandonment / 7 X
AA 1.02 - Reactor/turbine pressure regulating system 3.1
- 1 295017 High Off-Site Release Rate / 9 X
AA2.01 - 'Off-site release rate: Plant-Specific 4.2*
1
(
Facility:
S t
S S
I
Hope Creek Generating Station BWR SR' xamination Outline Emergency and Abnormal Plant Evolutions - Tier I / Groun I E/APE #
E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.
Points 295023 Refueling Accidents / 8 X
AAI.02 - Fuel pool cooling and cleanup system 3.1 1
295023 Refueling Accidents / 8 X
AA2.05 - tEntry conditions of emergency plan 4.6*
1 295024 High Drywell Pressure / 5 X 2.2.7 - Knowledge of the process for conducting tests or 3.2 1
experiments not described in the safety analysis report.
295024 High Drywell Pressure / 5 X
EA 1.10 - A.C. distribution 3.6 1
295025 High Reactor Pressure / 3 X
EK1.05 - tExceeding safety limits 4.7*
1 295026 Suppression Pool High Water Temperature / 5 X
EK 1.02 - Steam condensation 3.8 1
295030 Low Suppression Pool Water Level / 5 X
EA2.04 - Drywell/ suppression chamber differential 3.7 1
pressure: Mark-I&II 295030 Low Suppression Pool Water Level / 5 X
EK2.03 - LPCS 3.9 1
295031 Reactor Low Water Level / 2 X
EK2.13 - ARI/RPT/ATWS: Plant-Specific 4.2 1
295038 High Off-Site Release Rate / 9 X
EK1.02 - tProtection of the general public 4.4*
1 500000 High Containment Hydrogen Concentration / 5 X
EK3.03 - Operation of hydrogen and oxygen 3.5 1
recombiners K/A Category Totals:
4 5
4 45 4
Group Point Total:
Facility:
ES - 401 S
26 2
Printed:
01/0(
)2 Form F.q-Afl 1 - 1
Hope Creek Generating Station BWR SR4 xamination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Printed:
01/0(
)2 Form ES-401-1 E/APE #
E/APE Name / Safety Function KI K2 K3 Al A2 G
KA Topic Imp.
Points 295001 Partial or Complete Loss of Forced Core Flow X
AA1.02 - RPS 3.3 1
Circulation / I 295002 Loss of Main Condenser Vacuum / 3 X
AK1.04 - Increased offgas flow 3.3 1
295004 Partial or Complete Loss of D.C. Power / 6 X
AA2.01 - Cause of partial or complete loss of D.C.
3.6 1
power 295004 Partial or Complete Loss of D.C. Power / 6 X
AK3.03 - Reactor SCRAM: Plant-Specific 3.5 1
295005 Main Turbine Generator Trip / 3 X
AA2.04 - Reactor pressure 3.8 1
295008 High Reactor Water Level / 2 X
AA 1.01 - Reactor water level control: Plant-Specific 3.7 1
295008 High Reactor Water Level / 2 X
AK3.04 - Reactor feed pump trip: Plant-Specific 3.5 1
295012 High Drywell Temperature / 5 X
AK 1.0 1 - Pressure/temperature relationship 3.5 1
295018 Partial or Complete Loss of Component Cooling X
AA2.03 - Cause for partial or complete loss 3.5 1
Water / 8 295019 Partial or Complete Loss of Instrument Air / 8 X
AAI.02 - Instrument air system valves: Plant-Specific 3.1 1
295021 Loss of Shutdown Cooling / 4 X 2.4.41 - Knowledge of the emergency action level 4.1 1
thresholds and classifications.
295022 Loss of CRD Pumps / I X 2.4.48 - Ability to interpret control room indications to 3.8 1
verify the status and operation of system, and understand how operator action s and directives affect plant and system conditions.
295022 Loss of CRD Pumps / I X
AK2.03 - Accumulator pressures.
3.4 1
Facility:
ES - 401 S
S S
I
Facility:
I-iope Creek Generating Station ES - 401 BWR S, "xamination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-1 K/A Category Totals:
3 2
3 3
3 3
Group Point Total:
E/APE #
E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.
Points 295028 High Drywell Temperature / 5 X
EK1.02 - Equipment environmental qualification 3.1 1
295034 Secondary Containment Ventilation High Radiation X 2.2.18 - Knowledge of the process for managing 3.6 1
9 maintenance activities during shutdown operations.
295036 Secondary Containment High Sump/Area Water X
EK2.01 - Secondary containment equipment and floor 3.2 1
Level / 5 drain system 295036 Secondary Containment High Sump/Area Water X
EK3.01 - Emergency depressurization 2.8 1
Level / 5 S
17 2
Printed:
011d.
02
mination Outline Hope Creek Generating Station Plant Systems - Tier 2 / Groutn 1 Sys/Ev #
System / Evolution Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.
Points 203000 RHR/LPCI: Injection Mode (Plant X
A4.07 - Reactor water level 4.5*
1 Specific) / 2 203000 RHR/LPCI: Injection Mode (Plant X
K1.14 - Shutdown cooling system:
3.7 Specific) / 2 Plant-Specific 206000 High Pressure Coolant Injection X
A 1.06 - System flow: BWR-2, 3, 4 3.7 1
System / 2 209001 Low Pressure Core Spray System / 2 X
K 1.10 - Emergency generator 3.8 1
209001 Low Pressure Core Spray System / 2 X
K2.02 - Valve power 2.7*
1 212000 Reactor Protection System / 7 X
K5.02 - Specific logic arrangements 3.4 1
215004 Source Range Monitor (SRM) System X 2.2.6 - Knowledge of the process for making 3.3 1
/7 changes in procedures as described in the safety analysis report.
215004 Source Range Monitor (SRM) System X
A3.03 - RPS status 3.5 1
/7 215005 Average Power Range Monitor/Local X
K5.05 - Core flow effects on APRM trip 3.6 1
Power Range Monitor System / 7 setpoints 215005 Average Power Range Monitor/Local X
K3.05 - Reactor power indication 3.8 1
Power Range Monitor System / 7 216000 Nuclear Boiler Instrumentation / 7 X
A2.08 - Elevated containment temperature 3.4 1
216000 Nuclear Boiler Instrumentation / 7 X
K2.01 - Analog trip system: Plant-Specific 2.8 1
Facility:
ES - 401 S
Printed:
01,(
002 Farm Eq-401-1 I
.mination Outline Printed:
014 902 Facility:
Hope Creek Generating Station Plant Systems - Tier 2 / Group I Form ES-401-1 Sys/Ev #
System/ Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 217000 Reactor Core Isolation Cooling X
A2.01 - System initiation signal 3.7 1
System (RCIC) / 2 217000 Reactor Core Isolation Cooling X
K4.05 - Prevents radioactivity release to 3.5 1
System (RCIC) / 2 auxiliary/reactor building 223002 Primary Containment Isolation X
K3.16 - Shutdown cooling system/RHR 3.3 1
System/Nuclear Steam Supply Shut-Off/ 5 223002 Primary Containment Isolation X
K4.01 - Redundancy 3.2 1
System/Nuclear Steam Supply Shut-Off/ 5 226001 RHR/LPCI: Containment Spray X
A3.05 - Containment pressure 4.0*
1 System Mode / 5 239002 Relief/Safety Valves / 3 X
A1.05 - Reactor water level 3.8 I
259002 Reactor Water Level Control System /
X 2.4.32 - Knowledge of operator response to loss 3.5 1
2 of all annunciators.
261000 Standby Gas Treatment System / 9 X
K6.03 - Emergency diesel generator system 3.1 1
261000 Standby Gas Treatment System / 9 X
A4.07 - System flow 3.2 1
262001 A.C. Electrical Distribution / 6 X
K6.01 - D.C. power 3.4 264000 Emergency Generators (Diesel/Jet) / 6 X 2.1.11 - Knowledge of less than one hour 3.8 technical specification action statements for systems.
2 ES - 401 S
BWR SR6" Amination Outline Printed:
0 O,'002 Facility:
Hope Creek Generating Station ES - 401 Plant Systems - Tier 2 / Group I Form ES-401-1 System / Evolution Name K/A Category Totals:
KA Topic Group Poir L4.......L.I..............1..............I
_____ L..............i..............+/-..............I...............3............i.
.3 _________ L __________
(
Sys/Ev #
KI 2
K2 2
K3 2
K4 2
K5 2
K6 2
Al 2
A2 2
A3 2
A4 2
G 3
Imp.
t Total:
Points 23
BWR SROf
.mination Outline Hope Creek Generating Station Plant Systems - Tier 2 / Group 2 Form ES-401-1 Sys/Ev #
System/ Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 201001 Control Rod Drive Hydraulic System!
X A3.05 - Reactor water level 2.8 1
1 201002 Reactor Manual Control System / I X
K4.08 - Continuous In rod insertion 3.2 1
201006 Rod Worth Minimizer System (RWM)
X K3.01 - Reactor manual control system:
3.5 1
(Plant Specific) / 7 P-Spec(Not-BWR6) 201006 Rod Worth Minimizer System (RWM)
X 2.1.12 - Ability to apply technical specifications 4.0 1
(Plant Specific) / 7 for a system.
202001 Recirculation System / 1 x
K3.07 - Vessel bottom head drain temperature 2.9 1
204000 Reactor Water Cleanup System / 2 X
A2.14 - System high temperature 3.2 230000 RHRILPCI: Torus/Suppression Pool X
K6.01 - A.C. electrical 3.4 1
Spray Mode / 5 234000 Fuel Handling Equipment / 8 X 2.2.25 - Knowledge of bases in technical 3.7 1
specifications for limiting conditions for operations and safety limits.
263000 D.C. Electrical Distribution / 6 X
K2.01 - Major D.C. loads 3.4 1
263000 D.C. Electrical Distribution / 6 X
A 1.01 - Battery charging/discharging rate 2.8 1
271000 Offgas System / 9 X
K1.02 - Process radiation monitoring system 3.3 1
272000 Radiation Monitoring System / 7 X
K6.03 - A.C. power 3.0 1
Facility:
ES - 401 5
Printed:
01/(
)02 I
BWR SRO6 Amination Outline Facility:
Hope Creek Generating Station ES - 401 K/A Category Totals:
1 1
2 1
1 2
1 1
1 0
2 Group Point Total:
13 2
Printed:
0 l(
!002
Amination Outline Facility:
Hope Creek Generating Station Plant Svstems - Tier 2 / Groun 3 Form ES-401-1 Sys/Ev#
System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.
Points 201003 Control Rod and Drive Mechanism / 1 X
K4.05 - Rod position indication 3.3 1
215001 Traversing In-Core Probe / 7 X
KI.05 - Primary containment isolation system:
3.4 1
(Not-BWR1) 233000 Fuel Pool Cooling and Clean-up / 9 X 2.1.7 - Ability to evaluate plant performance 4.4 1
and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
268000 Radwaste / 9 X
A 1.01 - Radiation level 3.1*
1 K/A Category Totals:
1 0
0 1
0 0
1 0
0 0
1 ES - 401 S
Printed:
01(
'.002 Group Point Total:
4 I
Generic Knowledge(, I Abilities Outline (Tier 3)
Printed:
01/08/201 BWR SRO Examination Outline Form ES-401-5 Imp.
Points Conduct of Operations 2.1.34 Ability to maintain primary and secondary plant chemistry within allowable limits.
2.9 1
2.1.14 Knowledge of system status criteria which require the notification of plant personnel.
3.3 1
2.1.33 Ability to recognize indications for system operating parameters which are entry-level 4.0 1
conditions for technical specifications.
2.1.31 Ability to locate control room switches, controls and indications and to determine that 3.9 1
they are correctly reflecting the desired plant lineup.
2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.
3.1 1
Category Total:
5 Equipment Control 2.2.29 Knowledge of SRO fuel handling responsibilities.
3.8 1
2.2.26 Knowledge of refueling administrative requirements.
3.7 1
2.2.22 Knowledge of limiting conditions for operations and safety limits.
4.1 1
2.2.27 Knowledge of the refueling process.
3.5 1
Category Total:
4 Radiation Control 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control requirements.
3.0 1
2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against 3.3 1
personnel exposure.
2.3.11 Ability to control radiation releases.
3.2 1
2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible 3.1 1
levels in excess of those authorized.
Category Total:
4 Facility:
Hope Creek Generating Station Generic Category KA KA Topic IS S
5 S
Generic Knowledge, d Abilities Outline (Tier 3)
BWR SRO Examination Outline Facility:
Hope Creek Generating Station Generic Category KA KA Topic Imp.
Points Emergency Plan 2.4.28 Knowledge of procedures relating to emergency response to sabotage.
3.3 1
2.4.34 Knowledge of RO tasks performed outside the main control room during emergency 3.6 1
operations including system geography and system implications.
2.4.18 Knowledge of the specific bases for EOPs.
3.6 1
2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, 3.6 1
and emergency evolutions.
Category Total:
4 Generic Total:
17 2
S Printed:
01/08/20d
- 1.
Form ES-401-5
NC.TQ-WB.ZZ-0027(Z)
ES-301 Administrative Topics Outline FORM ES-301-1 Page 1 of 1 Facility:
HOPE CREEK Date of Examination:
03/11/02 Examination Level:
[
RO F-] SRO Operating Test Number:
Administrative Describe method of evaluation:
Topic/Subject
- 2. TWO Administrative Questions A.1 Conduct of 2.1.25 Ability to obtain and interpret station reference materials Operations such as graphs/monographs/and tables which contain data. (2.8)
Question-Given plant conditions, determine the required Circulation Water System requirements for extreme cold weather.
Plant Parameter (NEW)
Verification 2.1.25 Ability to obtain and interpret station reference materials such as graphs/monographs/and tables which contain data. (2.8)
Question-Obtain maximum RWCU return to Feedwater Temperature.
(NEW) 2.1.3 Knowledge of shift turnover practices. (3.0)
Shift Turnover JPM-Complete shift turnover attachment as off-going RO.
(Simulator Perform) (5/00 NRC Exam) (Modified)
A.2 Equipment Control 2.2.12 Knowledge of surveillance procedures. (3.0)
Surveillance JPM-Perform alternate determination of Drywell Air Temperature.
Procedures (Simulator Perform) (NEW)
A.3 Radiation Control 2.3.11 Ability to control radiation releases (2.7)
Radiation Releases JPM-Calculate Iodine Release Rates (Simulator Perform) (NEW)
A4 Emergency Plan 2.4.39 Knowledge of the RO's responsibilities in emergency plan Emergency Action implementation. (3.3)
Levels and JPM-Perform the Licensed Operator Review of the Operational Classifications Status Board-Hope Creek (Simulator Perform) (NEW)
Last saved: 01/10/2002 10:09 AM Page 27 of 64 Rev. 1
NC.TQ-WB.ZZ-0027(Z)
ES-301 Administrative Topics Outline FORM ES-301-1 Page 1 of 1 Facility:
HOPE CREEK Date of Examination:
03/11/02 Examination Level:
E]
RO Z
SRO Operating Test Number:
Administrative Describe method of evaluation:
Topic/Subject
- 2. TWO Administrative Questions Conduct of Operations 2.1.25 Ability to obtain and interpret station reference materials such as graphs/monographs/and tables which contain data.
(3.1)
Question-Given plant conditions, determine the required Circulation Water System requirements for extreme cold weather.
Plant Parameter (NEW)
Verification A. 1 2.1.25 Ability to obtain and interpret station reference materials such as graphs/monographs/and tables which contain data.
(3.1)
Question-Calculate time to establish Secondary Containment following a loss of Shutdown Cooling. (NEW) 2.1.3 Knowledge of shift turnover practices. (3.4)
Shift Turnover JPM-Complete key verification required during CRS shift turnover.
(In-plant Perform)(NEW)
A.2 Equipment Control 2.2.12 Knowledge of surveillance procedures. (3.4)
Surveillance JPM-Perform Drywell Air Temperature Operability Check.
Procedures (Simulator Perform) (NEW)
A.3 Radiation Control 2.3.11 Ability to control radiation releases (3.2)
Radiation JPM-Calculate Iodine Release Rates (Simulator Perform) (NEW)
Exposure Control A4 Emergency Plan 2.4.41 Knowledge of the Emergency Action Level thresholds and Emergency Action classifications. (4.1)
Levels and JPM -Given a set of conditions, classify an event and complete the Classifications Initial Contact Message Form. (Modified)
Last saved: 01/10/2002 10:09 AM Page 27 of 64 Rev. 1
NC.TQ-WB.ZZ-0027(Z)
ES-301 Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2 Page 1 of 1 Facility:
HOPE CREEK Date of Examination:
03/11/02 Examinations Developed by:
M Facility F-NRC Examination Level:
[
[
SRO(I)
Operating Test Number:
B.1 Control Room Systems System / JPM Title Type Code*
Safety Function
- a. CRD-Stuck Rod during Shutdown Rod Exercising (N), (A), (L), (S) 1
- b. EHC-Respond to Low EHC Pressure (D), (A), (S) 3
- c. Recirc-Raise Reactor Recirculation Pump Speed >100%
(N), (S) 4
- d. Condensate-Place 2 nd Secondary Condensate Pump In-(D), (L), (8) 2 service
- f. Instrument Air-Place the Emergency Instrument Air (M), (A), (S) 8 Compressor in service
- g. EDG-Non-emergency operations of an EDG (D), (S), (E) 6 B.2 Facility Walk-Through
- b. Sample Primary Containment Atmosphere (D), (P), (R) 5
- c. Respond to a Failed Open Safety Relief Valve (Abnormal)
(D), (P), (E) 3
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA, (E)SF Last saved: 01 /10/2002 10:09 AM Page 28 of 64 Rev. 1
NC.TQ-WB.ZZ-0027(Z)
ES-301 Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2 Page 1 of 1 Facility:
HOPE CREEK Date of Examination:
03/11/02 Examinations Developed by:
Z Facility Fii NRC Examination Level:
E] RO Z
SRO(U)
Operating Test Number:
B.1 Control Room Systems System I JPM Title Type Code*
Safety Function
- a. CRD-Stuck Rod during Shutdown Rod Exercising (N), (A), (L), (S) 1
- b. Instrument Air-Place the Emergency Instrument Air (M), (A), (S) 8 Compressor in service
- c. EDG-Non-emergency operations of an EDG (D), (S), (E) 6
- d.
- e.
- f.
- g.
B.2 Facility Walk-Through
- a. Respond to a Failed Open Safety Relief Valve (Abnormal)
(D), (P), (E) 3
- b. Sample Primary Containment Atmosphere (D), (P), (R) 5 C.
Last saved: 01/10/2002 10:09 AM
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA, (E)SF Page 28 of 64 Rev. 1
NC.TQ-WB.ZZ-0027(Z)
Appendix D Scenario Outline Form ES-D-1 Page 1 of 1 Facility:
Hope Creek Scenario Number:
1 Operating Test Number:
Examiners:
Evaluators:
Objectives:
Initial Plant is operating at 80% power. Shutdown in progress. 10-0004, Step 5.1.5.
Conditions:
Shutdown sequence Step 723 Continue with plant shutdown. Place C RFP in Recirc. Reduce power with control Turnover:
rods by inserting RWM Group 84, and then contact Reactor Engineer for further guidance.
Event Malf.
Event Event Description Number Number Type*
1 N(PO)
Place 3rd Reactor Feed Pump in Recirc.
N(SRO)
- 2.
R(RO)
- 2.
N(SRO)
Reduce power with Control Rods I(SRO)
- 3.
RR-19 I(SRO)
Flow Comparator Failure C(PO)
- 4.
C(SRO)
Loss of Reactor Building Ventilation/Secondary Containment C(SRO)
- 5.
CD-10OA C(SRO)
CRD Pump trip RCIC steam leak w/ failure to isolate/High HPCI Room
- 6.
RC-09/10 M(ALL)
Temp/Scram
- 7.
I(PO)
ADS failure to initiate during Emergency Depressurization I(SRO)
(Similar event to Audit, different initiating cause and failure.)
(I)nstrument, (C)omponent, (M)ajor Last saved: 01/11/2002 11:39 AM (N)ormal, (R)eactivity, Page 64 of 64 Rev. 1
NC.TQ-WB.ZZ-0027(Z)
Appendix D Scenario Outline Form ES-D-1 Page 1 of 1 Facility:
Hope Creek Scenario Number:
2 Operating Test Number:
Examiners:
Evaluators:
Objectives:
Initial Modified ESG-042.
Conditions:
Plant is operating at 95% power. D Circulating Water Pump OOS for maintenance.
Turnover:
Place B RFP in service. Raise Reactor power to 100% with Recirculation flow.
Event Malf.
Event Event Description Number Number Type*
- 1.
N(PO)
- 2.
C(PO)
Inadvertent Loss of Circulating Water Pump B/Degrading C(SRO)
Condenser Vacuum
- 3.
R(RO)
Reduce power to maintain Condenser Vacuum
- 4.
RR-05/
C(RO)
Dual Recirc Seal Failure RR-06 C(SRO)
RR-08/
- 5.
RR-26 I(ALL)
Recirc Pump Speed Control Failure/High Vibrations/Scram
- 6.
RR-31 M(ALL)
Recirc Line Break/Primary Containment Failure
- 7.
C(PO)
Containment Spray Valve Failure C(SRO) 8.
(N)ormal, (I)eactlivty, (I)nstrument, (C)omponent, (M)ajor Last saved: 01/10/2002 10:09 AM Rev. 1 Page 64 of 64
NC.TQ-WB.ZZ-0027(Z)
Appendix D Scenario Outline Form ES-D-1 Page 1 of 1 Facility:
Hope Creek Scenario Number:
3 Operating Test Number:
Examiners:
Evaluators:
SPARE Objectives:
Initial Conditions:
Turnover:
SPARE SCENARIO 36% Power. Reactor startup in progress.
Transfer B RPS to the Alternate Power Supply. Raise Reactor power with Control Rods.
)ormal, (R)ea Event Description Transfer B RPS to the Alternate Power Supply ailure is different)
DB Loss of SWC/ATWS/SLC Pump Failure/Loss of Off-site Power IC HPCI auto initiation failure
- mnent, (C)omponent, (M)ajor Last saved: 01/10/2002 10:09 AM Page 64 of 64 Rev. 1