ML17298B969
| ML17298B969 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/25/2017 |
| From: | NRC/RGN-II |
| To: | South Carolina Electric & Gas Co |
| References | |
| Download: ML17298B969 (15) | |
Text
ES-401N. Rev. 10 PWR Examination Outline Form ES-401 N-2 Facility:
Summer Unit 2 Date of Exam:
RO K/A Category Points SRO-Only Points Tier Group
K K
K K
K K
A A
A A
G[
A2 G*
[Total 1
2 3
4 5
6 1
2 3
4
- ITotal I
1.
1 3
3 3
3 3
3 18 3
3 6
Emergency &
2
-i 2
1 2
9 2
2 4
Abnormal Plant
N/A N/A
Evolutions Tier Totals 4
5 4
5 4
5 27 5
5 10 1
3 2
2 3
3 3
2 2
3 2
3 28 2
3 5
2.
2 1
0 1
1 1
1 1
1 1
1 1
10 1
2 3
Plant I
Systems Tier Totals 4
2 3
4 4
4 3
3 4
3 4
38 5
8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 J 3
4 7
Categories 3
2 3
2 1
2 2
2 1.
Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).
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 0.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A 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 KIAs 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 I and 2 from the shaded systems and KIA categories.
7.
- The generic (G) KIA5 in Tiers I 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 0.1.b of ES-401 for the applicable KAs.
8.
On the following pages, enter the K/A 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 K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#)on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401N, REV 10 TIGI PWR EXAMINATION OUTLINE FORM ES-401 N-2 KA NAME/SAFETY FUNCTIO IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO A-307AK1.03 DAS Operation At Local Cabinets 3.5 0
El El El El El El El El LI []
ADS A-313AA2.05 Uncontrolled Cooldown 3.3 3.2 El El El El El El El El El El Passive Residual Heat Removal System flow A-317AK2.02 Loss of Component Cooling Water 3.1 El El El El El El El El El El Loss of Service Water System to the Component Cooling Water System heat exchanger A-323AK2.02 Loss of 6.9KV, 4160 Volt, or 480 3.9 Loss of power to Class IE DC and UPS System Volt Bus Power Distribution Panels on Automatic Depressurization System A-329AK1.04 Loss of Instrument Air 3.3 El Containment isolation valves (OE related)
A-336AK3.03 Malfunction of Protection and 2.9 El Using a Protection and Safety Monitoring System Safety Monitoring System component interface module to operate components A-337AA1.02 Passive Residual Heat Removal 3.2 Passive Residual Heat Removal System heat exchanger Heat Exchanger Leak control valves and inlet valve A-345AG2.4.14 Loss of Service Water 3.4 4.1 El El El El El El El El El []
Knowledge of Emergency/Abnormal Operating Procedures layout, symbols, and icons.
E-OEK3.10 Reactor Trip or Safeguards 3.2 El El El El El El El El El El Steam Generator Relief Isolation Actuation Actuation E-3EG2.4.25 Steam Generator Tube Rupture 3.6 4
El El El El El El El El El El Knowledge of operator response to a loss of all annunciators.
ECA-1.1EA1.04 3.2 El El El El El El El El El El ReactorCoolantSystem Loss of Coolant Accident Outside Containment Page 1 of 2 08/17/2015 6:55AM
ES-401N, REV 10 TIGI PWR EXAMINATION OUTLINE FORM ES-401N-2 Response to Loss of RCS Inventory During Shutdown Order of preference for Reactor Coolant System makeup sources SDP-2EK1.17 Response to Loss of Normal Residual Heat Removal System During Shutdown 2.7 Containment Recirculation Cooling System (OE related)
KA NAME I SAFETY FUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO ES-0.2EA1.07 Natural Circulation Cooldown 3.1 Pressurizer Pressure Control System ES-l.1 EA2.03 Passive Safety System Termination 3.8 3.7 El Core exit temperatures and/or subcooling ES-l.4EA2.04 ADS Stage 4 Actuation Response 3.4 2.9 IRWST proper alignment FR-C.1EG2.4.6 Response to Inadequate Core 3.7 4.7 Knowledge of Emergency/Abnormal Operating Cooling Procedures major action categories.
FR-H.l EK2.05 Response to Loss of Heat Sink 3.6 El El LI El El LI El El El El Establishing feedwater flow to a steam generator that is depressurized SDP-1EK3.17 3.1 Page 2 of 2 08/17/2015 6:55 AM
ES-401N, REV 10 TIG2 PWR EXAMINATION OUTLINE FORM ES-401N-2
2.8 LI LI LI LJLI Pressurizer level and/or pressure 4.5 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for Emergency/Abnormal Operating Procedures.
3.8 Suspending core alterations and placing fuel in storage location 2.8 Condensate pump and/or miniflow controls 3.1 LI Pressurizer Pressure Control System LI LI LI LI LI LI LI LI LI LI Ability to perform general and/or normal operating procedures during any plant condition.
3.5 Automatic Depressurization System 3.5 Reactor Coolant System pressure greater than the Reactor Coolant System pressure requirement for placing the Normal Residual Heat Removal System in service under normal conditions RO SRO KA NAME I SAFETY FUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
3.0 4,7 A-302AA2.01 A-306AG2.4.4 A-314AK3.03 A-318AA1.03 ES-l.2EA1.09 FR-H.2EG2. 1.21 FR-I.l EK1.01 SDP-5EK2.02 Emergency Boration Evacuation of Control Room Fuel Handling Incidents Condensate System Malfunctions Post Loss of Coolant Accident Cool Down and Depressurization Response to Steam Generator Overpressure Response to High Pressurizer Level Response to RCS Cold Overpressure During Shutdown SDP-6EK2.0l Response to Unexpected RCS Temperature Changes During Shutdown 3.3 LI LI LI LI LI LI LI LI LI LI Flooding the reactor cavity with in-containment refueling water storage tank water Page 1 of 1 08/17/2015 6:55 AM
ES-401N, REV 10 T2GI PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME I SAFETY FUNCTION IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO ADSG2.4.2 Automatic Depressurization System 4.5 4.6 Knowledge of system set points, interlocks and automatic actions associated with Emergency/Abnormal Operating Procedure entry conditions.
CASK6.03 Compressed dr System 2.7 Instrument air compressor package CCSK5.Ol Component Cooling Water System 2.7 Water hammer CNSG2.2.17 Containment System 4
4.7 LI Knowledge of limiting conditions for operations and safety limits.
CNSK4.05 Containment System 3.4 LI Containment closure CVSA4.ll Chemical and Volume Control 3.8 LI Chemical and Volume Control System Makeup Isolation System Actuation DASK4.Ol Diverse Actuation System 3.7 LI LI LI LI LI LI LI LI LI LI Reactor and Turbine Trip Actuations ECSK5.04 AC Electrical Distbution Systems 3.3 LI LI LI LI [] LI LI LI LI LI LI Fault on a unit auxiliary transformer ECSK6.09 AC Electrical Distribution Systems 3.2 LI LI LI LI LI LI LI LI LI LI Transmission Switchyard and Offsite Power System ESASA2.33 Engineered Safeguards Actuation 3.8 3,9 LI LI LI LI LI LI LI i LI LI LI Reactor Trip Actuation System FWSK6.ll Main and Startup Feedwater System 2.7 LI LI LI LI LI LI LI LI LI LI Turbine impulse pressure instrument Page 1 of 3 08/17/2015 6:55 AM
ES-401N, REV 10 T2GI PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME / SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO IDSA3.O1 Class 1E and Non 1E DC and UPS 3
[]
[]
lnverter input transfer between battery and regulated Systems transformer OE Related IDSK1.03 Class 1E and Non 1E DC and UPS 4
Li Engineered Safeguards Actuation System Systems MSSA3.05 Main Steam System 3.5 Steam Line Isolation Actuation PCSK4.03 Passive Containment Cooling 3
Spent Fual pit inventory makeup System PPCSA1.14 PressurizerPressureControl 3
[]
[] [] []
Makeupflow System PRHRK2.Ol Passive Residual Heat Removal 3.2 LI LI LI LI LI LI LI LI LI LI Passive Residual Heat Removal System heat exchanger System inlet isdation valves PXSA4.03 Passive Core Cooling System 4.4 LI Containment Isolation Actuation RCPK3.Ol Reactor Coolant Pump System 3.3 LI Reactor Coolant System (OE-related)
RCSA3.03 Reactor Coolant System 4
Reactor Coolant System Tavg control and protection functions RCSG2.4.7 Reactor Coolant System 3.8 4.5 LI Knowledge of how Abnormal Operating Procedures are used in conjunction with Emergency Operating Procedures.
RNSA2.lO 3.2 3.7 LI LI LI LI LI LI LI LI LI LI In-containment refueling water storage tank isolation valve Normal Residual Heat Removal System Page 2 of 08/17/2015 6:55AM
ES-401N, REV 10 T2GI PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME I SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO RTSK3.12 Reactor Trip System 3
Main Feedwater Pump Trip And Valve Isolation Actuation SGSK2.04 Steam Generator System 2.8
[]
[]
[]
MSIV hydraulic pump SGSK5.02 Steam Generator System 3.1 Li Li Li Steam generator level shrink and swell SWSK1.Ol SericeWaterSystem 2.8 Li Li Li Li Li Li Li Li Li Li CompressedAirSystem ZOSA1.Ol Onsite Standby Power System 2.8 Li Li Li Li Li Li Li Li Li Li Diesel engine operating parameters ZOSK1.04 Onsite Standby Power System 2.6 Li Li Li Li Li Li Li Li Li Li Fire Protection System Page3of3 08/17/2015 6:55AM
pou-FaI 001105 betWeen units eta lability. A 1
Dli$4 &
cv opwo.4t orb, Wc Motor driven fire pump failure IISK3.02 moore Instrumentation System 2.6 Data Display and Processing System PLCSK4.07 Pressurizer Level Control System 2.5 Remote shutdown workstation operations RMSA3.0l Radiation Monitoring System 3
Changes in system alignment SFSK5.03 Spent Fuel Pool Cooling System 3
j j Spent fuel pool level on area dose rates VFSA1.07 Containment Air Filtration System 2.5 D
D D
Containment supply air smoke VLSA2.02 Containment Hydrogen Control 3.4 3.5 Passive autocatalytic recombiner failure System WLSK1.07 Liquid Radwaste System 2.6 Dilution flow sources (such as; circ water or raw water)
ES-401N, REV 10 T2G2 PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME I SAFETY FUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO CDSA4,04 Condensate System 2.8 Condensate pumps FHSG224 Fuel Handling System
) 38 LI LI LI LI LI LI LI LI LI LI G.2 I
44Glffie19 lsyout, systems, instrumentatian. ndJi FPSK6.08 Fire Protection System 2.8 LI LI LI LI LI LI LI LI LI LI Page 1 of 1 08/17/2015 5:55AM
ES-401N, REV 10 T3 PWR EXAMINATION OUTLINE FORM ES-401N-3 KA NAME / SAFETY FUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO G2.l.18 Conduct of operations 4.6 4.3 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
G2.l 33 Conduct of operations 3.7 3.8 Knowledge of the stations requirements for verbal communications when implementing procedures.
G2.l.40 Conduct of operations 4.3 4.3 Ability to identify and interpret diverse indications to validate the response of another indication.
G2.2.15 Equipment Control 2.6 3.8 J
Knowledge of the process for managing troubleshooting activities.
G2.2.30 Equipment Control 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
G2.3.4 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
G2.3.5 Radiation Control 3.8 4.3 Ability to control radiation releases.
G2.3.6 Radiation Control 3.2 3.7 Li Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, or aligning filters.
G2.4.23 Emergency Procedures/Plans 2.7 4.1 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
G2.4.37 Emergency Procedures/Plans 4.2 4.2 Li Li Li Li Li Li Li Li Li Li Ability to verify that the alarms are consistent with the plant conditions.
Page 1 of 08/17/2015 6:55 AM
ES-401N, REV 10 KA NAME / SAFETY FUNCTIO A-337AA2.Ol Passive Residual Heat Removal Heat Exchanger Leak E-OEA2.lO Reactor Tdp or Safeguards Actuation ES-O. 1 EG2.1.27 Reactor Tnp Response FR-S.1 EG2.4.7 Response to Nuclear Power Generation ATWS SDP-l EG2.4.36 Response to Loss of RCS Inventory During Shutdown SDP-2EA2.05 Response to Loss of Normal Residual Heat Removal System During Shutdown SRO TIGI PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
3.8 4.5 4.1 4.3 2.8 3.3 FORM ES-401N-2 TOPIC:
Passive Residual Heat Removal System inlet temperatures and/or pressures Secondary radiation Ability to locate and operate components, including local controls.
Knowledge of how Abnormal Operating Procedures are used in conjunction with Emergency Operating PrOcedures.
Ability to prioritize and interpret the significance of each annunciator or alarm.
Containment temperature (OE related)
Page 1 of 1 08/17/2015 6:55AM
ES-401N, REV 10 SRO TIG2 PWR EXAMINATION OUTLINE FORM ES-401N-2 FR-C.3EG2.4.14 Response to Saturated Core Cooling Knowledge of Emergency/Abnormal Operating Procedures layout, symbols, and icons.
KA NAME / SAFETY FUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO A-306AA2.03 Evacuation of Control Room 3.3 3
Reactor Coolant System temperature A-328AA2.04 Malfunction of Feedwater Heaters 3.4 3.4 Maximum Reactor Power vs. Pumps in Service (see and Extraction Steam procedure attachment)
ES-l.2EG2.l.18 Post Loss of Coolant Accident 4.6 4.3 Ability to locate control room switches, controls, and Cool Down and Depressurization indications, and to determine that they correctly reflect the desired plant lineup.
3.4 4.1 Page 1 of 1 08/17/2015 6:55AM
ES-401N, REV 10 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401N-2 KA NAME I SAFETY FUNCTIO IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO CASG2.2.17 Compressed Air System 4
4.7 Knowledge of limiting conditions for operations and safety limits.
MSSA2.07 Main Steam System 3.1 3
El El Li El El El El Steam Dump Control System PCSG2.l.14 Passive Containment Cooling 4
3.3 El El El El El El El El [1 Li Ability to use integrated control systems to operate plant System systems or components.
RCSA2.30 Reactor Coolant System 4.4 4.6 Li Li Li Li Li Li Li ll Li Li Li Loss of heat sink RNSG2.4.39 Normal Residual Heat Removal 4.2 4
Li Li Li Li Li Li Li Li Li Li Ability to verify system alarm setpoints and operate System controls identified in the Alarm Response Procedure.
Page 1 of I 08/17/2015 6:55 AM
ES-401N, REV 10 KA NAME / SAFETY FUNCTIO DRCSA2.08 Digital Rod Control System I 1502.4.7 Incore Instrumentation System TOPIC:
Rod Position Indication System Knowledge of how Abnormal Operating Procedures are used in conjunction with Emergency Operating Procedures.
.KnowIdg of th baseo for prioritiaing safety funetins i4ng-obnormol/cmergency--op1-d[ioI is.
cw4 cpj sS+
3.8 4.5 3
.g FORM ES-401N-2 SFSGt Spent Fuel Pool Cooling System GZ.I. L Page 1 of 1 08/17/2015 6:55 AM
ES-401N, REV 10 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401N-3 KA NAME I SAFETY FUNCTIO IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RD SRO G.2.3.9 Radiation Control 2.9 3.1 H H H H H H H H H H Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, or personnel monitoring equipment.
G2.l.2 Conduct of operations 4.1 4.4 j J Knowledge of operator responsibilities during any mode of plant operation.
G2.2.1l Equipment Control 3.9 4.3 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, or tag-outs.
G2.2.2 Equipment Control 4.6 4.1 H
Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
G2.3.2 Radiation Control 2.9 2.9 H H H H H H H H H H Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, or personnel monitoring equipment.
G2.4.24 Emergency Procedures/Plans 4.2 4.1 H H H H H H H H H H Knowledge of annunciator alarms, indications, or response procedures.
G2.4.25 Emergency Procedures/Plans 3.6 4
H H H H H H H H H H Knowledge of operator response to a loss of all annunciators.
Page 1 of 1 08/17/2015 6:56 AM
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