NTD-12-084, Draft - Outlines (Folder 2)
| ML12353A165 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/14/2012 |
| From: | Byykkonen T Public Service Enterprise Group |
| To: | David Silk Operations Branch I |
| Jackson D | |
| References | |
| NTD-12-084, TAC U01859 | |
| Download: ML12353A165 (25) | |
Text
ML David Silk Chief Examiner Division of Reactor Safety US Nuclear Regulatory Commission 2100 Renaissance Blvd King of Prussia, P A. 19406 NTD-12-084 September 14,2012 Salem Initial License Class 11-01 Outline Submittal and Draft Examinations
Dear Mr. Silk,
Enclosed are the Outlines and Proposed Examinations (except for the SRO Written draft exam) for the initial license examination to be conducted for Salem candidates during a two-week period beginning on November 26,2012. These materials should be withheld from public disclosure until after the examinations are complete.
Outline Materials included with this package are:
- Form ES-201-2, Examination Outline Quality Checklist.
- Form ES-201-3, Examination SecUlity Agreement.
- Form ES-301-1, (2 pages) Administrative Topics Outline.
- Form ES-301-2, (2 pages) Control Room Systems I In-Plant System Outline.
- Form ES-D-l, (5 pages), Appendix D, Scenario Outline.
Form ES-401-4, Record ofRejected K/As The written exam outlines were developed using the Westinghouse PWROG Outline Generation Software. Safety Function 5: Containment IntegIity, System 025 Ice Condenser System was suppressed during outline development, as it has for all previous Salem exams. Additionally, all KIA's with an importance factor of <2.5 were suppressed.
Exam Materials included with this package are:
- Form ES-301-3, Operating Test Quality Checklist.
- Form ES-301-4, Simulator Scenario Quality Checklist.
- Form ES-401-6, Written Examination Quality Checklist
- Form ES-301-6, Competencies Checklist
- SRO Admin JPMs (8) includes (4) under Emergency Plan category, one for each Scenario Guide (none for spare scenario)
- Simulator Examination Scenario Guides (5)
- RO Written Examination
- 1 compact disc with exam materials
- 1 Thumb Drive with reference materials If you have any questions, please contact Jack Carney, Salem Operations Training Manager at 856-339-1801. The Lead Exam Author, Gerry Gauding, may be contacted as needed at 856-339-1554.
~l~t __________
o~~~konen Facility Representative Salem Operations Support Manager 856-339-1527 Page 2 of2
ES-401 PWR Examination Outline Form ES-401-2 FSI~jli~:
Salem Printed: 09/12/2012 Date Of Exam:
12/03/2012 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G*
Total
- 1.
Emergency 1
2 3
2 3
2 3
1 N/A H-k-N/A 3
1 18 9
0 0
0 0
0 0
Abnormal Tier Plant Totals Evolutions 5
5 4
5 4
4 27 0
0 0
- 2.
1 3
2 3
3 3
2 3
1 2
3 3
28 0
0 0
Plant 2
1 1
1 1
1 1
1 ~
I 1
1 0
10 0 I 0
0 0
Systems Tier Totals 4
3 4
4 4
3 4
2 3
4 3
38 0
0 0
- 3. Generic Knowledge And Abilities Categories 1
2 2
3 2
4 3
10 1
0 2
0 3
0 4
0 0
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 (i.e., 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/evolutions 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 KlAs 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 KIA 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 ES-401-3.
limit SRO selections to KlAs that are linked to 10 CFR 55.43.
09/12/2012 11:45:45 am
PWR RO Examination Outline Printed: 09112/2012 Facility:
Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 11 Group 1 Form ES-40t-2 EfAPE # f Name f Safety Function Kl K2 K3 At A2 G
KA Topic Imp.
Points 000007 Reactor Trip - Stabilization*
Recovery 11 X
EK 1.06 - Relationship ofemergency feedwater flow to S/G and decay heat removal following reactor trip 3.7 1
000011 Large Break LOCA 1 3 X
EK2.02 - Pumps 2.6*
1 000015/000017 RCP Malfunctions /4 X
AK2.10 - RCP indicators and controls 2.8*
1 000022 Loss ofRx Coolant Makeup 12 X
AKl.03 - Relationship between charging flow and PZR level 3.0 1
000026 Loss of Component Cooling Water I 8
X AK3.02 - The automatic actions (alignments) within the CCWS resulting from the actuation of the ESF AS 3.6 1
000027 Pressurizer Pressure Contro~
Malfunction I 3 X
. AAl.OI* PZR heaters, sprays, and PORVs 4.0 1
000029 A TWS I 1 X
- .c; EK2.06 - Breakers, relays, and disconnects 2.9*
1 000038 Steam Gen. Tube Rupture / 3 X 2.4.8 - Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
3.8 1
000054 Loss ofMain Feedwater / 4 X 2.4.46 - Ability to veritY ~
are consistent with the plan 1
000055 Station Blackout /6 X
EA2.03 - Actions necessary to restore power 1
000056 Loss of Off~site Power / 6 X
AK3.02 - Actions contained in EOP for loss of offsite power I
'f.'f I
000057 Loss of Vital AC Inst. Bus / 6 X
AA2.03 - RPS panel alarm annunciators and trip indicators 3.7 1
000065 Loss of Instrument Air / 8 X 2.3.14 - Knowledge ofradiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
3.4 I
000077 Generator Voltage and Electric Grid Disturbances I 6 X
AAl.02 - Turbine / generator controls 3.8 I
W fE04 LOCA Outside Containment / 3 X
EA1.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 4.0 1
W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 X
c*"*
c EK3.2 - Normal, abnormal and emergency operating procedures associated with Loss of Secondary Heat Sink 3.7 1
c..
,~ '.
09/12/2012 11 :45:17 am
PWR RO Examination Outline Printed: 09112/2012 Facility:
Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group I Form ES-401-2 EJAPE # / Name JSafety Function Kl K2 K3 Al A2 G
KA Topic Imp.
Points W/Ell Loss of Emergency Coolant Recirc. /
.x EA2.2 - Adherence to appropriate 3.4 1
4 procedures and operation within the limitations in the facility's license and amendments WlE12 - Steam Line Rupture - Excessive X
EKl.l - Components:, capacity, and 3.4 1
Heat Transfer; 4 function of emergency systems KIA Category Totals:
3 3
3 3
3 3
Group Point Total:
18 09/12/2012 11:45:17 am 2
PWR RO Examination Outline Printed: 09112/2012 Facility:
Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function Kl K2 K3 At A2 G
KA Topic Imp.
Points i 000003 Dropped Control Rod / 1 X
AK2.0S - Control rod drive power 2.S 1
supplies and logic circuits 000074 Inad. Core Cooling / 4 X
EK3.04 - Tripping RCPs 3.9 1
000076 High Reactor Coolant Activity / 9 X
AAl.04 - Failed fuel-monitoring 3.2 1
equipment WlE02 SI Termination / 3 X
EK2.1 - Components, and functions of 3.4 1
control and safety systems, including
- ... instrumentation, signals, interlocks,
.. failure modes, and automatic and manual features W/E03 LOCA Cooldown - Depress. 14 X
EK1.3 - Annunciators and conditions 3.5 1
indicating signals, and remedial actions
.. associated with the LOCA Cooidown and Depressurization WIEOS RCS Overcooling - PTS! 4 X
EK1.2 - Normal, abnormal and 3.4 1
.*. emergency operating procedures associated with Pressurized Thermal Shock W/EIO Natural Circ./4 X
EA 1.2 - Operating behavior 3.6 I
characteristics of the facility WIE 15 Containment Flooding / 5 X 2.1.45 - Ability to identity and interpret 4.3 1
diverse indications to validate the response ofanother indication.
W IE 16 High Containment Radiation I 9 X~
. EA2.2 - Adherence to appropriate 3.0 1
procedures and operation within the limitations in the facility's license and amendments KIA Category Totals:
2 2
1 2
1 1
Group Point Total:
09/12/2012 11:45:23 am 9
PWR RO Examination Outline Printed:
09112/2012 Facility:
Salem Plant Systems - Tier 2/ Group 1 Form ES-401-2 ES - 401 SyslEvol # / Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 003 Reactor Coolant Pump X
K6.02 - RCP seals and seal 2.7 I
water supp ly 003 Reactor Coolant Pump X
K5.03 - Effects of RCP 3.1 I
'. shutdown on T-ave.,
including the reason for the unreliability ofT-ave. in the shutdown loop 004 Chemical and Volume Control X
K4.16 - Temperature at 2.6 1
which the temperature
...; control valve automatically diverts flow from the demineralizer to the VCT; reason for this diversion 005 Residual Heat Removal X
K4.10 - Control ofRHR 3.1 I
heat exchanger outlet flow 005 Residual Heat Removal X
A4.02 - Heat exchanger 3.4*
1 X
bypass flow control 006 Emergency Core Cooling I
K6.10 - Valves 2.6 1
006 Emergency Core Cooling X
K3.01 - RCS 4.1
- I 007 Pressurizer Relief/Quench X
"", K5.02 - Method offorming 3.1 I
Tank a steam bubble in the PZR 008 Component Cooling Water X
1<.
K4.02 - Operation of the 2.9 1
surge tank, including the associated valves and controls 010 Pressurizer Pressure Control
~01 - PZR heaters 3.0 1
012 Reactor Protection X
A3.0 I - Individual channel 3.8 1
tt 013 Engineered Safety Features
- 1. 2.1.27 - Knowledge of 3.9 1
Actuation system purpose andlor function.
013 Engineered Safety Features X
A4.03 - ESF AS initiation 4.5 I
Actuation 022 Containment Cooling X
Al.02 - Containment 3.6 1
. pressure 026 Containment Spray X 2.4.31-Knowledge of 4.2 1
annunciator alarms,
'. indications, or response
....... procedures.
039 Main and Reheat Steam X 2.1.28 - Knowledge of the 4.1 1
. purpose and function of major system components and controls.
039 Main and Reheat Steam X
K5.08 - Effect of steam 3.6 I
removal on reactivity 059 Main Feedwater X
A 1.07 - Feed Pump speed, 2.5*
1 including normal control speed for ICS 059 Main Feedwater X
K1.05 - RCS 3.1
- 1 09/12/2012 11:45:29 am
PWR RO Examination Outline Printed:
09112/2012 Facility:
Salem Plant Systems - Tier 2 I Group 1 Form ES-401-2 ES - 401 SyslEvol # I Name Kl K2 K3 K4 KS K6 Al A.2 A3 A4 G KA Topic Imp.
Points 061 Auxiliary/Emergency X
Kl.03 - Main steam system 3.5 1
Feedwater 061 Auxiliary/Emergency X
K3.02 - S/G 4.2 1
Feedwater 062 AC Electrical Distribution X
A 1.03 - Effect on 2.5 1
instrumentation and controls of switching power supplies supply system releases header pressure 063 DC Electrical Distribution X
K2.0t - Major DC loads 2.9*
1 064 Emergency Diesel Generator X
K 1.03 - Diesel fuel oil 3.6 1
073 Process Radiation Monitoring X
K3.01 Radioactive effluent 3.6 1
076 Service Water X
A2.02 - Service water 2.7 1
078 Instrument Air X
A3.0l - Air pressure 3.1 1
103 Containment X
A4.09 - Containment 3.1
- 1 vacuum system KIA Category Totals:
3 2
3 3
3 2
3 1
2 3
3 Group Point Total:
28 09/12/2012 11:45:29 am 2
PWR RO Examination Outline Printed:
09112/2012 Facility:
Salem Plant Systems - Tier 2 / Group 2 Form ES-401-2 ES - 401 SyslEvol # I Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 001 Control Rod Drive X
Al.Ol-T-ave. and no-load 3.8 1
T-ave oII Pressurizer Level Control X
K6.04 - Operation of PZR 3.1 I
level controllers 015 Nuclear Instrumentation X
A2.02 - Faulty or erratic 3.1 1
operation ofdetectors or compensating components 017 In-core Temperature Monitor X
K5.03 - Indication of 3.7 1
superheating 027 Containment Iodine Removal X
K2.01 - Fans 3.1
- 1 033 Spent Fuel Pool Cooling t;nI K4.03 - Anti-siphon devices 2.6 D=
=
041 Steam Dump/Turbine Bypass K3.02 - RCS 3.8 1
Control 045 Main Turbine Generator X I
." A3.I1 - Generator trip 2.6*
I 068 Liquid Radwaste X
Kl.07 - Sources ofliquid 2.7 I
wastes for LRS 086 Fire Protection X
A4.02 - Fire detection 3.5 1
panels KIA Category Totals:
I 1
1 1
1 1
1 '*.1 1
1 0
Group Point Total:
10 09/12/2012 11:45:35 am
Generic Knowledge and Abilities Outline (Tier 3)
PWR RO Examination Outline Printed: 09/12/2012 Facility:
Salem Form ES-401-3 Generic Catel:orv KA KA ToUic Conduct of Operations 2.1.4 Knowledge of individual licensed operator 3.3 1
responsibilities related to shift staff'mg, such as medical requirements, "no-solo" operation, maintenance ofactive license status, 1 OCFR55, etc.
2.1.28 Knowledge ofthe purpose and function of major 4.1 1
system components and controls.
2.1.40 Knowledge ofrefueling administrative 2.8 1
req uirements.
Category Total:
3 Equipment Control 2.2.20 Knowledge of the process for managing 2.6 1
troubleshooting activities.
2.2.44 Ability to interpret control room indications to 4.2 1
verifY the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
Category Total:
2 Radiation Control 2.3.14 Knowledge of radiation or contamination hazards 3.4 1
that may arise during normal, abnormal, or emergency conditions or activities.
2.3.15 Knowledge ofradiation monitoring systems, such 2.9 1
as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
Category Total:
2 Emergency ProcedureslPlan 2.4.3 Ability to identifY post-accident instrumentation.
3.7 1
2.4.19 Knowledge ofEOP layout, symbols, and icons.
3.4 1
2.4.27 Knowledge of "fire in the plant" procedure.
3.4 1
Category Total:
3 Generic Total:
10 09/12/2012 11:45:40 am
ES-401 PWR Examination Outline Form ES-401-2 Fil~ilitll~
Salem Printed: 09/12/2012 Date Of Exam:
12/03/2012 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G*
Total
- 1.
1 0
0 0
0 0
0 0
3 3
6
- Emergenc,
- 3. Generic Knowledge And 2
I
(
0 0
N/A 0
0 N/A 0
0 2
2 4
Abnormal Plant Evolutions Tier Totals 0
0 0
0 0
0 0
5 5
10
- 2.
1 0
0 0
0 0
0 0
0 0
0 0 I 0
3 2
5 Plant 2
0 0
0 0
0 0
0 0
0 0
0 0
0 I 2 1
3 Systems Tier Totals 0
0 0
0 0
0 0
0 0
0 0
0 5
3 8
1 2
3 4
1 2
3 4
0 7
Abilities Categories 0
0 0
0 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 paints.
- 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/evolutions 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 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 1 and 2 from the shaded systems and KiA categories.
7.* The generic (G) KiAs in Tiers 1 and 2 shall be selected from Section 2 of the KiA 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 KiAs.
- 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 paint 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 ES-401-3.
Limit SRO selections to KiAs that are linked to 10 CFR 55.43.
09/12/2012 12:08:27 pm
PWR SRO Examination Outline Printed: 09112/2012 Facility:
Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function Kl K2 K3 At A2 G KA Topic Imp.
Points 000007 Reactor Trip - Stabilization -
X 2.1.20 - Ability to interpret and execute 4.6 I
Recovery /1 I
procedure steps.
000009 Small Break LOCA / 3
'fi:* X 2.2.44 - Ability to interpret control 4.4 1
room indications to veritY the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
000025 Loss of RHR System I 4 X
AA2.05 - Limitations on LPI flow and 3.5*
1 temperature rates of change 000054 Loss of Main Feedwater / 4 Ix AA2.05 - Status of MFW pumps, 3.7 1
regulating and stop valves 000062 Loss of Nuclear Svc Water / 4 X 2.4.6 - Knowledge ofEOP mitigation 4.7 1
strategies.
WfE12 - Steam Line Rupture - Excessive X
EA2.1 - Facility conditions and 4.0 1
Heat Transfer! 4
.., selection of appropriate procedures during abnormal and emergency operations KIA Category Totals:
0 0
0 0
3 3
Group Point Total:
6 09/12/2012 12:08:01 pm
PWR SRO Examination Outline Printed: 09/12/2012 Facility:
Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 11 Group 2 Form ES-401-2 EIAPE # I Name I Safety Function Kl K2 K3 At A2 G
KA Topic Imp.
Points I 000001 Continuous Rod Withdrawal/I X
AA2.03 - Proper actions to be taken if 4.8 I
.*.. automatic safety functions have not taken place 000028 Pressurizer Level Malfunction 12 X 2.2.43 - Knowledge ofthe process used 3.3 1
to track inoperable alarms.
.,' AA2.04 3.7 000037 Steam Generator Tube Leak / 3 X
Comparison of RCS fluid 1
inputs and outputs, to detect leaks WlEI6 High Containment Radiation /9 l
X 2.4.30 - Knowledge of events related to 4.1 1
system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
KIA Category Totals:
0 0
0 0
2 2
Group Point Total:
4 09/12/2012 12:08:07 pm
PWR SRO Examination Outline Printed:
09112/2012 Facility:
Salem ES - 401 Plant Systems - Tier 2 I Group 1 Form ES-401-2 Sys/Evol # I Name Kl K2 1 K3 1 K4 K5 K61Al A2 A3 A4 G KA Topic Imp_
Points 005 Residual Heat Removal X
A2.02 - Pressure transient 3.7 I
protection during cold shutdown 012 Reactor Protection X
A2.0 I - Faulty bistable operation 3.6 1
013 Engineered Safety Features Actuation X
A2.05 - Loss of dc control power 4.2 1
026 Containment Spray X 2.4.50 - Ability to verifY system alarm setpoints and operate controls identified in the alarm response manuaL 4.0 I
103 Containment X 2.4.22 - Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.
4.4 1
KIA Category Totals:
0 0
0 0
0 0
0 3
0 0
2 Group Point Total:
5 09/12/2012 12:08:12 pm
PWR SRO Examination Outline Printed:
09112/2012 Facility:
Salem Plant Systems - Tier 2 / Group 2 Form ES-401-2 ES - 401 SyslEvol # I Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points r
016 Non-nuclear Instrumentation X 2.2.37 - Ability to determine 4.6 1
operability and/or availability of safety related
.,.; equipment.
034 Fuel Handling Equipment X
A2.0 1 - Dropped fuel 4.4 1
element 086 Fire Protection X
A2.03 - Inadvertent 2.9 1
actuation of the FPS due to circuit failure or welding KIA Category Totals:
0 0
0 0
0 0
0
- 2 0
0 1
Group Point Total:
3 09/12/2012 12:08:17 pm
Generic Knowledge and Abilities Outline (Tier 3)
Facility:
Salem Generic Cate20ry Conduct of Operations Equipment Control Radiation Control Emergency ProceduresIPlan PWR SRO Examination Outline Printed: 09112/2012 Form ES-401-3 KA Topic 2.1.32 Ability to explain and apply system limits and 4.0 1
precautions.
2.1.35 Knowledge ofthe fuel-handling responsibilities 3.9 1
ofSROs.
Category Total:
2 2.2.11 Knowledge of the process for controlling 3.3 1
temporary design changes.
2.2.37 Ability to detennine operability andlor 4.6 1
availability of safety related equipment.
Category Total:
2 2.3.13 Knowledge ofradiological safety procedures 3.8 1
pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Category Total:
1 2.4.26 Knowledge of facility protection requirements, 3.6 1
including fire brigade and portable fire fighting equipment usage.
2.4.29 Knowledge ofthe emergency plan.
4.4 1
Category Total:
2 Generic Total:
7 09/12/2012 12:08:22 pm
ES-401 Randomly r Tier/Group I Selected KIA
~~~
,-~---"".-
002 K4.09
~~...
R0211 026 K4.08
~~~~
~~-~~
R0211 061 Gen 2.2.41 R02II 064 Gen 2.1.19
~-
R02II 086 Gen 2.1.13 ROII2 024 Gen 2.1.13
~~~~~
~-----~~--
RO 112 003 AK2.03 ROII1 OS4 Gen 2.1.17
-~~~
~
~~-
ROllI 062 Gen 2.1.15 ROll1 02S AAl.09 RO 111 008 AK1.01 i--"~~~
SRO 211 010 A2.03 SR03 2.3.4 R
'd of Reiected KlAs 11-01 NRC E F
ES-401-4 Reason for Rejection
~~~~--
Salem has no RCS loop isolation valves. Randomly automatically replaced with System 068, Liquid Radw,!ste system, Kl.07.
Containment spray system has no suction auto swapover feature, it is part ofthe RHR system.
_Rll~0111ly automati(;ally replaced with System 026 Containment Spray system, 2.4.31.
"Ability to obtain" drawings NIA to written exam. Randomly automatically replaced with System 012, RPS ::SYMI..;IU, A3.0I.
"Ability to use Plant Computer" NIA to written exam. Randomly automatically replaced with
~ystem 064, ;EDG ::Sy::Slt;lll, KI.03.
Knowledge ofrequirements for controlling vital area access not related to Fire Protection system.
R~lldolnly automatically re[!laced with system 086, Fire Protection system A4.02.
Knowledge of requirements for controlling vital area access not related to Emergency Boration.
Randomly automatically replaced with 003 Dropped Control Rod, AK2.0S. (see next deletion also)
Salem does not have a metroscope associated with Rod Control. Randomly automatically replaccd with 003. AK2.0S.
"Ability to make accurate, clear, and concise verbal reports" more suited to operating exam
~2'(lluation. Randomly automatically re[!laced with OS4 2.4.46.
"Knowledge ofadministrative requirements such as standing orders, night orders..." not applicable to loss ofNuclear Service Water. Randomly automatically replaced with 065 Loss ofInstrument AIr, 2.3.] 4.
KIA overlapped from previous 2 exams. Deleted per NRC instruction. Randomly replaced with 077 Generator Voltage and Electric Grid Disturbances, AAl.02. This KIA was not sampled on the previous 2 exams.
KIA overlapped from previous 2 exams. Deleted per NRC instruction. Randomly replaced with E12 Uncontrolled Depressurization ofAll Steam Generators, EKl.1. This KIA was not sampled on the 2 previous exams.
KIA overlapped from previous 2 exams. Deleted per NRC instruction. Randomly replaced with OOS Residual Heat Removal system, A2.02. This KIA was not sam[!led on the 2 [!revious exams.
KIA overlapped from previous 2 exams. Deleted per NRC instruction. Randomly replaced with 2.3.13. (Was sampled on the 08-01 RO exam.)
ES-401, Page 27 of 33 Page 1 of 2
ES-401 Record of Reiected KlAs 11-01 NRC Exam Form ES-401-4 SR03 2.1.6 I "Abiiityto manage the control room crew during plant transients" more suited to operating exam
~~---i--------i e!'<.l!uation. Randomly automatically replaced with 2.1.32
~~~~~~~~~t-I-E-0-6-G-eI-1-2-.2-.-6-t-I-K-n-0-w-Cl-edgeotthepl"o~e~fol"~-ak-i-n-g-c-h-an-g-e-s-t-o-p-ro---'-c-e-d-u-re-s-N-A-t-o-D-e-gr~ad-e-d-C-or-e-C-o-o-I-in-g-.-0-2-8---l SRO 111 Ell Gen 2.2.5 I Knowledge of process for making design or operating changes to the facility NA to Loss of Emergency Coolant Recirculation. Randomly automatically replaced with PZR Vapor Space Accident 2.1.4.
next deletion 008 Gen 2.1.4 I Individual Licensed Operator Responsibilities NA to PZR Vapor Space Accident. Randomly automatically replaced with 009 Small Break LOCA, 2.2.44.
---!---------il PZR Control Malfunctions 2.2.43 029 Gen 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing....NA to Containment Purge. Randomly automatically replaced with System 016 Non-Nuclear lInstnllll~ntation, 2.2.37 ES-401, Page 27 of 33 Page 2 of 2
ES-301 Administrative Outline Form ES-301-1 Facility:
SALEM Date of Examination:
11/26/12 Examination Level:
11-01 NRC Administrative Describe activity to be performed Type Topic (See Note)
Code*
Calculate Shutdown Margin Conduct of R,M 2.1.25 Ability to interpret reference materials such as graphs, curves, tables, etc..
Operations R03.9 Conduct of Verify qualifications prior to assuming Licensed Operator Duties.
R,D Operations 2.1.3 Knowledge of Shift or short term relief turnover practices. R03.7 Perform ST.CVC-010 Borated Water Sources (Simulator)
Equipment Control S,N 2.2.37 Ability to determine operability and/or availability of safety related equipment. RO 3.6 Perform radiation dose calculation and determine if any Dose Limit will be exceeded.
Radiation Control R,M,P 2.3.4 Knowledge of radiation exposure limits under normal and emergency conditions. RO 3.2 Emergency N/A Procedures I Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
- Type Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank, (:::;3 for ROs; :::;4 for SROs & RO retakes)
(N)ew or (M)odified from bank (~1)
(P)revious 2 exams (:::;1; randomly selected)
ES-301 Administrative Outline Form ES-301-1 Facility:
SALEM Date of Examination:
11/26/12 Examination Level:
11-01 NRC Administrative Describe activity to be performed Type Topic (See Note)
Code*
Review a completed surveillance to demonstrate Operability of 21 CFCU Conduct (If R,D 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
Operations SRO-4.2 Direct Actions for Spent Fuel Movement (Determine work which would require Conduct of R,D suspension of Fuel Movement)
Operations 2.1.42 Knowledge of new and spent fuel movement procedures. SRO-3.4 Review an OTSC to an Implementing Procedure Equipment Control R,M 2.2.6 Knowledge of the process for making changes in procedures. SRO 3.6 Determine required actions upon Radioactive Effluent Monitor failure Radiation Control R,N 2.3.11 Ability to control radiation releases SRO 4.3 (based on Pilgrim 1/2011 NRC Exam SRO A3)
Emergency Classify Emergency / Non-Emergency Events, and complete the ICMF.
S,M,P Procedures I Plan 2.4.29 Knowledge of the Emergency Plan SRO 4.4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unle9~ they are retaking only the administrative topics, when 5 are required.
- Type Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank, (.:;:3 for ROs;.:;:4 for SROs & RO retakes)
(N)ew or (M)odified from bank (~1)
(P)revious 2 exams (.:;:1; randomly selected)
ES-301 Control Room Systems/ln-Plant System Outline Form ES-301-2 Facility:
SALEM Date of Examination:
11/26/2012 Operating Test No.:
11-01 NRC Exam Level:
SRO-I SRO-U II Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
Safety Function System / ~IPM Title Type Code*
a) Perform a Control Rod Operability Verification.
001 A4.03 RO-4.0 SRO-3.7 A,D,S 1
b) Perform ECCS Accumulator check valve forward flow surveillance (S2.OP-ST.SJ-0006) 006 A4.02, RO-4.0, SRO 3.8 N,A,L,S,EN 2
c) TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve) 010 A4.01, RO 3.7 SRO 3.5 A,D,P,L,S 3
d) TCAF loss of RHR in Shutdown Cooling Mode APE 025 AA1.09 RO-3.2 SRO 3.1 D,L,S 4(pri) e) TCAF Turbine Trip <P-9 (MT ASO trip)
Generic 2.4.31 RO-4.2 SRO-4.1 M,A,P,S 4(sec) f) Adjust PZR Relief Tank (PRT) Level and Pressure 007 A4.04 RO-2.6 SRO-2.6 D,S 5
g) Respond to a loss of Control Air APE 065 AA2.06 RO 3.6 SRO 4.2 A,N,S 8
h) Perform an Authorized Release of Radioactive Liquid Waste to the Circulating Water System (and respond to High Radiation with failure of A,D,S 9
2WL51 to automatically shut.) 068 A4.03 RO-3.9, SRO-3.8 In-Plant Systems (3 for R.O; 3 for SRO-I; 3 or 2 for SRO-U) i)
Locally Borate the RCS APE 068 AA1.08 RO-4.2 SRO-4.2 D,E,R 2
j)
Start and synch EDG Start and synchronize an EDG 064 A2.09 RO-3.1 SRO-3.3 D,R 6
k) Start the SBO Air Compressor Generic 2.1.23 RO-4.3 SRO-4.4 D,E,P 8
@ All RO and SRO-I control room (and in plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes:
Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6/ 4-6 / 2-3 (C)ontroll room (D)irect from bank
~9 / ~8 / ~ 4 (E)mergency or abnormal in-plant
.:::1 /
.::: 1 /.::: 1 (EN)gineered safety feature
- / -
/.::: 1 (control room system)
(L)ow-Power / Shutdown
.:::1
/.:::1 /.:::1 (N)ewor (M)odified from bank including 1 (A)
.:::2 /
.::: 2 /.::: 1 (P)revioLis 2 exams
~ 3 / ~ 3 / ~ 2 (randomly selected)
(R)CA
.:::1 /
.::: 1/.::: 1 (S)imulator
ES-301 Control Room Systems/In-Plant System Outline Form ES-301-2
.----------------------~
Facility:
SALEM Date of Examination:
11/26/2012 Exam Level:
RO ISRO-I!
SRO-U Operating Test No.:
11-01 NRC Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
Safety Function System / JPM Title J
ode*
a) Perform a Control Rod Operability Verification.
001 A4.03 RO-4.0 SRO-3.7 A,D,S 1
b) Perform ECCS Accumulator check valve forward flow surveillance (S2.0P-ST.SJ-0006) 006 A4.02, RO-4.0, SRO 3.8 N,A,L,S,EN 2
TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve) 010 A4.01, RO 3.7 SRO 3.5 A,D,P,L,S 3
, J
,, :cAFTurbine Trip <P-9 (MT ASO trip)
Generic 2.4.31 RO-4.2 SRO-4.1
,r,S 4(sec)
./
~)
PZR Relief Tank (PRT) Level and Pressure 007 A4.04 RO-2.6 SRO-2.6
,"v;:)!Jvnd to a loss of Control Air APE 065 AA2.06 RO 3.6 SRO 4.2
~S 5
8 h) Perform an Authorized Release of Radioactive Liquid Waste to the Circulating Water System (and respond to High Radiation with failure of 2WL51 to automatically shut.) 068 A4.03 RO-3.9, SRO-3.8 A,D,S 9
ems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
I~Y Borate the ReS APE 068 AA 1.08 RO-4.2 SRO-4.2 I
D,E,R 2
and synch EDG Start and synchronize an EDG 064 A2.09 RO-3.1 SRO-3.3 D,R I
6 c+.
coO Air Compressor Generic 2.1.23 RO-4.3 SRO-4.4 D,E,P 8
@ All RO and SRO-I control room (and in plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes:
Criteria for RO / SRO-II SRO-U (A)lternate path 4-6/ 4-5 I 2-3 (C)ontrol room (D)irect from bank
~9 I ~8 I ~ 4 (E)mergency or abnormal in-plant
> 1 I
> 1 I'?, 1 (EN)gineered safety feature
- I - I '?, 1 (control room system)
(L)ow-Power / Shutdown
'?,1
/ '?,1 / '?,1 (N}ewor (M)odified from bank including 1 (A)
>2 /
'?, 2 / '?, 1 (P}revio\\.ls 2 exams
< 3 / ~ 3 / ~ 2 (randomly selected)
(R}CA
'?,1 I
'?, 1/ '?, 1 (S)imulator
Appendix D Scenario Outline Form ES-D-1 Facility:
SALEM 1 & 2 Scenario No.:
ESG-1 Op-TestNo.: 11-01 NRC Examiners:
Operators:
Initial Conditions: 100% power, EOL. PZR Pressure channel II is O/S for calibration.
Turnover: Maintain current power. Perform 1ST Room Cooler Valves Modes 1-6 lAW S2.0P-ST.SW 0014.
Event Malf. No.
No.
1 2
SG0095A TA0314 3
RD0061 I
4 O/R CF12 5
RP0176A C812/C809 RCOOO1 6
RP318A1,2 7
RP0277A,B 8
CV62B
.. (N)ormal, (R)eactlvlty, Event Type*
N CRS/PO I
R ALL C
CRS/PO M
ALL C
ALL C
CRSRO C
RO (I)nstrument, Event Description Safety Related Room cooler surveillance (TS)
SG NR Ch failure (TS)
Stator Water runback wI subsequent auto rod control failure MS10 failure in automatic Inadvertent SI, 2C 4KV vital bus UV following Rx trip, LBLOCA Lo Head ECCS fails to actuate CS fails to actuate Charging pump cavitation CT's: Init Cont Spray, initiate Lo head ECCS, xfer to CLR, trip cavitating charging pp.
(C)omponent, (M)aJor Appendix D, Page 38 of 39
Appendix D Scenario Outline Form ES-D-1 Facility:
SALEM 1 & 2 Scenario No.:
ESG-2 Op-Test No.: 11-01 NRC Examiners:
Operators:
Initial Conditions: 75% power, MOL. Power was reduced 30 minutes ago due to a short duration oscillation on 21 SGFP speed. PZR PORV 2PR1 was declared inoperable 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago due to control circuit problems, and its motor operated block valve 2PR6 is shut and power is removed from its breaker to comply with TSAS 3.4.5 action b.
Turnover: Maintain current power.
Event No.
Malf. No.
Event Type*
Event Description 1
RC0014B I
CRSRO 22 RC Loop Tavg Channel failure (TS) 2 SG0078C C
ALL 500 gpd SGTL on 23 SG. (TS) 3 R
ALL Power reduction 4
SG0078C M
EL0134 C
ALL Loss of Off Site power during SGTR RCS cooldown (ROfCRS restart safeguards loads, PO re-establish RCS cooldown via SG atmospheric reliefs) 6 VL0298 C
CRS RO Only available PZR PORV 2PR2 fails to open results in SGTR without RCS pressure control CTs: 1. Isolate feedwater into and steam flow out of 23 SG,
- 2. Cooldown and maintain CET Target temperature.
- (N)orrnal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Appendix D, Page 38 of 39
Appendix D Scenario Outline Form ES-D-1 Facility:
SALEM 1 & 2 Scenario No.:
ESG-3 Op-Test No.: 11-01 NRC Examiners:
Operators:
Initial Conditions: 47%, BOL, Rod control is in manual for insertion of new NI currents, currently performing SC.IC-DC.NIS-0021 for 2N41. 21 Charging pump is CIT due to bio-fouling. 22 charging pump is in service. 23 charging pump is inoperable but available. 21 SGFP O/S for speed control troubleshooting, HDPs O/S, calorimetric just performed SAT lAW requirement of S2.0P-10.ZZ-0004, Power Operations. 21 and 22 condensate pumps in service. 23A Circulator CIT for corrective maintenance. Minor CW grassing has been occurring.
Turnover: Raise power to 51 %@ 10% per hour, place all HDP liS, continue power ascension to 60%
at 10% per hour, all lAW IOP-4.
Event No.
Malf. No.
Event Type*
Event Description 1
N ALL Raise power AN3855 2
AN0023 CRS 2A 1 125VDC baUer charger trip (TS)
DA003D 3
PR0016A I
CRS RO PZR Press Inst fails hi (during first 1 % power up) (TS) 4 C325 CN0086B C
CRS PO Loss of Circ Water Bus Section 23 causes loss of 2 more "A" circulators, degrading Condenser Vacuum 5
R ALL Power reduction.
6 CN0117A M
ALL 21 Condensate pump trip causes loss of only operating SGFP ---+ Manual Rx trip 7
AF018'IB AF0181A B606 C
CRS PO Sequential loss of all AFW---+FRHS Red Path 8
CV0208B C
ALL FRHS Bleed and Feed initiation (no centrifugal charging pumps available) Cond pump recovery.
CT#1 Establish AFW flow CT#2 Establish RCS Bleed and Feed
- (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Appendix D, Page 38 of 39