ML14240A626
| ML14240A626 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/27/2014 |
| From: | NRC/RGN-II/DRS/OLB |
| To: | Duke Energy Corp |
| Shared Package | |
| ML14290A363 | List: |
| References | |
| 50-413/14-301, 50-414/14-301 | |
| Download: ML14240A626 (19) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM FINAL SUBMITTAL (T-45)
Facility: Catawba Nuclear Station Date of Examination: May 2014 Examination Level: RO SRO El Operating Test Number: 2014301 Administrative Topic Tvne ir
- Describe activity to be performed (See Note) Code Determine License Status G2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing such as Conduct of Operations R D medical requirements, no-solo operation, maintenance of active license status, 1 OCFR55, etc.
Calculate Boric Acid and Water Addition to FWST Conduct of Operations R,D G2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
Tagout A KR (Recirc. Cooling Water) Pump for check valve inspection Equipment Control R N G2.2.13 Knowledge of tagging and clearance procedures.
Calculate Low Pressure Service Water Discharge Flow Radiation Control PR for Radioactive Release G2.3.11 Ability to control radiation releases.
Emergency Procedures/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 & 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, Page 22 of 27
ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM FINAL SUBMITTAL (T-45)
Facility: Catawba Nuclear Station Date of Examination: May 2014 Examination Level: RO LI SRO Operating Test Number: 2014301 Administrative Topic Tune
- Describe activity to be performed (See Note) Code Determine License Status G2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing such as Conduct of Operations R D medical requirements, no-solo operation, maintenance of active license status, 1 OCFR55, etc.
Calculate Boric Acid and Water Addition to FWST Conduct of Operations R,D G2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
Tagout I EBC (Vital Battery)
Equipment Control R,N G2.2.13 Knowledge of tagging and clearance procedures.
Calculate Low Pressure Service Water Discharge Flow Radiation Control PR for Radioactive Release G2.3.11 Ability to control radiation releases.
Update Protective Action Recommendations (PAR)
Emergency Procedures/Plan R,D G2.4.44 Knowledge of emergency plan protective action recommendations 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 & 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, Page22of27
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2014 Exam Level: RO SRO-l LI SRO-U LI Operating Test Number: 2014301 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
Safety System / JPM Title.
Type Code
- Function
- a. Respond to inadvertent dilution while shutdown AL N S 1 004A2.06 Control/mitigate inadvertent dilution. 4.2/4.3
- e. Synchronize the Generator to the Grid A N S 4S 045A4.02 Monitor/operate T/G controls, including breakers. 2.7/2.6
- f. Restore Normal Power to I ETB and shutdown DIG from control room AM S 6 064A4.01 Operate/monitor local/remote operation of the ED/G 4.0/4.3
- g. Shift Lower Containment Ventilation Units C N 5 022A4.01 Operate/monitor CCS fans 3.6/3.6
- h. Shift KC (CCW) Trains MS 8 008A4.01 Operate/monitor CCW indications and controls 3.3/3.1 In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
- i. Break Main Condenser Vacuum Locally Unit 2 -
P D E 4S 045A1 .06 Monitor parameters following T/G trip 3.3/3.7
- j. Shift Main Transformer Auxiliaries P D 6 062A2.01 Operate loads that would degrade plant operation. 3.4/3.9
- k. Place 2A Hydrogen Analyzer in service D,E,L,R 5 028A1 .01 Monitor parameters for operating HRPS controls-H2 con. 3.4/3.8
@ All RO and SRO-l 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 I SRO-l / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrom bank <9/ <8 / <4 (E)mergency or abnormal in-plant 1 / 1 I 1 (EN)gineeredsafetyfeature - I - I 1 (L)ow-Power / Shutdown > 1 I > 1 / > 1 (N)ew or (M)odified from bank including 1(A) 2 I 2 I 1 (P)revious 2 exams < 3 < 3 I < 2 (randomly selected)
(R)CA >1/ >1 />1 (S)im u lator
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2014 Exam Level: RD LI SRO-I SRO-U El Operating Test Number: 2014301 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
Safety System I JPM Title Type Code*
Function
- a. Respond to inadvertent dilution while shutdown ALN S 1 004A2.06 Control/mitigate inadvertent dilution. 4.2/4.3
- e. N/A
- f. Restore Normal Power to I ETB and shutdown DIG from control room AMs 6 064A4.01 Operate/monitor local/remote operation of the ED/G 4.0/4.3
- g. Shift Lower Containment Ventilation Units C N 5 022A4.01 Operate/monitor CCS fans 3.6/3.6
- h. Shift KC (CCW) Trains MS 8 008A4.01 Operate/monitor CCW indications and controls 3.3/3.1 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Break Main Condenser Vacuum Locally Unit 2 -
P D E 4S 045A1 .06 Monitor parameters following T/G trip 3.3/3.7
- j. Shift Main Transformer Auxiliaries P D 6 062A2.01 Operate loads that would degrade plant operation. 3.4/3.9
- k. Place 2A Hydrogen Analyzer in service D E L,R 5 028A1 .01 Monitor parameters for operating HRPS controls-H2 con. 3.4/3.8
© All RO and SRO-l 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 RD / S RD-I / SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irectfrom bank <9/ <8 / <4 (E)mergency or abnormal in-plant > 1 I 1 / 1 (EN)gineered safety feature - I - I > 1 (L)ow-Power / Shutdown > 1 I > 1 I > 1 (N)ew or (M)odified from bank including 1 (A) > 2 I > 2 I > 1 (P)revious 2 exams < 3 < 3 I < 2 (randomly selected)
(R)CA >1/ >1 1>1 (S)imulator ES-3O ,Page 23 of 27
ES-301 Control Room!ln-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2014 Exam Level: RO El SRO-l El SRO-U Operating Test Number: 2014301 Control Room Systems (8 for RO); (7 for SRO-l): (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Functn
- a. N/A
- d. N/A
- e. N/A
- f. Restore Normal Power to 1 ETB and shutdown DIG from control room 064A4.01 Operate/monitor local/remote operation of the ED/G 4.0/4.3 AM S 6
- g. N/A
- h. N/A In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
- i. Break Main Condenser Vacuum Locally Unit 2 -
045A1 .06 Monitor parameters following T/G trip 3.3/3.7 P D E 4S
- j. N/A
- k. Place 2A Hydrogen Analyzer in service D,E L,R 5 028A1 .01 Monitor parameters for operating HRPS controls-H2 con. 3.4/3.8 All RO and SRO-l 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-l / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irectfrom bank <9/ <8 / <4 (E)mergency or abnormal in-plant > 1 / > 1 / > 1 (EN)gineered safety feature - / - / 1 (L)ow-Power / Shutdown > 1 / > 1 / > 1 (N)ew or (M)odified from bank including 1 (A) 2 / 2 / 1 (P)revious 2 exams < 3 < 3 / < 2 (randomly selected)
(R)CA >1/ >1 1>1 (S)i m ulator ES-301, Page 23 of 27
ES-401 PWR Examination Outline Form ES-401-2 Facility: CATAWBA Date of Exam: MAY 2014 ROK/ACatojyPcnts SRO-OnIy_Points Tier Group K K K K K K AAAA G A2 G* Total 1 2 3 4 5 6 1 2 3 4
- Total
- 1. 1 333 33 3 18 3 3 6 Emergency &
Abnormal 2 j* j N/A 2 1 N/A j.. 9 2 2 4 Plant Evolutions Tier Totals 5 4 4 5 4 5 27 5 5 10 1 23232233323 28 2 3 5 2.
Plant 2 11111 10 11 10 0 2 1 3 Systems Tier Totals 3 4 3 4 3 3 4 4 3 3 4 38 4 4 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 1 2 2 2 Note: 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).
- 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 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 K/As 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 K/A categories.
7* The generic (G) K/As in Tiers 1 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 D.1 .b of ES-401 for the applicable K/As.
- 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-401, REV9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:
RO SRO 007EK3.0l Reactor Trip Stabilization Recovery 4 4.6 Actions contained in EOP for reactor trip EJ 008AK2.03 Pressurizer Vapor Space Accident / 3 2.5 2.4 Controllers and positioners 009EK1 .02 Small Break LOCA / 3 3.5 4.2 Use of steam tables 011 EG2.l .7 Large Break LOCA / 3 4.4 47 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
022AK3.06 Loss of Rx Coolant Makeup / 2 3.2 3.3 RCP thermal barrier cooling 025AK2.05 Loss of RHR System /4 2.6 2.6 Reactor building sump 027AA1.02 Pressurizer Pressure Control System 3.1 3 SCR-controlled heaters in manual mode Malfunction / 3 029EA1 .09 ATWS / 1 4 3.6 Manual rod control 038EK3.08 Steam Gen. Tube Rupture / 3 4.1 4.2 Criteria for securing RCP 054AK1 .02 Loss of Main Feedwater / 4 3.6 4.2 Effects of feedwater introduction on dry S/G 055EG2.2.42 Station Blackout / 6 3.9 4.6 Ability to recognize system parameters that are entry level conditions for Technical Specifications Page 1 of 2 10/09/2013 7:21 AM
ES-401, REV9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 056AA1 .26 Loss of Off-site Power! 6 2.5 2.6 Circuit breakers 057AA2.18 Loss of Vital AC Inst. Bus / 6 3.1 3.1 The indicator, valve, breaker, or damper position which will occur on a loss of power 058AK1 .01 Loss of DC Power! 6 2.8 3.1 Battery charger equipment and instrumentation WEO4EK2.2 LOCA Outside Containment / 3 3.8 4.0 Facilitys 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.
weO5EG2.4.1 -
Inadequate Heat Transfer Loss of 3.3 4.0 Knowledge of the specific bases for EOP5.
Secondary Heat Sink I 4 WE1 1 EA2.1 Loss of Emergency Coolant Recirc. / 4 3.4 4.2 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
WE1 2EA2.2 Steam Line Rupture Excessive Heat 3.4 3.9 Adherence to appropriate procedures and operation Transfer / 4 within the limitations in the facilitys license and amendments.
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ES-401, REV 9 TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:
RO SRO 005AG2.4.31 Inoperable/Stuck Control Rod! 1 4.2 4.1 Knowledge of annunciators alarms, indications or response procedures 028AG2.2.3 Pressurizer Level Malfunction! 2 3.8 39 (multi-unit license) Knowledge of the design, procedural and operational differences between units.
032AK1 .01 Loss of Source Range NI / 7 2.5 3.1 Effects of voltage changes on performance 033AA2.07 Loss of Intermediate Range NI / 7 3.9 4.2 Confirmation of reactor trip O61AA1 .01 ARM System Alarms! 7 3.6 3.6 Automatic actuation 067AA1 .01 Plant Fire On-site / 8 3.6 3.6 Respirator air pack WEO3EK3.4 LOCA Cooldown Depress. / 4 3.5 3.9 RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
WE1 3EK1 .2 Steam Generator Over-pressure / 4 3.0 3.3 Normal, abnormal and emergency operating procedures associated with (Steam Generator Overpressure).
WE16EK2.l High Containment Radiation! 9 3.0 3.3 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
Page 1 of 1 l0!09!2013 7:21 AM
ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:
RO SRO 003K4.04 Reactor Coolant Pump 2.8 3.1 Adequate cooling of RCP motor and seals 004A4.13 Chemical and Volume Control 3.3 2.9 VCT level control and pressure control 005A2.02 Residual Heat Removal 3.5 3.7 Pressure transient protection during cold shutdown 006K6.19 Emergency Core Cooling 3.7 3.9 HPI/LPI systems (mode change) 007A3.0l Pressurizer Relief/Quench Tank 2.7 2.9 Components which discharge to the PRT 008G2.4.47 Component Cooling Water 4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
008K1 .04 Component Cooling Water 3.3 3.3 RCS, in order to determine source(s) of RCS leakage into the CCWS 010A2.01 Pressurizer Pressure Control 3.3 3.6 Heater failures 012A3.06 Reactor Protection 3.7 3.7 Trip logic 012K5.02 Reactor Protection 3.1 3.3 Power density 013G2.l .30 Engineered Safety Features Actuation 4.4 4.0 Ability to locate and operate components, including local controls.
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ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 01 3K2.0l Engineered Safety Features Actuation 3.6 3.8 ESFAS/safeguards equipment control 022G2.4.34 Containment Cooling 4.2 4.1 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 025A2.03 Ice Condenser 3.0 3.2 Opening of ice condenser doors 025K6.01 Ice Condenser 3.4 3.6 Upper and lower doors of the ice condenser 026K2.0l Containment Spray 3.4 3.6 Containment spray pumps J
039A1 .03 Main and Reheat Steam 2.6 2.7 Primary system temperature indications and required values, during main steam system warm-up 039K3.04 Main and Reheat Steam 2.5 2.6 MEW pumps 059K1.05 Main Eeedwater 3.1 3.2 RCS 061 K5.0l Auxiliary/Emergency Feedwater 3.6 3.9 D Relationship between AEW flow and RCS heat transfer 062A4.04 AC Electrical Distribution 2.6 2.7 Local operation of breakers 063K4.02 DC Electrical Distribution 2.9 3.2 Breaker interlocks permissives, bypasses and cross-ties.
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ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 064K2.02 Emergency Diesel Generator 2.8 3.1 Fuel oil pumps 073K3.Ol Process Radiation Monitoring 3.6 4.2 LI Radioactive effluent releases 076A1 .02 Service Water 2.6 2.6 LI LI LI LI LI LI Reactor and turbine building closed cooling water LI LI LI LI temperatures.
078A3.01 Instrument Air 3.1 3.2 Air pressure LI LI LI LI LI LI LI LI LI LI 103A1.01 Containment 3.7 4.1 Containment pressure temperature and humidity LI LI LI LI LI LI LI LI LI LI 103K4.01 Containment 3.0 3.7 Vacuum breaker protection LI LI LI LI LI LI LI LI LI LI Page3of3 10/09/2013 7:21 AM
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 002K5.12 Reactor Coolant 3.7 3.9 Relationship of temperature average and loop differential temperature to loop hot-let and cold-leg temperature indications 016K4.03 Non-nuclear Instrumentation 2.8 2.9 Input to control systems 017K6.01 In-core Temperature Monitor 2.7 3.0 Sensors and detectors 027K2.0l Containment Iodine Removal 3.1 3.4 Fans 033A1 .02 Spent Fuel Pool Cooling 2.8 3.3 Radiation monitoring systems 034G2.2.39 Fuel Handling Equipment 3.9 4.5 j Knowledge of less than one hour technical specification EJ action statements for systems.
035K1.14 Steam Generator 3.9 4.1 ESF 071A2.03 Waste Gas Disposal 2.7 3.3 Rupture disk failures LI LI LI LI LI LI LI LI LI LI 079A4.0l Station Air 2.7 2.7 Cross-tie valves with AS LI LI LI LI LI LI LI LI LI LI 086K3.01 Fire Protection 2.7 3.2 Shutdown capability with redundant equipment LI LI LI LI LI LI LI LI LI LI Page 1 of 1 10/09/2013 7:21 AM
ES-401, REV9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G2.1.14 Conduct of operations 3.1 3.1 , Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.
G2.1.19 Conduct of operations 3.9 3.8 Ability to use plant computer to evaluate system or component status.
G2.1.23 Conduct of operations 4.3 4,4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
G2.2.1 Equipment Control 4.5 4.4 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
G2.2.22 Equipment Control 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.
G2.3.1 I Radiation Control 3.8 4.3 Ability to control radiation releases.
G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.4.22 Emergency Procedures/Plans 3.6 4.4 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.
G2.4.3 Emergency Procedures/Plans 3.7 3.9 Ability to identify post-accident instrumentation.
G2.4.32 Emergency Procedures/Plans 3.6 4.0 Knowledge of operator response to loss of all annunciators.
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ES-401, REV 9 SRO TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RD SRO O11EA2.l0 Large Break LOCA/3 4.5 4.7 Verification of adequate core coohng 025AA2.04 Loss of RHR System / 4 3.3 3.6 Location and isolability of leaks 026AG2.4.21 Loss of Component Cooling Water /8 4.0 4.6 Knowledge of the parameters and logic used to assess the LI LI status of safety functions 056AG2.4.30 Loss of Off-site Power / 6 2.7 4.1 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
065AG2.2.36 Loss of Instrument Air / 8 3.1 4.2 Ability to analyze the effect of maintenance activities, such LI LI LI LI LI LI LI []
as degraded power sources, on the status of limiting conditions of operations WEO4EA2.1 LOCA Outside Containment/3 3.4 4.3 Facility conditions and selection of appropriate procedures LI LI LI LI LI LI LI LI LI LI during abnormal and emergency operations.
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ES-401, REV 9 SRO TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 003AA2.03 Dropped Control Rod / 1 3.6 3.8 Dropped rod, using in-core/ex-core instrumentation in-core or loop temperature measurements 028AG2.2.12 Pressurizer Level Malfunction / 2 3.7 4.1 Knowledge of surveillance procedures.
068AG2.2.40 Control Room Evac. I 8 Ability to apply technical specifications for a system.
WE1OEA2.2 Natural Circ. With Seam Void! 4 Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
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ES-401, REV 9 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 003G2.4.45 Reactor Coolant Pump 4.1 4.3 Ability to prioritize and interpret the significance of each annunciator or alarm.
005G2.l.20 Residual Heat Removal 4.6 4.6 Ability to execute procedure steps.
012G2.2.25 Reactor Protection 3.2 4.2 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
076A2.Ol Service Water 3.5 3.7 Loss of SWS 1 03A2.02 Containment 2.2 3.2 Necessary plant conditions for work in containment Page 1 of 1 10/09/2013 7:21 AM
ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:
RO SRO 015G2.l .31 Nuclear Instrumentation 4.6 4.3 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
068A2.02 Liquid Radwaste 2.7 2.8 Lack of tank recirculation prior to release 071A2.Ol Waste Gas Disposal 2.3 2.8 Use of WGDS to prevent entry of oxygen into holdup tanks during liquid transfers Page 1 of 1 10/09/2013 7:21 AM
ES-401, REV9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME! SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G2.1.13 Conduct of operations 2.5 3.2 Knowledge of facility requirements for controlling vital /
controlled access.
G2.2.21 Equipment Control 2.9 4.1 Knowledge of pre- and post-maintenance operability requirements.
G2.2.5 Equipment Control 2.2 3.2 Knowledge of the process for making design or operating changes to the facility G2.3.14 Radiation Control 3.4 3.8 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.6 Radiation Control 2.0 3.8 Ability to aprove release permits G2.4.14 Emergency Procedures/Plans 3.8 4.5 Knowledge of general guidelines for EOP usage.
G2.4.40 Emergency Procedures/Plans 2.7 4.5 Knowledge of the SROs responsibilities in emergency plan implementation.
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