ML13184A174
| ML13184A174 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/28/2013 |
| From: | David Silk Operations Branch I |
| To: | Constellation Energy Nuclear Group |
| Jackson D | |
| Shared Package | |
| ML13060A101 | List: |
| References | |
| ES-401, ES-401-2, TAC U01901 | |
| Download: ML13184A174 (11) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 EI~ilibl; Robert E Ginna Printed: 01/24/2013 Date Of Exam: 04/22/2013 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K6 A1 A2 A3 A4 G* Total A2 G* Total
- 1. 1 3 3 3 3 3 3 18 0 0 0 Emergenc1 2 1 1 3 N/A 1 2 I 9 0 0 0
& N/A Abnormal Tier Plant Totals 4 4 6 4 5 4 27 0 0 0 Evolutions 2.
1 3 2 3 3 I2 2 2 3 2 3 3 28 0 0 0
- 8 I 2 1 1 1 0 1 1 1 1 1 10 0 0 0 0 Plant Systems Tier 0 0 0 4 3 3 2 3 4 3 4 4 38 Totals 1 2 3 4 1 2 3 4
- 3. Generic Knowleqge And Abilities Categories 10 0 3 2 2 3 0 0 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 (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 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 (Nole #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 10tals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
01/24/2013 2:00:39 pm
PWR RO Examination Outline Printed: 01124/2013 Facility: Robert E Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 11 Group 1 Form ES-401-2 EfAPE # / Name / Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000008 Pressurizer Vapor Space Accident / X AK2.02 - Sensors and detectors 2.7* 1 3
000009 Small Break LOCA / 3 X EA2.36 - Difference between 4.2 1 overcooling and LOCA indications 000011 Large Break LOCA / 3 X EAI.07 - Containment isolation system 4.4 1 000015/000017 RCP Malfunctions / 4 X AK3.04 - Reduction of power to below 3.1* 1 the steady state power-to-flow limit 000022 Loss of Rx Coolant Makeup / 2 X AA2.01- Whether charging line leak 3.2 1 exists 000025 Loss ofRHR System /4 X AK3.01 - Shift to alternate flowpath 3.1 1 000026 Loss of Component Cooling Water / X AA 1.06 - Control of flow rates to 2.9 1 8 components cooled by the CCWS 000029 A TWS / 1 X EK2.06 - Breakers, relays, and 2.9* 1 disconnects 000038 Steam Gen. Tube Rupture / 3 X 2.4.1 - Knowledge of EOP entry 4.6 1 conditions and immediate action steps.
000040 Steam Line Rupture - Excessive X AK2.02 - Sensors and detectors 2.6* 1 Heat Transfer / 4 000054 Loss of Main Feedwater / 4 X AKl.02 - Effects offeedwater 3.6 1 introduction on dry S/G 000055 Station Blackout 16 X ;h!j 38 - Knowledge of conditions and
. itations in the facility license.
3.6 1 000056 Loss of Off-site Power / 6 X 2.1.28 - Knowledge of the purpose and 4.1 1 function of major system components and controls.
000058 Loss of DC Power / 6 X AA2.03 - DC loads lost; impact on to 3.5 1 operate and monitor plant systems 000062 Loss of Nuclear Svc Water 14 X AAl.07 - Flow rates to the components 2.9 1 and systems that are serviced by the SWS; interactions among the components WlE04 LOCA Outside Containment / 3 X EK1.2 - Normal, abnormal and 3.5 1 emergency operating procedures associated with LOCA Outside Containment W1E05 Inadequate Heat Transfer - Loss of X EK 1.1 - Components, capacity, and 3.8 1 Secondary Heat Sink / 4 function of emergency systems WlEll Loss of Emergency Coolant Recirc. / X EK3.2 - Normal, abnormal and 3.5 1 4 emergency operating procedures associated with Loss of Emergency Coolant Recirculation 01/24/2013 2:00:11 pm
PWR RO Examination Outline Printed: 01124/2013 Facility: Robert E Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier] / Group 1 Form ES-401-2 E/APE # I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp_ Points KIA Category Totals: 3 3 3 3 3 3 Group Point Total: 18 01/24/2013 2:00:11 pm 2
PWR RO Examination Outline Printed: 01124/2013 Facility: Robert E Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1/ Group 2 Form ES-40l-2 E/APE # I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000051 Loss of Condenser Vacuum 000060 Accidental Gaseous Radwaste ReI. 1 X
~ DAA1.04 - Rod position AK3.02 - Isolation of the auxiliary 2.5*
3.3*
1 1
9 building ventilation 000061 ARM System Alarms 1 7 X AK3.02 - Guidance contained in alarm 3.4 1 response for ARM system 000074 Inad. Core Cooling I 4 X EK2.03 - AFW pump 4.0 1 000076 High Reactor Coolant Activity I 9 X 2.4.45 - Ability to prioritize and 4.1 1 interpret the significance of each annunciator or alarm.
WlE02 SI Termination 13 X EK3.1 - Facility operating 3.3 1 characteristics during transient conditions, including coolant chemistry and the effects oftemperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics W IE03 LOCA Cooldown - Depress. / 4 X EA2.2 - Adherence to appropriate 3.5 1 procedures and operation within the limitations in the facility's license and amendments W 1E0S RCS Overcooling - PTS /4 X EA2.1 - Facility conditions and 3.4 1 selection of appropriate procedures during abnormal and emergency operations W/EIO Natural Circ. /4 X EKl.l - Components, capacity, and 3.3 1 function of emergency systems KIA Category Totals: 1 1 3 1 2 1 Group Point Total: 9 01/24/2013 2:00:17 pm
PWR RO Examination Outline Printed: 01124/2013 Facility: Robert E Ginna ES*401 Plant Systems* Tier 2 I Group 1 Form ES-401*2 SyslEvol # I Name 1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump K1.l2 -CCWS 3.0 1 003 Reactor Coolant Pump X A3.05 - RCP lube oil and 2.7* 1 bearing lift pumps 004 Chemical and Volume Control X K2.05* MOVs 2.7 1 005 Residual Heat Removal X KI.09* RCSO 3.6 1 006 Emergency Core Cooling X K4.10 - Redundant pressure 3.3 1 meters 007 Pressurizer Relief/Quench X K3.01 - Containment 33 1 Tank 008 Component Cooling Water X 2.4.34 - Knowledge ofRO 4.2 )
tasks performed outside the main control room during an emergency and the resultant operational effects.
008 Component Cooling Water X A2.05 - Effect ofloss of 3.3* 1 instrument and control air on the position of the CCW valves that are air operated 010 Pressurizer Pressure Control X K3.03 - ESFAS 4.0 1 012 Reactor Protection K6.11 - Trip setpoint 2.9* 1 calculators 013 Engineered Safety Features X K6.0 1- Sensors and 2.7* 1 Actuation detectors 022 Containment Cooling X A2.0 I - Fan motor 2.5 1 over-current
+-H 026 Containment Spray X Kl.02 - Cooling water 4.1 039 Main and Reheat Steam X K5.08 - Effect of steam 3.6 removal on reactivity 059 Main Feedwater A 1.03 - Power level 2.7* 1 IX restrictions for operation of MFW pumps and valves 059 Main Feedwater X 2.2.22 - Knowledge of 4.0 1 limiting conditions for operations and safety limits.
061 AuxiliarylEmergency Feedwater X K5.05 - Feed line voiding and water hammer 2.7 J I 062 AC Electrical Distribution X K4.05 - Paralleling of ac 2.7* 1 I sources (synchroscope) 063 DC Electrical Distribution X A2.0 1 - Grounds 2.5 1 063 DC Electrical Distribution X K3.02 - Components using 3.5 1 DC control power 064 Emergency Diesel Generator X A 1.02 - Fuel consumption 2.5 I rate with load 064 Emergency Diesel Generator X 2.2.37 - Ability to determine 3.6 1 operability andlor availability of safety related equipment.
01/24/2013 2:00:23 pm
PWR RO Examination Outline Printed: 01124/2013 Facility: Robert E Ginna
, - 401 Plant Systems - Tier 21 Group 1 Form ES-401-2 ES I
Sys/Evol # I Name Kt K2 K3 K4 K5 K6 At A4 G KA Topic Imp. Points 073 Process Radiation Monitoring X A4.03 - Check source for 3.1 1 operability demonstration 076 Service Water X A4.0 1 - SWS pumps 2.9 1 076 Service Water X ater 2.7* 1 078 Instrument Air X ure 3.1 1 103 Containment X A4.04 - Phase A and phase 3.5* 1 B resets 103 Containment X K4.04 - Personnel access 2.5 1 hatch and emergency access hatch KIA Category Totals: 3 2 3 3 2 2 2 3 2 3 3 Group Point Total: 28 01/24/2013 2:00:23 pm 2
PWR RO Examination Outline Printed: 01124/2013 Facility: Robert E Ginna ES - 401 Plant Systems - Tier 2 I Group 2 Form ES-401-2 SyslEvol # I Name Kl K2 ~ K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 001 Control Rod Drive X 2.1.30 - Ability to locate and 4.4 1 operate components, including local controls.
002 Reactor Coolant 014 Rod Position Indication X
TIX A 1.08 - RCS average temperature A2.04 - Misaligned rod 3.7 3.4 1
1 015 Nuclear Instrumentation X K2.0 1 - NIS channels, 3.3 1 components, and interconnections I 027 Containment Iodine Removal X KS.Ol- Purpose of charcoal 3.1* 1 filters I 029 Containment Purge X Kl.03 - Engineered 3.6 I 1 safeguards 034 Fuel Handling Equipment X K4.03 - Overload protection 2.6 1 055 Condenser Air Removal K3.01 - Main condenser 2.5 1 068 Liquid Radwaste X A3.02 - Automatic isolation 3.6 1 075 Circulating Water X A4.01- Emergency/essential 3.2* 1 SWS pumps KIA Category Totals: 1 1 1 1 1 0 1 1 1 1 1 Group Point Total: 10 01/24/2013 2:00:28 pm
Generic Knowledge and Abilities Outline (Tier 3)
PWR RO Examination Outline Printed: 01/24/2013 Facility: Robert E Ginna Form ES-401-3 Generic Cateeory KA Topic Conduct of Operations 2.1.3 I~o,:ledge actIces.
of shift or short-tenn relieftumover 3.7 1 2.1.23 Ability to perfonn specific system and integrated 4.3 1 plant procedures during all modes of plant operation.
2.1.29 Knowledge of how to conduct system lineups, 4.1 1 such as valves, breakers, switches, etc.
Category Total: 3 Equipment Control 2.2.13 Knowledge of tagging and clearance procedures. 4.1 1 2.2.40 Ability to apply Technical Specifications for a 3.4 1 system.
Category Total: 2 Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.2 1 nonnal or emergency conditions.
2.3.13 Knowledge of radiological safety procedures 3.4 1 pertaining to licensed operator duties, such as response to radiation monitor alanns, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Category Total: 2 Emergency ProcedureslPlan 2.4.4 Ability to recognize abnonnal indications for 4.5 1 system operating parameters that are entry-level conditions for emergency and abnonnal operating procedures.
2.4.18 Knowledge of the specific bases for EOPs. 3.3 1 2.4.29 Knowledge of the emergency plan. 3.1 1 Category Total: 3 Generic Total: 10 01/24/2013 2:00:34 pm
ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA T1! G1 062 AA1.02 Loss of Nuclear Service Water: Loads on the SWS in the Control Room. There are no service water loads in the control room proper - only two small room coolers in the Relay Room. Replaced with randomly selected AA1.07 Quest. #15 T1/G1 025AK3.03 Loss of RHR System: Immediate actions contained in EOP for loss of RHRS. There are not any Immediate actions contained in EOPs or APs for loss of RHR. Replaced with randomly selected AK3.01. Quest. #6 T11 G1 040AK2.02 02/05/13: Per telecom wI Chief Examiner, cannot duplicate KIA from initiallLT exam. Authorized random replacement, replaced with 027 AK2.03. Quest. #10
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Robert E. Ginna Date of Examination: April 8,2013 Examination Level: RO SRO X Operating Test Number: 20121LT RETAKE Administrative Topic Type Describe activity to be performed (see Note) Code" Evaluate data obtained from the latest 0-22 cold weather walk down procedure (JS351.001)
Conduct of Operations D,R KIA 2.1.8 3.4/4.1 Ability to coordinate personnel activities outside the control room Determine Time to Boil for a Loss of Shutdown Cooling Conduct of Operations M,R KIA 2.1.25 3.9/4.2 Ability to interpret reference materials, such as graphs, curves, tables, etc.
Fill out an A-52.4 Equipment Control M,R KIA 2.2.23 3.1/4.6 Ability to track Technical Specification limiting conditions for operations Approve radioactive waste discharge/release permit Radiation Control D,R KIA 2.3.11 3.8/4.3 Ability to control radiation releases.
Event Classification (JS340.022)
Emergency Procedures/Plan D, S or R KIA 2.4.41 2.9/4.6 Knowledge of the emergency action level thresholds and classifications.
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
" Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S :3 for ROs; S 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (<:: 1)
(P)revious 2 exams (s 1; randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 I Facility: Robert E. Ginna Date of Examination: April 8, 2013 xam Level: RO D SRO-I X SRO-U D Operating Test No.: 20121lT RETAKE Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety Function A. Transfer the electric plant from 50-50 Normal to 100/0 Lineup on N,S,A 6 Circuit 767.
062 A4.01 3.3/3.1 B. Place the Standby AFW System in service P,S 4S E05 EA1.1 4.1/4.0 (2010 NRC)
C. Place Letdown in Service D,S,A 2 004 A4.0S 3.6/3.1 (JR004.012)
D. Perform Immediate Actions of E-O with SI D,S,A 1 007 EA2.02 4.3/4.6 (JR012.012)
E. Evaluate CNMT Spray flow requirements and reduce flow in E-1 P,S S 026 A4.01 4.S/4.3 (2010 NRC)
F. Startup Containment Mini Purge M,S,A 8 029 A2.03 2.7 /3.1 (JR029.001 )
G. Defeat a Failed PRZR Pressure Channel D,S 7 012 A4.05 3.6/3.6 (JR012.001 )
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
H. Energize a Minimum of 100 KVV Backup heaters onto DIG D,R,E 3 APE OS6 AA1.03 3.2 I 3.3 (JC010.001 )
I. Perform a manual pumpdown of the RCDT using RCDT Pump A 9 N,R 068 K1.04 2.4* /2.S" J. Shift SPF cooling lineup from 'A' to 'B' heat exchangers N,R,L 8 033 G2.1.29 4.1 /4.0
@ 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 1 SRO-II SRO-U (A)lternate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank ::;9/::;8/S4 (E)mergency or abnormal in-plant 2:1/2:1/2:1 (EN)gineered safety feature - I - I 2:1 (control room system)
(L)ow-Power 1 Shutdown 2:1/2:1/2:1 (N)ew or (M)odified from bank including 1(A) 2:2/2:2/2:1 (P)revious 2 exams s 3 I s 3 I ::; 2 (randomly selected)
(R)CA 2:1/2:1/2:1 (S)imulator