ML13184A126
| ML13184A126 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/22/2013 |
| From: | Constellation Energy Nuclear Group |
| To: | David Silk Operations Branch I |
| Jackson D | |
| Shared Package | |
| ML13060A101 | List: |
| References | |
| TAC U01901 | |
| Download: ML13184A126 (10) | |
Text
ES-401 PWR EXamination Outline Form ES-401-2 Facility,: Ginna 2012 RO Retake Printed: 03/27/2013 Date Of Exam: 04/22/2013 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G* Total A2 G* Total
- 1. I 1 3 3 3 3 3 3 18 0 0 0 Emergency 2 1 ] 3 1 2 1 9 0 0 0
& NIA N/A Abnormal Tier Plant Totals 4 4 6 4 5 4 27 0 0 0 Evolutions 1 3 2 3 3 2 2 2 '>
.) 2 3 3 28 0 0 0 2.
Plant 2 J 1 1 1 1 0 I I 1 I 1 10 0 I 0 0 0 Systems Tier 4 3 4 4 3 2 3 4 3 4 4 38 0 0 0 Totals I 1 2 3 4 1 2 3 4
- 3. Generic Knowledge And 10 0 Abilities Categories 3 2 2 3 0 0 0 0 Note:
- 1. Ensure that at least two topics from every applicable KJA 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 KJA 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 lotal 75 points and Ihe 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 KJA 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 KJAs 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) KJAs in Tiers 1 and 2 shall be selected from Sec!Jon 2 of the KJA 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 KJAs.
- 8. On the following pages, enter the KJA 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-onlyexams.
- 9. For Tier 3, select topics from Section 2 of the KJA catalog, and enter the KJA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KJAs trat are linked to 10 CFR 55.43.
PWR RO Examination Outline Printed: 03/27/20l3 Facility: Ginna 2012 RO Retake ES - 401 Emergency and Abnormal Plant Evolutions - Tier 11 Group 1 Form ES-401 E/APE # / Name 1 Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Quest 000008 Pressurizer Vapor Space Accident / 3 X AK2.02 - Sensors and detectors 2.7* 12 000009 Small Break LOCA I 3 X EA2.36 - Difference between overcooling 4.2 28 and LOCA indications 000011 Large Break LOCA 1 3 EAl.07 - Containment isolation system 4.4 3 000015/000017 RCP Malfunctions 14 X AK3.04 - Reduction of power to below 3.1
- 4 the steady state power-to-flow limit 000022 Loss of Rx Coolant Makeup / 2 X AA2.01 - Whether charging line leak 3.2 5 exists 000025 Loss ofRHR System / 4 X AK3.01 - Shift to alternate flowpath 3.1 6 000026 Loss of Component Cooling Water! 8 X AAI.06 - Control of flow rates to 2.9 7 components cooled by the CCWS 000027 Pressurizer Pressure C X AK2.03 - Controllers and positioners 2.6 10 Malfunction! 3 000029 A TWS ! 1 X EK2.06 - Breakers, relays, and 2.9* 8 disconnects 000038 Steam Gen. Tube Rupture I 3 X 2.4.1 - Knowledge ofEOP entry conditions and immediate action steps.
000054 Loss of Main Feedwater / 4 X AKl.02 - Effects offeedwater 11 introduction on dry SIG 000055 Station Blackout 16 X 2.2.38 - Knowledge of conditions and limitations in the facility license.
000056 Loss of Off-site Power I 6 X 2.1.28 - Knowledge of the purpose and 4.1 13 function of major system components and controls.
000058 Loss of DC Power /6 X AA2.03 - DC loads lost; impact on to 3.5 14 operate and monitor plant systems 000062 Loss of Nuclear Svc Water /4 X AAI.07 - Flow rates to the components 2.9 15 and systems that are serviced by the SWS; interactions among the components W/E04 LOCA Outside Containment I 3 X EK1.2 - Normal, abnormal and 3.5 16 emergency operating procedures associated with LOCA Outside Containment W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink 14 X EKl.l - Components, capacity, and function of emergency systems T3.8117 WiEll Loss of Emergency Coolant Recirc. / 4 X EK3.2 - Normal, abnormal and 3.5 18 emergency operating procedures associated with Loss of Emergency Coolant Recirculation E/APE # / Name i Safety FUllction KI K2 K3 Al A2 G KA Topic Imp. Points KIA Category Totals: 3 3 3 3(( Group Quest Total: 18
PWR RO Examination Outline Printed: 03/27/2013 Facility: Ginna 2012 RO Retake ES - 401 Emergency and Abnormal Plant Evolutions Tier 11 Group 2 Form ES-401-2 E/APE # I Name I Safety Function Kl K2 K3 Al A2 G KA. Topic Imp_ Ouest 000051 Loss of Condenser Vacuum 14 X AAl.04 - Rod position 2.5* 19 3 .J..,*
000060 Accidental Gaseous Radwaste ReI. 19 X AK3.02 - Isolation of the auxiliary 20 building ventilation 000061 ARM System Alarms 1 7 X AK3.02 - Guidance contained in alarm 3.4 21 response for ARM system
~
000074 Inad. Core Cooling 14 X EK2.03 - AFW pump 4.0 I I 000076 High Reactor Coolant Activity 19 X 2.4.45 - Ability to prioritize and interpret 4.1 23 the significan,;e of each annunciator or alarm.
WlE02 SI Termination 13 X EK3.l - Facility operating characteristics 3.3 24 during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics WiE03 LOCA Cool down - Depress. 14 X EA2.2 - Adherence to appropriate 3.5 25 procedures and operation within the limitations in the facility's license and amendments WlE08 RCS Overcooling - PIS I 4 X EA2.1 - Facility conditions and selection 3.4 26 of appropriate procedures during abnormal and emergency operations WIE 10 Natural Circ. I 4 X EKl.l - Components, capacity, and 3.3 function of emergency systems KIA Category Totals: 1 1 3 1 2 1 Group Total: 9
PWR RO F~xamination Outline Printed: 03/27/2013 Facility: Ginna 2012 RO Retake Plant Systems Tier 2 1 Group 1 Form ES-401-2 ES 401 Sys/Evol # / Name 003 Reactor Coolant Pump KI K2 K3 K4 K5 K6 At X
A2 A3 A'I I G KA Topl' WS Imp.
3.0 Ouest 2
003 Reactor Coolant Pump X A3.05 - RCP lube oil and 2.7* 29 bearing lift pumps 004 Chemical and Volume Control K2.05 MOVs 2.7 30 Residual Heat Removal Kl.09 - RCS 3.6 31 006 Emergency Core Cooling I X I K4.10 - Redundant pressure 3.3 32 meters I 007 Pressurizer Relief/Quench Tank X I I K3.01 Containment 3.3 33 008 Component Cooling Water X 2.4.34 Knowledge ofRO 4.2 34 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* 35 instrument and control air on the position of the CCW valves that are air operated 010 Pressurizer Pressure Control X to.03 ESFAS I 4.0 36 012 Reactor Protection K6.11 - Trip setpoint 2.9* 37 calculators 013 Engineered Safety Features K6.01 - Sensors and detectors 2.7* 38 022 Containment Cooling X A2.01 - Fan motor 2.5 39 over-current 026 Containment Spray X Kl.02 Cooling water 4.1 40 039 Main and Reheat Steam X K5.08 - Effect of steam 3.6 41 removal on reactivity 059 Main Feedwater X A 1.03 - Power level 2.7* 42 restrictions for operation of MFW pumps and valves 059 Main Feedwater X 2.2.22 Knowledge of 4.0 43 limiting conditions for operations and safety limits.
061 Auxiliary/Emergency Feedwater X K5.05 Feed line voiding and I 2.7 44 water hammer 062 AC Electrical Distribution X K4.0S - Paralleling of ac 2.7* 45 I sources (synchroscope) 063 DC Electrical Distribution
- 063 DC Electrical Distribution X = X A2.01 - Grounds K3.02 Components DC control power 2.5 3.5 46 47 064 Emergency Diesel Generator X AI.02 Fuel consumption rate 2.S 48 with load
.., c 064 Emergency Diesel Generator X 2.2.37 - Ability to detemiine ..).u 49 operability and/or availability of safety related equipment.
PWR RO Examination Outline Printed: 03127/2013 Facility: Ginna 2012 RO Retake Plant Systems - Tier 21 Group 1 Form ES-401-2 ES - 401 Sys/Evol # I Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Quest 073 Process Radiation Monitoring X A4.03 - Check source for 3.1 50 operability demonstration 076 Service Water X A4.0 1 - SWS pumps 2.9 51 076 Service Water X K2.0 1 - Service water 2.7* 52 078 Instrument Air X A3.01 - Air pressure 3.1 53 103 Containment X A4.04 - Phase A and phase B 3.5* 54 resets 103 Containment X K4.04 - Personnel access 2.5 55 hatch and emergency access hatch KIA Category Totals: 2 3 3 2 2 3 2 3 3 Group Total: 28 2
PWR RO Examination Outline Printed: 03/27/2013 Facility: Ginna 2012 RO Retake Plant Systems - Tier 2 I Group 2 Form ES-401-2 ES 401 J
SyslEvol # / Name Kl K21 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Quest 001 Control Rod Drive X 2.1.30 - Ability to locate and 4.4 56 operate components, including local controls.
002 Reactor Coolant X A 1.08 - RCS average I 3.7 57 temperature 014 Rod Position Indication X A2.04 Misaligned rod 3.4 58 015 Nuclear Instrumentation X K2.01 NIS channels, 3.3 59 components, and interconnections h+=~
027 Containment Iodine Removal X 3.1
- 60 029 Containment Purge X 3.6 61 034 Fuel Handling Equipment X K4.03 Ov,doad pm" ,';0 0 2.6 62 055 Condenser Air Removal X K3.0 I - Main condenser 2.5 63 068 Liquid Radwaste A3.02 Automatic isolation 3.6 64 075 Circulating Water X A4.01 - Emergency/essential 3.2* 65 sws pumps KIA Category Totals: 1 1 1 1 1 0 1 1 1 I 1 Group Total: 10
Generic Knowledge and Abilities Outline (Tier 3)
PWR RO Examination Outline Printed: 03/27/2013 Ginna 2012 RO Retake Form ES-40]-3 Generic Category Conduct of Operations 2.1.3 Knowledge of shift or short-term relief turnover 3.7 66 practices.
2.1.23 Ability to perform specific system and integrated 4.3 67 plant procedures during all modes of plant operation.
2.1.29 Knowledge of how to conduct system lineups, such 4.1 68 as valves, breakers, switches, etc.
Category Total: 3 Equipment Control 2.2.13 Knowledge of tagging and clearance procedures. 4.1 69 2.2.40 Ability to apply Technical Specifications for a 3.4 70 system.
Category Total: 2 Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.2 71 normal or emergency conditions.
2.3.13 Knowledge ofradiologicaJ safety procedures 3.4 72 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: 2 2.4.4 Ability to ,i* abnOlmal indications for system Emergency ProcedureslPlan '0' 4.5 73 operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
2.4.\8 Knowledge ofthe specific bases for EOPs. "..J:.,)" 74 2.4.29 Knowledge ofthe emergency plan. 3.1 75 Category Total: 3 Generic Total: 10
ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA Loss of Nuclear Service Water: Loads on the SWS in the Til G1 062 AA1.02 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 Til G1 025 AK3.03 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 AK3.0i. Quest. #6 02/05/13: Per telecom wI Chief Examiner, cannot duplicate Til G1 040AK2.02 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: May 15-16 , 2013 Examination Level: RO SRO X Operating Test Number: 20121LT RETAKE Administrative Topic Type Describe activity to be performed (see Note) Code*
Perform a Shutdown Margin calculation for a reactor with a dropped control rod Conduct of Operations D,R KIA 001 A4.11 3.5/4.1 Ability to manually operate and/or monitor in the control room: Determination of SDM 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.
Perform an A-52.4, Control of LCO Evaluation i 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 2.3.6 2.0/3.8 Ability to approve release permits Event Classification and Notification form completion Emergency Procedures/Plan D,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 (;C 1)
(P}revious 2 exams (S 1; randomly selected)
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Robert E. Ginna Date of Examination: May 15-16 , 2013 Exam Level: RO D SRO-I X SRO-U D Operating Test No.: 20121LT RETAKE
"" Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / J PM 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 C. Place Letdown in Service D,S,A 2 004 A4.05 3.6/3.1 (JR004.012)
D. Perform Immediate Actions of E-O with SI D,S,A 1 EPE007 EA2.02 4.3/4.6 (.IR012.012)
E. Evaluate CNMT Spray flow requirements and reduce flow in E-1 P,S 5 026 A4.01 4.5/4.3 (JR006.006)
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 A4.04 3.3/3.3 (JR012.001) tems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
H. Energize a Minimum of 100 t<MI Backup heaters onto DIG D,R,E 3 APE 056 AA1.03 3.2/3.3 (JC01 0.001)
I. Perform a manual pumpdown of the RCDT using RCDT Pump A 9 N,R 068 K1.04 2.4* 12.5*
J. Shift SPF cooling lineup from 'A' to 'B' heat exchanger 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 14-6 I 2-3 (C)ontrol room (D)irect from bank :;;9/:;;8/:;;4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature 1 ~1 (control room system)
(L)ow-Power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams :;; 31 s 31:;; 2 (randomly selected)
(R)CA ~1/~1/~1 (S)imulator