ML15175A429
| ML15175A429 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/22/2015 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-321/15-301, 50-366/15-301 50-321/15-301, 50-366/15-301 | |
| Download: ML15175A429 (19) | |
Text
ES-301 Administrative Topics Outline - RO DRAFT Form ES-301-1 Facility: PLANTE. I. HATCH ILT 9 Date of Examination: 03/23/2015 Exam Level: RO ii SRO-I D SRO-U D Operating Test No.:
2015-301 Administrative Topic Type Describe activity to be performed (see Note)
Code*
Conduct of Operations M,R Ul - Correct Reactor Water Level for high Adminl drywell temperatures. G2.1.35 (3.9/4.2) ALL Conduct of Operations Perform Att. 15 of 3400-0PS-001-1, "IRM D,R Alternate Power Check" and then determine any Admin2 additional actions. G2.1.23 (4.3/4.4) ALL Equipment Control N,R Review RCIC Pump Operability Surveillance Admin3 G2.2.12 (3.7/4.1) ALL Emergency Procedures/Plan M,R Determine the Evacuation Route During an Admin4 Emergency G2.4.39 (3.9/3.8) RO ONLY 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 Administrative Topics Outline - SRO-I DRAFT Form ES-301-1 Facility: PLANT E. I. HATCH ILT 9 Date of Examination: 03/23/2015 Exam Level: RO D SRO-I liJ SRO-U D Operating Test No.:
2015-301 Administrative Topic Type Describe activity to be performed (see Note)
Code*
Conduct of Operations M,R Ul - Correct Reactor Water Level for high Admin 1 drywell temperatures. G2.1.35 (3.9/4.2) ALL Conduct of Operations Perform Att. 15 of 34GO-OPS-OO 1-1, "IRM D,R Alternate Power Check" and then determine any Admin2 additional actions. G2.1.23 (4.3/4.4) ALL Equipment Control N,R Review RCIC Pump Operability Surveillance Admin3 G2.2.12 (3.7/4.1) ALL Radiation Control Evaluate Venting DW Irrespective of Offsite Admin5 M,R Release rates IA W PCG G2.3.11 (4.3)
SRO ONLY Emergency Procedures/Plan Given Plant Conditions, Determine the D,S,R Emergency Classification and complete EN Form/
Admin6 G2.4.29 ( 4.0) SRO ONLY 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 - RO DRAFT Form ES-301-2 Facility: PLANT E. I. HATCH ILT 9 Date of Examination: 03/23/2015 Exam Level: RO ~
SRO-I D SRO-U D Operating Test No.:
2015-301 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function SF-1 CR/SIM 1 - Normal Start of Recirc ASD With A,L,D,S Reactivity Control Cooling Water Failure 202001K6.02 (3.1/3.2) ALL SF-2 CR/SIM 2 - Lower RWL Using The RHR System, A,L,M,S Reactor Water Inventory Control LR-JP-06.11 (1 51 Loop fails to start) 20300A4.0l (4.3/4.1) ALL SF-3 CR/SIM 3 - Roll the Main Turbine A,L,D,S Reactor Pressure Control 245000A4.06 (2.7/2.6) ALL SF-4 CR/SIM 4 - HPCI I Place HPCI in Pressure D,S Heat Removal From The Core Control Mode 206000A4.06 (4.3/4.3) ALL SF-5 CR/SIM 5 - Initiate Emergency Torus Venting A,M,S Containment Integrity using the Emergency Vent Path (Alt path) 223001A4.07 (4.2/4.1) ALL SF-6 CR/SIM 6 - Re-Energize Bus with Diesel A,D,S Partial or Complete Loss of AC Generator 295003Al.02 (4.2/4.3) ALL SF-8 CR/SIM 7 - Loss of Air Actions for Rx Bldg A,D,S Plant Service System Ventilation 295019AK2.08 (2.8/2.9) ALL SF-9 CR/SIM 8 - Place Control Room HV AC Systems C,L,D Radioactivity Release in the Purge Mode, JPM 25026 290003A4.01 (3.9/4.0) RO ONLY In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
SF-8 PLANT 1 - JP20024 Actuate DG C02 Sys D,E Plant Service System 286000A2.08 (3.2/3.3) ALL SF-3 PLANT 2 - Loss of Air I Align Emergency D,R,E Reactor Pressure Control Nitrogen to drywell Pneumatics - JPM 25028 218000A2.03 (RO 3.4/SRO 3.6) ALL SF-6 PLANT 3 - JP02718-07.1 Transfer LPCI Bus D
Electrical 262001A4.03 (3.2/3.4) ALL
ES-301 Control Roomnn-Plant Systems Outline-SRO-I DRAFT Form ES-301-2 Facility: PLANT E. I. HATCH ILT 9 Date of Examination: 03/23/2015 Exam Level: RO 0 SRO-I ~
SRO-U 0 Operating Test No.:
2015-301 Control Room Systems0 (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function SF-1 CR/SIM 1 - Normal Start of Recirc ASD With A,L,D,S Reactivity Control Cooling Water Failure 202001K6.02 (3.1/3.2) ALL SF-2 CR/SIM 2-Lower RWL Using The RHR System, A,L,M,S Reactor Water Inventory Control LR-JP-06.11 (1 51 Loop fails to start) 20300A4.01 (4.3/4.1) ALL SF-3 CR/SIM 3 - Roll the Main Turbine A,L,D,S Reactor Pressure Control 245000A4.06 (2.712.6) ALL SF-4 CR/SIM 4 - HPCI I Place HPCI in Pressure D,S Heat Removal From The Core Control Mode 206000A4.06 (4.3/4.3) ALL SF-5 CR/SIM 5 - Initiate Emergency Torus Venting A,M,S Containment Integrity using the Emergency Vent Path (Alt path) 223001A4.07 (4.2/4.1) ALL SF-6 CR/SIM 6-Re-Energize Bus with Diesel A,D,S Partial or Complete Loss of AC Generator 295003Al.02 (4.2/4.3) ALL SF-8 CR/SIM 7 - Loss of Air Actions for Rx Bldg A,D,S Plant Service System Ventilation 295019AK2.08 (2.8/2.9) ALL In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
SF-8 PLANT 1 - JP20024 Actuate DG C02 Sys D,E Plant Service System 286000A2.08 (3.2/3.3) ALL SF-3 PLANT 2 - Loss of Air I Align Emergency D,R,E Reactor Pressure Control Nitrogen to drywell Pneumatics - JPM 25028 218000A2.03 (RO 3.4/SRO 3.6) ALL SF-6 PLANT 3-JP02718-07.1 Transfer LPCI Bus D
Electrical 262001A4.03 (3.2/3.4) ALL
ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility Hatch Date of Exam:
RO KIA Category Points SRO-Only Points Tier Group K
K K
K K
K A
A A
A G
A2 G*
Total 1
2 3
4 5
6 1
2 3
4 Total
- 1.
1 3
4 3
3 3
4 20 4
3 7
Emergency&
2 1
1 1
2 1
1 7
2 1
3 Abnormal Plant NIA NIA Evolutions Tier Totals 4
5 4
5 4
5 27 6
4 10 1
3 2
2 2
3 2
2 2
3 3
2 26 3
2 5
- 2.
1 1
1 1
1 1
2 1
1 1
1 12 0
2 1
3 Plant 2
Systems Tier Totals 4
3 3
3 4
3 4
3 4
4 3
38 5
3 8 -
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2
2 3
3 1
2 2
2
- 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 ATier 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 V'1 from that specified In the table based on NRC revisions. The final RO exan:i. must total 75 points and the SRO-only exam must total 25 points.
- 3.
Systems/evolutions within each group are Identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to E5-401, Attachment 2, 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) Kl As 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.
- 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 (~ote
- 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, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to Kl As that are linked to 10 CFR 55.43.
March 2015
ES-401, REV 9.
KA NAME I SAFETY FUNCTION:
295001AA2.06 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003AK2.04 Partial or Complete Loss of AC I 6 295004AK2.01 Partial or Total Loss of DC Pwr I 6 295005AK3.02 Main Turbine Generator Trip I 3 295006G2.1.31 SCRAM I 1 295016G2.4.11 Control Room Abandonment I 7 295018AA2.02 Partial or Total Loss of CCW I 8 295019AA1.02 Partial or Total Loss of Inst. Air I 8 295021AK3.01 Loss of Shutdown Cooling I 4 295023AK1.03 Refueling Ace Cooling Mode I 8 295024EA2.08 High Drywell Pressure I 5 T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.2 3.3 D D D D D D D ~ D D D 3.4 3.5 D ~ D D D D D D D D D 3.1 3.1 D ~ D D D D D D D D D 3.4 3.5 D D ~ D D D D D D D D 4.6 4.3 D D D D D D D D D D ~
4.o 4.2 D D D D D D D D D D ~
3.1 3.2 D D D D D D D ~ D D D 3.3 3.1 D D D D D D ~ D D D D 3.3 3.4 D D ~ D D D D D D D D 3.7 4.o
~ D D D D D D D D D D 3.6 4.o D D D D D D D ~ D D D Page 1of2 FORM ES-401-1 TOPIC:
Nuclear boiler instrumentation........................
A.C. electrical loads.................................
Battery charger.......................................
Recirculation pump downshift/trip: Plant-Specific...
Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
Knowledge of abnormal condition procedures.
Cooling water temperature.............................
Instrument air system valves: Plant-Specific.........
Raising reactor water level...........................
Inadvertent criticality...............................
Drywell radiation levels..............................
03/18/2014 6:26 AM
E5-401, REV 9 T1G1 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IA K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 295025EK2.01 High Reactor Pressure I 3 4.1 4.1 D ~ D D D D D D D D D 295026EK1.02 Suppression Pool High Water Temp./
3.5 3.8
~ D D D D D D D D D D 5
29502802.1.25 High Drywall Temperature I 5 3.9 4.2 D O O 0 D 0 D D D 0 ~
295030EA 1.03 Low Suppression Pool Wtr Lvl I 5 3.4 3.4 D D D D 0 0 ~ D D 0 D 295031 EK2.09 Reactor Low Water Level I 2 3.3 3.4 D ~ O O D D D D D D 0 295037EK3.03 SCRAM Condition Present and Power 4.1 4.5 O D ~ D 0 0 D D D 0 0 Above APRM Downscale or Unknown
/ 1 295038EA1.01 High Off-site Release Rate I 9 600000AK1.02 Plant Fire On Site I 8 10000002.2.44 Generator Voltage and Electric Grid Distrurbancecs 3.9 4.2 D 0 0 0 0 D ~ D D D D 2.9 3.1
~ D D D D D D D D 0 0 4.2 4.4 D O D D 0 D D D D D ~
Page2 of 2 FORM ES-401-1 TOPIC:
RPS...................................................
Steam condensation....................................
Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
HPCS: Plant-Specific.................................
Recirculation system: Plant-Specific.................
Lowering reactor water level..........................
Stack-gas monitoring system: Plant-Specific..........
Fire Fighting Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 03/18/2014 6:26 AM
E$-401, REV 9 KA NAME I SAFETY FUNCTION:
29500BG2.1.20 High Reactor Water Level I 2 295014AA2.04 Inadvertent Reactivity Addition I 1 295015AK1.02 Incomplete SCRAM I 1 295020AA1.02 Inadvertent Cont. Isolation I 5 & 7 295032EK3.03 High Secondary Containment Area Temperature/ 5 295033EK2.02 High Secondary Containment Area Radiation Levels I 9 295036EA 1.04 Secondary Containment High Sump/Area Water Level I 5 T1G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.6 4.6 D D D D D D D D D D ~
4.1 4.4 D D D D D D D ~ D D D 3.9 4.1
~ D D D D D D D D D D 3.2 3.2 D D D D D D ~ D D D D 3.8 3.9 D D ~ D D D D D D D D 3.8 4.1 D ~ D D D D D D D D D 3.1 3.4 D D D D D D ~ D D D D Page 1of1 FORM E$-401-1 TOPIC:
Ability to execute procedure steps.
Violation of fuel thermal limits......................
Cooldown effects on reactor power.....................
Drywall ventilation/cooling system....................
Isolating affected systems............................
Process radiation monitoring system...................
Radiation monitoring: Plant-Specific.................
03/18/2014 6:26 AM
ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 203000A2.15 RHR/LPCI: Injection Mode 4.2 4.2 D D D D D D D ~ D D D Loop selection logic failure: Plant-Specific 205000K3.02 Shutdown Cooling 3.2 3.3 D D ~ D D D D D D D D Reactor water level: Plant-Specific 206000A1.04 HPCI 3.7 3.8 D D D D D D ~ D D D D Suppression pool level: BWR-2,3,4 206000A4.03 HPCI 3.1 3
O D D D D 0 0 D D ~ D Turbine temperatures: BWR-2,3,4 209001 K2.01 LPCS 3.o 3.1 D ~ O O D D D D D D 0 Pump power 211000K1.05 SLC 3.4 3.6
~ D D D D D 0 0 0 D 0 RWCU 212000K6.05 RPS 3.5 3.8 O O 0 D 0 ~ 0 0 0 D D RPS sensor inputs 215003A2.05 IRM 3.3 3.5 O D D D D D D ~ 0 0 0 Faulty or erratic operation of detectors/system 215004A3.01 Source Range Monitor a.2 3.2 O O O O D D D 0 ~ D 0 Meters and recorders 215004K2.01 Source Range Monitor 2.6 2.8 O ~ O O 0 O 0 0 0 D D SAM channels/detectors 215005K5.03 APRM I LPRM 2.s 3.3 O O O D ~ 0 0 0 0 0 D Control rod symmetrical patterns Page 1of3 03/18/2014 6:26 AM
ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 217000K3.03 RCIC 3.5 3.5 D D ~ D D D D D D D D 218000K1.04 ADS 3.9 4.2
~ D D D D D D D D D D 218000K5.01 ADS 3.8 3.8 D D D D ~ D D D D D D 223002A4.01 PCIS/Nuclear Steam Supply Shutoff 3.6 3.5 D D D D D D D D D ~ D 223002K6.02 PCIS/Nuclear Steam Supply Shutoff 3.0 3.2 D D D D D ~ D D D D D 239002K1.07 SRVs 3.6 3.8
~ D D D D D D D D D D 259002A3.04 Reactor Water Level ~ontrol 3.2 3.2 D D D D D D D D ~ D D 261000A4.02 SGTS 3.1 3.1 D D D D D D D D D ~ D 262001A1.04 AC Electrical Distribution 2.1 2.9 D D D D D D ~ D D D D 262002K4.01 UPS (AC/DC) 3.1 3.4 D D D ~ D D D D D D D 263000G2.1.19 DC Electrical Distribution 3.9 3.8 D D D D D D D D D D ~
Page 2 of 3 FORM ES-401-1 TOPIC:
Decay heat removal Drywell/containment pressure: Plant-Specific ADS logic operation Valve closures D.C. electrical distribution Suppression pool Changes in reactor feedwater flow Suction valves Load currents Transfer from preferred power to alternate power supplies Ability to use plant computer to evaluate system or component status.
03/18/2014 6:26 AM
Es-401, REV 9 T2G1 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 263000K5.01 DC Electrical Distribution 2.6 2.9 0 0 0 0 ~ 0 0 0 0 0 0 264000A3.06 EDGs 3.1 3.2 D O D D 0 0 D D ~ 0 D 300000G2.2.42 Instrument Air 3.9 4.6 D D 0 D 0 0 0 D 0 0 ~
400000K4.01 Component Cooling Water 3.4 3.9 D O D ~ D D 0 D D D 0 Page 3 of 3 FORM ES-401-1 TOPIC:
Hydrogen generation during battery charging.....
Cooling water system operation Ability to recognize system parameters that are entry-level conditions for Technical Specifications Automatic start of standby pump 03/18/2014 6:26 AM
ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 201002K3.03 RMCS 2.9 3.0 D D ~ D D D D D D D D 201003A1.02 Control Rod and Drive Mechanism 2.8 2.8 O D D D 0 0 ~ 0 0 0 0 201006A1.03 RWM 2.9 3.0 D D D D D D ~ D D D D 219000A2.13 RHR/LPCI: Torus/Pool Cooling Mode 3.5 3.7 O O D D 0 D 0 ~ 0 0 0 230000K2.02 RHR/LPCI: Torus/Pool Spray Mode 2.8 2.9 D ~ D D D D D D D D D 245000K5.07 Main Turbine Gen. I Aux.
2.6 2.9 O D D D ~ 0 0 0 0 D 0 2s6000Ks.o1 Reactor Condensate 2.8 2.8 O D D D D ~ D D D D D 259001 G2.4.35 Reactor Feedwater 3.8 4.o D D D D D D D D D D ~
271000K4.01 Offgas 2.9 3.3 D D D ~ D D D D D D D 272000A3.02 Radiation Monitoring 3.6 3.7 D D D D D D D D ~ D D 2aaoooK1.04 Plant Ventilation 2.6 2.6
~ D D D D D D D D D D Page 1of2 FORM ES-401-1 TOPIC:
Ability to process rod block signals CAD drive pressure Latched group indication: P-Spec(Not-BWR6)
High suppression pool temperature Pumps Generator operations and limitations Plant air systems Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects Dilution of hydrogen gas concentration Offgas system isolation indications Applicable component cooling water system: Plant-Specific 03/18/2014 6:26 AM
Es-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 290001A4.04 Secondary CTMT 2.6 2.7 0 0 0 0 0 0 0 0 0 ~ 0 Auxiliary building area temperature: Plant-Specific Page 2 of 2 03/18/2014 6:26 AM
ES-401, REV 9 T3 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IA K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO G2.1.23 Conduct of operations 4.3 4.4 D D D D D D D D D D ~
G2.1.40 Conduct of operations 2.8 3.9 D D D D D D D D D D ~
G2.2.21 Equipment Control 2.9 4.1 D D D D D D D D D D ~
G2.2.36 Equipment Control 3.1 4.2 D D D D D D D D D D ~
G2.3.11 Radiation Control 3.8 4.3 D D D D D D D D D D ~
G2.3.13 Radiation Control 3.4 3.8 D D D D D D D D D D ~
G2.3.14 Radiation Control 3.4 3.8 D D D D D D D D D D ~
G2.4.21 Emergency Procedures/Plans 4.o 4.6 D D D D D D D D D D ~
G2.4.32 Emergency Procedures/Plans 3.6 4.o D D D D D D D D D D ~
G2.4.49 Emergency Procedures/Plans 4.6 4.4 D D D D D D 0 0 0 0 ~
Page 1of1 FORM ES-401-1 TOPIC:
Ability to perfonn specific system and integrated plant procedures during all modes of plant operation.
Knowledge of refueling administrative requirements Knowledge of pre-and post-maintenance operability requirements.
Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations Ability to control radiation releases.
Knowledge of radiological safety procedures pertaining to licensed operator duties Knowledge of radiation or contamination hazards that may arise during nonnal, abnonnal, or emergency conditions or activities Knowledge of the parameters and logic used to assess the status of safety functions Knowledge of operator response to loss of all annunciators.
Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
03/18/2014 6:26 AM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
295001G2.1.7 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295006AA2.02 SCRAM / 1 High Drywall Pressure I 5 SRO T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.4 4.7 0 0 0 0 0 0 0 0 0 0 ~
4.3 4.4 0 0 0 0 0 0 0 ~ 0 0 0 ODODOOD~DDO 295026EA2.01 Suppression Pool High Water Temp. I 4.1 4.2 O O 0 D D D D ~ D D D 5
295028EA2.05 High Drywell Temperature/ 5 3.6 3.8 O D 0 D D D D ~ D D D 295038G2.4.8 High Off-site Release Rate I 9 3.8 4.5 D D D D D D D D D D ~
600000G2.4.47 Plant Fire On Site I 8 4.2 4.2 O D 0 D D D D D 0 D ~
Page 1of1 FORM ES-401-1 TOPIC:
Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
Control rod position..................................
Suppression pool water temperature....................
Torus/suppression chamber pressure: Plant-Specific...
Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
03/18/2014 6:26 AM 295024EA2.02 Drywell temperature 3.9 4.0
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
295008AA2.05 High Reactor Water Level / 2 295014G2.4.11 Inadvertent Reactivity Addition / 1 295035EA2.01 Secondary Containment High Differential Pressure I 5 SRO T1G2 BWR EXAMINATION OUTLINE IA K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 2.9 3.1 D D D D D D D ~ D D D 4.o 4.2 O O O O 0 0 0 0 D 0 ~
3.8 3.9 D O O O D D D ~ D D 0 Page 1of1 FORM ES-401-1 TOPIC:
Swell.................................................
Knowledge of abnormal condition procedures.
Secondary containment pressure: Plant-Specific.......
03/18/2014 6:26 AM
ES-401, REV 9 SRO T2G1 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 205000A2.07 Shutdown Cooling 2.1 2.1 D D D D D D D ~ D D D 206000A2.07 HPCI 3.4 3.6 D D D D D D D ~ D D D 259002G2.4.20 Reactor Water Level Control 3.8 4.3 D D D D D D D D D D ~
262002G2.4.46 UPS (AC/DC) 4.2 4.2 D D D D D D D D D D ~
DDDDDDD~DDD Page 1 of 1 FORM ES-401-1 TOPIC:
Loss of motor cooling: Plant-Specific Low suppression pool level: BWR-2,3,4 Knowledge of operational implications of EOP warnings, cautions and notes.
Ability to verify that the alarms are consistent with the plant conditions.
03/18/2014 6:26 AM 223002A2.01 PCIS/Nuclear Steam Suppy Shutoff 3.2 3.5 AC Electrical Distribution failures
Es-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 202001A2.26 Recirculation 2.9 3.1 0 0 0 0 0 0 0 ~ 0 0 0 215002G2.1.19 ABM 3.9 3.8 0 0 0 0 0 0 0 0 0 0 ~
268000A2.02 Radwaste 2.3 2.7 0 0 0 0 0 0 0 ~ 0 0 0 Page 1of1 FORM ES-401-1 TOPIC:
Incomplete start sequence: Plant-Specific Ability to use plant computer to evaluate system or component status.
High turbidity water 03/18/2014 6:26 AM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
G2.1.39 Conduct of operations G2.2.14 Equipment Control G2.2.25 Equipment Control G2.3.12 Radiation Control G2.3.15 Radiation Control G2.4.31 Emergency Procedures/Plans G2.4.9 Emergency Procedures/Plans SRO T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.6 4.3 D D D D D D D D D D ~
3.9 4.3 D D D D D D D D D D ~
3.2 4.2 D D D D D D D D D D ~
3.2 3.7 D D D D D D D D D D ~
2.9 3.1 D D D D D D D D D D ~
4.2 4.1 D D D D D D D D D D ~
3.8 4.2 D D D D D D D D D D ~
Page 1of1 FORM ES-401-1 TOPIC:
Knowledge of conservative decision making practices Knowledge of the process for controlling equipment configuration or status Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
Knowledge of radiological safety principles pertaining to licensed operator duties Knowledge of radiation monitoring systems Knowledge of annunciators alarms, indications or response procedures Knowledge of low power I shutdown implications in accident (e.g. LOCA or loss of AHR) mitigation strategies.
03/18/2014 6:26 AM