ML13324A210
| ML13324A210 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/18/2013 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-321/13-301, 50-366/13-301 | |
| Download: ML13324A210 (20) | |
Text
ES-301 Administrative Topics Outline - RO DRAFT Form ES-301-1 Facility:
PLANT E. I. HATCH ILT-8 Date of Examination: 09/03/2013 Exam Level: RO SRO-l D SRO-U D
Operating Test No.:
2013-301 Administrative Topic (see Type Describe activity to be performed Note)
Code*
Conduct of Operations M, R Heat Stress Stay Time Determination Admin 1 G2.1.26 (3.4/3.6) ALL Conduct of Operations N, R Determine if section 7.4 of the Control Room Admin 2 Surveillance checks, 34SV-SUV-019-2, requires Torus Cooling to be placed in service.
G2.1.07 (4.4/4.7) ALL Emergency Procedures/Plan M, R Determine the Evacuation Route During an Admin 4 Emergency G2.4.39 (3.9/3.8) RO ONLY Radiation Control M, R Evaluate a Radiation Work Permit (RWP) and Admin 5 Survey Map G2.3.7 (3.5/3.6) ALL NOTE: All items (5 total) are required for SRO5. 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 ( 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 Topics Outline SRO-l DRAFT Form ES-301-1 Facility:
PLANT E. I. HATCH ILT-8 Date of Examination: 09/03/2013 Exam Level: RO D SRO-l SRO-U D
Operating Test No.:
201 3-301 Administrative Topic (see Type Describe activity to be performed Note)
Code*
Conduct of Operations M, R Heat Stress Stay Time Determination Admin 1 G2.L26 (3.4/3.6) ALL Conduct of Operations N, R Determine if section 7.4 of the Control Room Admin 2 Surveillance checks, 34SV-SUV-019-2, requires Torus Cooling to be placed in service.
G2.1.07 (4.4/4.7) ALL Equipment Control N, R Review a Required Action Sheet (RAS) for an Admin 3 inoperable Tech Spec component G2.2.23 (4.6) SRO ONLY Radiation Control M, R Evaluate a Radiation Work Permit (RWP) and Admin 5 Survey Map G2.3.7 (3.5/3.6) ALL Emergency Procedures/Plan D, R Determine a Protective Action Recommendation Admin 6 (PAR) G2.4.9 (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 ( 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 Topics Outline SRO-U DRAFT Form ES-301-1 Facility:
PLANT E. 1. HATCH ILT-8 Date of Examination: 09/03/2013 Exam Level: RO D SRO-l D SRO-U Operating Test No.:
2013-301 Administrative Topic (see Type Describe activity to be performed Note)
Code*
Conduct of Operations M, R Heat Stress Stay Time Determination Admin 1 G2.1.26 (3.4/3.6) ALL Conduct of Operations N, R Determine if section 7.4 of the Control Room Admin 2 Surveillance checks, 34SV-SUV-019-2, requires Torus Cooling to be placed in service.
G2.1.07 (4.4/4.7) ALL Equipment Control N, R Review a Required Action Sheet (RAS) for an Admin 3 inoperable Tech Spec component G2.2.23 (4.6) SRO ONLY Radiation Control M, R Evaluate a Radiation Work Permit (RWP) and Admin 5 Survey Map G2.3.7 (3.5/3.6) ALL Emergency Procedures/Plan D, R Determine a Protective Action Recommendation Admin 6 (PAR) G2.4.9 (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 ( 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 RoomIln-Plant Systems Outline ALL DRAFT Form ES-301 -2 Facility:
PLANT E. I. HATCH ILT 8 Date of Examination: 09/02/2013 Exam Level: RO SRO-l SRO-U Operating Test No.:
201 3-301 Control Room Systems@ (8 for P0); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function SF-i CRJSIM 1 Normal Start of Recirc ASD D, L, S Reactivity Control 202001K6.02 (3.1/3.2)
RO ONLY SF-2 CR/SIM 2 Perform a Manual S/U of the Core A, EN, L, M, S Reactor Water Inventory Control Spray With 1st Injection valve failure 209001A4.05 (3.8/3.6)
ALL SF-3 CR/SIM 3 ED Using Head Vents D, S Reactor Pressure Control 295025Ai.01 (2.9/3.0)
RO & SRO-I SF-4 CRISIM 4 Perform A Manual Initiation of LPCI A, L, M, S Heat Removal From the Core From Shutdown Cooling 206000A4.06 (4.3/4.3)
RO & SRO-I SF-5 CRJSIM S Verify An Automatic Isolation Of A, D, E, EN, S Containment Integrity PCIS Group 223002A3.02 (3.5/3.5)
ALL SF-6 CR/SJM 6 Perform a DIG Manual Start A, D, S Electrical Surveillance (Trip Failure) 364000A4.04 (3.7/3.7)
RO & SRO-I SF-8 CRJSIM 7 Loss of Air Actions for Rx Bldg A, D, S Plant Service Systems Ventilation 295019 K2.08 (2.8/2.9)
RO & SRO-I SF-9 CRJSIM 8 Place Control Room HVAC Systems A, C, M Radiation Release in the Isolation Mode (1st C012 fan falls) 290003A4.01 (3.2/3.2)
ALL In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
SF-i PLANT 1 Vent the Scram Air Header on Unit 1 D, E, L, R Reactivity Control 2i2000A4.17 (4.1/4.1)
ALL SF-S PLANT 2 From the Unit 2 Remote Shutdown D, E, R Contain ment Integrity Panel, Start RHR in Torus Cooling 295013 AA1.0i (3.9/3.9)
RO & SRO-I SF-6 PLANT 3 Crosstie Unit 2 Instrument Bus B to D, E, Electrical Instrument Bus A 26200 1A2.07 (3.0/3.2)
ALL
All AC and SAC-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SAC-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 / SAC-I / SAC-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank (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)ew or (M)odified from bank including 1 (A) 2 /
2 /
1 (P)revious 2 exams 3 /
3 /
2 (randomly selected)
(A)CA (S)imulator
Date of Exam:
2013 ES-401, Rev. 9 BWR Examination Outline Form ES4O111 Facility Hatch RO KIA Category Points SRO-OnIy Points Tier*
Group KKKKKKIAAAAG A2 G*
Total 1
2 3
4 5
6l 2
3 4
Total 1.
1 433343 20 4
3 7
Emergency &
2 1
2 1
1 7
2 1
3 Abnormal Plant
NIA NIA
Evolutions Tier Totals
=
27 6
4 10 1
32313223232 26 3
2 5
2.
2 TTTTTT 12 0
2 1
3 Plant Systems Tier Totals
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 3
3 2
2 2
2 1
2 1.
Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (I.e., except for one category in Tier 3 ofthe SRO-only outline, the Tler Totals in each K1A 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 ti 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.
Systemslevolutions 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 ES-401, Attachment 2, for guidance regardIng the elimination of Inappropriate KM 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 I and 2 from the shaded systems and K!A categories.
7
- m generic (G) KIAs in Tiers I and 2 shaH be selected from Section 2 of the K1A Catalog, but the topics must be relevant to the applicable evolution or system.
8.
On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IRS) for the applicable hcense level, and the point totals (N) for each system and category. Enter the group and tier totals for each category in the table above; iffuel handling equipment is sampled In other than Category A2 or G* on the SRO-oniy 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 ofthe WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (N) on Form ES-401-3. Limit SRO selections to lCIAs that are linked to 10 CFR 55.43.
ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION:
IR Ki 1(2 1(3 K4 1(5 1(6 Al A2 A3 A4 G TOPIC:
RO SRO 295001 AK2.06 Partial or Complete Loss of Forced 3.8 3.8
[]
[] [] [] [] [] El [] El El Reactor power Core Flow Circulation/i & 4 295003AK1.02 Partial or Complete Loss of AC/ 6 3.1 3.4 El [] [] [] [] [] El J [1 []
Load shedding 295004G2.1.7 Partial or Total Loss of DC Pwr /6 4.4 4.7
[] [] Ej El El El El El El [.]
Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
295005AK3.02 Main Turbine Generator Trip / 3 3.4 3.5 El El El El El El [1 El El El Recirculation pump downshift/trip: Plant-Specific...
295006AA1.O1 SCRAM! 1 4.2 4.2 El El El El El El ll El El El El RPS 29501 6AA2.07 Control Room Abandonment /7 3.2 3.4 El El El El [1 El El J El El El Suppression chamber pressure 29501 8AK3.06 Partial or Total Loss of CCW /8 3.3 3.3 El El El El El El El El El El Increasing cooling water flow to heat exchangers 295019AA2.02 Partial or Total Loss of Inst. Air / 8 3.6 3.7 El El El El El El El [l El El El Status of safety-related instrument air system loads (see 295021G2.2.40 Loss of Shutdown Cooling! 4 3.4 4.7 El El El El El El El El El El []
Ability to apply technical specifications for a system.
295023AA2.03 Refueling Acc Cooling Mode / 8 3.3 3.8 El El El El El El El [l El El El Airborne contamination levels 295024EA2.06 High Drywell Pressure / 5 4.1 4.1 El El El El El El El ll El El El Suppression pool temperature Page 1 of 2 12/4/2012 6:47 AM
I Knowledge of system purpose and or function.
3.7 4.1 J j J j J J El SBLC injection 3.9 3.9 LI LI Li LI LI El El LI LI Drywell cooling system 3.5 3.8 Pump NPSH 4.3 4.2 LI [ [J El El [] ] El [] [] []
High pressure core spray: Plant-Specific 3.6 3.8
[]
[] J [] [J []
[] fl [j Rod control and information system: Plant-Specific...
2.5 3.1
{] [j El El El [ [] []
Biological effects of radioisotope ingestion 2.5 2.8
[] [] [] [J El [] [] []
[
Fire Classifications by type 3.0 3.1 j [1 [1 LI LI LI El LI [I El Sensors, detectors, indicators ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:
IR 1<1 1<2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:
RO SRO 295025G2.1.27 High Reactor Pressure 13 3.9 4
El El El El El El El El El El I 295026EK3.04 295028EA1.O3 295030EK1.02 295031 EA1.04 295037EK2.12 295038EK1.O1 600000AK1.01 700000AK2.03 Suppression Pool High Water Temp.
5 High Diywell Temperature / 5 Low Suppression Pool Wtr Lvi /5 Reactor Low Water Level /2 SCRAM Condition Present and Power Above APRM Downscale or Unknown
/1 High Off-site Release Rate /9 Plant Fire On Site /8 Generator Voltage and Electric Grid Distrurbancecs Page 2 of 2 121412012 6:47AM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
295009AK1.02 Low Reactor Water Level /2 29501 OAA2.06 High Dnjwell Pressure/S 29501 2AK3.01 High Diywell Temperature / 5 29501 3Ga4.18 High Suppression Pool Temp. / 5 295017AA1.05 High Off-site Release Rate / 9 295035EA1.01 Secondary Containment High Differential Pressure / 5 5000009<2.07 High CTMT Hydrogen Conc. / 5 T1G2 BWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G SRO 3.1 3.6 3.6 4.0 3.2 3.6 3*
DJE1E1DLDDLDL1 TOPIC:
Recirculation pump net positive suction head: Plant-Specific Drywell temperature Increased drywell cooling Knowledge of the specific bases for EOPs.
SPDS/ERIS/CRIDS/GDS: Plant-Specific Secondary containment ventilation system Drywell vent system FORM ES-401-1 RO 3.0 3.6 3.5 3.3 2.7 3.6 3.2 Page 1 of 1 12/4/2012 6:47AM
ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:
IR Ki 1(2 K3 K4 1(5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 2030001(6.02 RHRJLPCI: Injection Mode 2.8 3.0 fl fl fl []
[] [] [] []
D.C. electrical power 2050001(5.02 Shutdown Cooling 2.8 2.9
[] [] [j L]
fl [] [] [] []
Valve operation 2050001(5.03 Shutdown Cooling 2.8 3.1 El [1 [] [] J [] jE] fl [] [] [J Heat removal mechanisms 206000A1.08 HPCI 4.1 4
[j [] [] [] fl [E]
El [] [] []
System lineup: BWR-2,3,4 209001xaoi L.PCS 3.8 3.9 El El El fl El El El [] fl El Reactor water level 2090011(3.03 LPCS 2.9 3.0 El El El El El El El El []
Emergency generators 2110001(2.02 SLC 3.1 3.2 El El El El El El El [] [} El Explosive valves 212000A3.02 RPS 3.2 3.5
[] [] El [J [] El El El El Individual system relay status: Plant-Specific 212000A4.15 RPS 3.9 3.8 El El El El El El El El [] ] El Recirculation pump trip/EOC RPT 2150031(4.05 IRM 2.9 3.0 El El El El El fl El El El []
Changing detector position 21 5004K1.05 Source Range Monitor 2.8 3.0 LI El El El El El El El El El Display control system: Plant-Specific Page 1 of 3 12/4/2012 6:47AM
ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION:
IR Ki K2 1(3 1(4 K5 1(6 Al A2 A3 A4 G TOPIC:
RO Sf0 215005A4.06 APRM I LPRM 3.6 3.8
[]
LI LI LI i LI LI lI LI Verification of proper functionlnI operability 217000K5.06 RCIC 2.7 2.7 Li [] [] [] [j
[]
[] [] []
Turbine operation 2180001(3.01 ADS 4.4 4.4
[] []
[] [] Li [] Li L] [j Restoration of reactor water level after a break that does not depressurize the reactor when required 223002A2.11 PClSINuclear Steam Supply Shutoff 3.8 3.9
[] [] []
[] Li Li [} []
[]
Standby liquid initiation 2390021(2.01 SRVs 2.8 3.2 LI ] [] [] [] Li Li [] [] Li []
SRV solenoids 259002A4.08 Reactor Water Level Control 4.5 4.5 Li Li Li [] [ [j
[] [] {j [
Manually initiate FWCI: FWCI 261000AZ07 SGTS 2.7 2.8
[] [] Li [] [
[] [] []
A.C. electrical failure 261000K1.03 SGTS 2.9 3.1 ) Li Li Li [J [1 Li [J [] [] J Suppression pool 282001K6.03 AC Electrical Distribution 3.5
[] L] [1 CI Li lI Li Li El fl El Generator trip 282002G2.4.4 UPS (AC/DC>
4.5 4.7
[] [] [] []
Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
263000A3.01 DC Electrical Distribution 3.2 3.3 Li Li [J LI CI Li fl []
Meters, dials, recorders, alarms and indicating lights Page2of3 12/4/2012 6:47AM
ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION:
JR Ki K2 K3 K4 1(5 1(6 Al A2 A3 A4 G TOPIC:
RO SRO 264000G2.2.42 EDGs 3.9 4.6
[] [] [] ] [ [j [] [] [] []
Ability to recognize system parameters that are entry level conditions for Technical Specifications 300000A2.Ol Instrument Air 2.9 2.8 fl J J j j J j J Air dryer and filter malfunctions 3000001(1.03 Instrument Air 2.8 2.9
[J [J [] [] [] [] [] [] [] [] []
Containment air 400000A1.01 Component Cooling Water 2.8 2.8
[j []
[] []
[] [] [] []
CCW flow rate Page 3 of 3 12/4/2012 6:47 AM
LILIiLI LI Li LI FORM ES-401-1 ES-401, REV 9 KA NAME / SAFETY FUNCTION:
T2G2 BWR EXAMINATION IR K1K2K3K4K5K6A1 OUTLINE A2 A3 A4 G TOPIC:
RO SRO 201003A09 Control Rod and Dnve MechanIsm 3.2 3.4
[] [] [] [E] [] fl LI ] LI [] Li Low reactor pressure 2040001<1.15 RWCU 3.1 3.2
[] [] [E fl [] fl
[E [] [1 Leak detection: Plant-Specific 215001A4.03 Traversing In-core Probe 3.0 3.1 fl Li [J
[] []
[E]
Isolation valves: Mark-l&lI(Not-BWR1) 216002G2.4.4 RBM LI Li El El Li Li Lj LI Li LI Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
223001A3.05 Primary CTMT and Aux.
4.3 4.3
[] fl LI fl [] [] LI Li [] LI []
Drywell pressure 226001 K6.04 RHR/LPCI: CTMT Spray Mode 2.7 2.7 LI LI LI LI L] I LI Li [E] LI Li Keep fill system 2330001<4.08 Fuel Pool Cooling/Cleanup 2.6 2.8 Li [] []
[] [] [] Li [] []
Pool cooling during loss of coolant accident: BWR-6 2390011<5.05 Main and Reheat Steam 2.8 2.8
[] [] [] [] j [] [] [j [] Li Li Flow indication 2410001<303 Reactor/Turbine Pressure Regulator 3.7 3.8 Li Li fl LI [] fl Li Li Li Li Reactor water level 2450001<4.10 MaIn Turbine Gen. /Aux.
2.6 2.7 Li [] [J j [] Li Li [] [] [] []
Extraction steam 268000A1.02 Radwaste 2.6 3.6 Off-site release Page 1 of 2 12/4/2012 6:47AM
ES-401 REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:
IR Kl 1(2 1(3 K4 1(5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 2860001(2.02 Fire Piotectlon 2.9 3.1
[] ] [] L] [] {J [] [1 [] [] []
Pumps Page 2 of 2 12/4/2012 6:47 AM
TOPIC:
FORM ES-401-1
Knowledge of conduct of operations requirements.
Ability to execute procedure steps.
Ability to coordinate personnel actMties outside the control room.
Knowledge of pre-and post-maintenance operability requirements.
Knowledge of limiting conditions for operations and safety limits.
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 EOP implementation hierarchy and coordination with other support procedures or guidelines.
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO SRO T3BWR EXAMINATION OUTLINE JR Ki K2 1(3 K4 1(5 K6 Al A2 A3 A4 G 3.8 4.2 LiLILILiLiLiLiI G2.l.1 Conductof operations
[] Li LI G2.1.20 Conduct of operations 4.6 4.6 Li Li LI LI Li El LI Li Li LI Ii G2.1.8 Conduct of operations 3.4 4.1
[] [] LI Li LI LI Li LI LI LI I]
G2.2.21 Equipment Control 2.9 4.1 LI Li LI LI Li Li Li LI LI LI II G2.222 Equipment Control 4.0 4.7 Li Li LI Li Li LI Li Li Li Li I1 G2.2.36 Equipment Control 3.1 4.2 Li Li Li Li Li Li LI Li Li Li Ii G2.3.1 I Radiation Control 3.8 Li Li Li LI Li LI Li Li Li Li IJ G2.3.13 Radiation Control 3.4 3.8 Li Li LI Li Li Li Li Li Li Li [1 G2.4.16 Emergency Procedures/Plans 3.5 4.4 LI LI LI Li LI LI LI LI LI LI [1 G2.4.5 Emergency Procedures/Plans LiIZLILILiLILiLiLiLi1 Knowledge of the organization of the operating procedures network for normal, abnormal and emergency evolutions.
Page 1 of 1 12/4/2012 6:47AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
295004AA2.02 Partial or Total Loss of DC Pwr 16 2950 1602.2.37 Control Room Abandonment / 7 295019(32.1.28 Partial or Total Loss of Inst. Air /8 295023AA2.02 Refueling Acc Cooling Mode / 8 295024EA2.02 High Dtyweli Pressure /5 295037G2.4.49 SCRAM Condition Present and Power Above APRM Downscale or Unknown
/1 700000AA2,07 Generator Voltage and Electric Grid Distrurbancecs SRO T1G1 BWR EXAMINATION OUTUNE IR K1K2K3K4K5K6AIA2A3A4G RO SRO 1ELEIDL 3.6 4.6 E1L1EE1L 4.1 4.1 3.4 3.7 3.9 4.0 4.6 4.4 3.6 4.0 FORM ES-401-1 TOPIC:
Extent of partIal or complete loss of D.C. power Ability to determine operability and/or availability of safety related equipment Knowledge of the purpose and function of major system components and controls.
Fuel pool level Drywell temperature Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
Operational status of engineered safety features Page 1 of 1 12/4)2012 6:47AM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
295007AA2.O1 High Reactor Pressure / 3 296012G2.4.11 High Drywell Temperature / 5 295032EA2.03 High Secondary Containment Area Temperature /5 SRO T1G2 BWR EXAMINATION OUTUNE IR K1K2K3K4K5K6A1A2A3A4G RO SRO 4.1 4.1 4.0 4.2 3.8 4.0 FORM ES-401-1 TOPIC:
Reactor pressure Knowledge of abnormal condition procedures.
Cause of high area temperature Page 1 of 1 12/4/2012 6:47 AM
ES-401, REV 9 SRO T2GI BWR EXAMINATION OUTUNE FORM ES-401-1 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
nO SRO 209001G2.4.49 LPCS 4.6 4.4
[] [] [] [] [] [] [] [ [] [] {j Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
215003A2.05 IRM 3.3 3.5
[] [] [J [J
[]
[] [] []
Faulty or erratic operation of detectors/system 218000A2.05 ADS 3.4 3.6 LI U U U U U U Loss of A.C. or D.C. power to ADS valves 281000A2.08 SGTS 2.4 2.7 U U U U U U J U U U D.C. electrical failure 263000G2.4.8 DC Electrical DistributIon 3.8 4.5 UUUUUUUUUUF Page 1 of 1 12/4/2012 6:47 AM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
201006A2.06 RWM 290001 A2.02 Secondary CTMT SRO T2G2 BWR EXAMINATION OUTLINE IR K1K2K3K4K5K6A1A2A3A4G RO SRO 2.9 3.3 D]DEH1JLE1L1
üüE1l1L1EiL 290003G2.4.4 Control Room HVAC FORM ES-401-1 TOPIC:
- Loss of reactor water level control input: P-Spec(Not BWR6)
Excessive outleakage Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
Page 1 oIl 1214/2012 6:47 AM
ES-401, REV 9 SRO T3 BWR EXAMINATION OUTLINE FORM ES4O1-1 KA NAME / SAFETY FUNCTION:
IR 1(1 1(2 K3 K4 1(5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 02.1.3 Conduct of operations 3.7 3.9
[j
[1 [1 [] fl [] [] [] [] []
Knowledge of shift or short term relief turnover practices.
02.1.36 Conduct of operations 3.0 4.1
[]
[] []
[] [] [] [J [J Knowledge of procedures and limitations Involved in core alterations 02.2.18 Equipment Control 2.6 3.8
Knowledge of the process for managing maintenance actMties during shutdown operations.
G2.2.39 Equipment Control 3.9 4.5 fl
[] [1 [] [] [] [] [] J Knowledge of less than one hour technical specification action statements for systems.
02.34 Radiation Control 3.2 3.7
Knowledge of radiation exposure limits under normal and emergency conditions 02.4.38 Emergency Procedures/Plans 2.4 4.4 LI El LI LI LI LI LI [] [ [J Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator.
02.4.4 Emergency Procedures/Plans 4.5 4.7 fl [] [] [] [] fl L] [] LI t]
Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
Page 1 of 1 12/4/2012 6:47AM