ML112301664
| ML112301664 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/18/2011 |
| From: | Division of Reactor Safety II |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-321/11-301, 50-366/11-301, ES-401, Rev. 9 | |
| Download: ML112301664 (21) | |
Text
Es-401 t Rev. 9 BWR Examination Outline Fonn Es-401*1
{PRIVATE} Facili'ty: Hatch Date of Exam: June 2011 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 4
3 3
3 4
3 20 3
4 7
Emergency &
2 2
1 1
1 1
1 7
1 2
3 Abnormal Plant N/A N/A Evolutions Tier Totals 6
4 4
4 5
4 27 4
6 10 1
3 2
3 2
3 2
2 2
2 3
2 26 2
3 5
- 2.
2 1
1 1
1 1
1 1
1 1
2 1
12 0
1 2
3 Plant Systems Tier Totals 4
3 4
3 4
3 3
3 3
5 3
38 3
5 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 "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 that are not included on the outline should be added. Refer to ES-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) KIAs 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.
S.
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; iffuel 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 KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. limit SRO selections to KIAs that are linked to 10 CFR 55.43.
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
295001AK1.01 Partial or Complete Loss of Forced Core Flow Circulation /1 & 4 295003AK1.04 Partial or Complete Loss of AC /6 295004AK3.02 Partial or Total Loss of DC Pwr /6 295005G2.4.34 Main Turbine Generator Trip / 3 295006G2.4.1 SCRAM /1 295016AA 1.04 Control Room Abandonment / 7 295018AK1.01 Partial or Total Loss of CCW /8 295019AA2.01 Partial or Total Loss of Inst. Air /8 295021G2.4.8 Loss of Shutdown Cooling /4 295023AA2.02 Refueling Acc Cooling Mode / 8 295024EK2.01 High Drywell Pressure / 5 T1Gl BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.5 3.6
~ 0 0 0 0 0 0 0 0 0 0 3.1 3.2
~ 0 0 0 0 0 0 0 0 0 0 2.9 3.3 0 0 ~ 0 0 0 0 0 0 0 0 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~
4.6 4.8 0 0 0 0 0 0 0 0 0 0 ~
3.1 3.2 0 0 0 0 0 0 ~ 0 0 0 0 3.5 3.6
~ 0 0 0 0 0 0 0 0 0 0 3.5 3.6 0 0 0 0 0 0 0 ~ 0 0 0 3.8 4.5 0 0 0 0 0 0 0 0 0 0 ~
3.4 3.7 0 0 0 0 0 0 0 ~ 0 0 0 3.9 4.0 0 ~ 0 0 0 0 0 0 0 0 0 Page 1 of 2 FORM ES-401-1 TOPIC:
Natural circulation...................................
Electrical bus divisional separation..................
Ground isolation/fault determination..................
Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Knowledge of EOP entry conditions and immediate action steps.
A.C. electrical distribution..........................
Effects on component/system operations................
Instrument air system pressure........................
Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
Fuel pool leveL......................................
HPCI (FWCI): Plant-Specific..........................
11/29/2010 6:06 AM
ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 295025EK3.02 High Reactor Pressure 13 3.9 4.1 0 0 ~ 0 0 0 0 0 0 0 0 295026EA1.01 Suppression Pool High Water Temp. I 4.1 4.1 0 0 0 0 0 0 ~ 0 0 0 0 S
295028EK3.06 High Drywell Temperature IS 3.4 3.7 0 0 ~ 0 0 0 0 0 0 0 0 295030EK2.01 Low Suppression Pool Wtr Lvl/S 3.8 3.9 0 ~ 0 0 0 0 0 0 0 0 0 295031 EA2.01 Reactor Low Water Level 12 4.6 4.6 0 0 0 0 0 0 0 ~ 0 0 0 295037EK1.01 SCRAM Condition Present and Power 4.1 4.3
~ 0 0 0 0 0 0 0 0 0 0 Above APRM Downscale or Unknown 11 295038EA1.03 High Off-site Release Rate/9 3.7 3.9 0 0 0 0 0 0 ~ 0 0 0 0 6OOOO0AK2.04 Plant Fire On Site 1 8 2.S 2.6 0 ~ 0 0 0 0 0 0 0 0 0 700000AA2.01 Generator Voltage and Electric Grid 3.5 3.6 0 0 0 0 0 0 0 ~ 0 0 0 Distrurbancecs Page 2 of 2 FORM ES-401-1 TOPIC:
Recirculation pump trip: Plant-Specific..............
Suppression pool cooling..............................
ADS...................................................
HPCI: Plant-Specific.................................
Reactor water level............................
Reactor pressure effects on reactor power.............
Process liquid radiation monitoring system............
Breakers 1 relays 1 and disconnects Operating point on the generator capability curve 11129/2010 6:06 AM
Es-401, REV 9 KA NAME / SAFETY FUNCTION:
295002AK1.04 Loss of Main Condenser Vac I 3 295007AK2.03 High Reactor Pressure 13 295022AK3.02 Loss of CRD Pumps 11 295029EA2.03 High Suppression Pool Wtr LviI 5 295033EK1.02 High Secondary Containment Area Radiation Levels I 9 295034G2.2.39 Secondary Containment Ventilation High Radiation I 9 295036EA1.04 Secondary Containment High SumplArea Water Level 15 T1G2 BWe EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 3.3
~ 0 0 0 0 0 0 0 0 0 0 3.1 3.2 0 ~ 0 0 0 0 0 0 0 0 0 2.9 3.1 0 0 ~ 0 0 0 0 0 0 0 0 3.4 3.5 0 0 0 0 0 0 0 ~ 0 0 0 3.9 4.2
~ 0 0 0 0 0 0 0 0 0 0 3.9 4.5 0 0 0 0 0 0 0 0 0 0 ~
3.1 3.4 0 0 0 0 0 0 ~ 0 0 0 0 Page 1 of 1 FORM Es-401-1 TOPIC:
Increased offgas flow.................................
RHA/LPCI: Plant-Specific.............................
CRDM high temperature.................................
DrywelVcontainment water level.......................
Personnel protection..................................
Knowledge of less than one hour technical specification action statements for systems.
Radiation monitoring: Plant-Specific.................
11/29/2010 6:06 AM
ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 203000A2.13 RHA/LPCI: Injection Mode 3.2 3.3 D D D D D D D ~ D D D Valve openings 203000K5.01 RHA/LPCI: Injection Mode 2.7 2.9 D D D D ~ D D D D D D Testable check valve operation 205000A4.12 Shutdown Cooling 3.4 3.4 D D D D D D D D D ~ D Recirculation loop temperatures 206000A4.10 HPCI 3.7 3.5 D D D D D D D D D ~ D System pumps: BWR-2,3,4 209001 K5.01 LPCS 2.6 2.7 D D D D ~ D D D D D D Indications of pump cavitation 211000K6.04 SLC 2.7 2.8 D D OD 0 ~ 0 0 0 0 0 Core spray system: Plant-Specific 212000A3.02 RPS 3.2 3.5 DO DO D D D D ~ 0 D Individual system relay status: Plant-Specific 215003A1.06 IRM 3.3 3.2 DODO D D ~ D DOD Lights and alarms 215003K5.01 IRM 2.6 2.7 0 0 0 0 ~ 0 0 0 0 0 0 Detector operation 215004A3.01 Source Range Monitor 3.2 3.2 DODO D D D D ~ 0 D Meters and recorders 215005K3.01 APRM / LPRM 4.0 4.0 D 0 ~ 0 D D D D DOD RPS Page 1 of 3 11/29/2010 6:06 AM
ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 217000K1.01 RCIC 3.5 3.5
~ 0 0 0 0 0 0 0 0 0 0 Condensate storage and transfer system 218000K2.01 ADS 3.1 3.3 0 ~ 0 0 0 0 0 0 0 0 0 ADS logic 223002G2.4.3 PCIS/Nuclear Steam Supply Shutoff 3.7 3.9 0 0 0 0 0 0 0 0 0 0 ~
Ability to identify post-accident instrumentation.
239002A4.04 SRVs 4.3 4.3 0 0 0 0 0 0 0 0 0 ~ 0 Suppression pool temperature 239002Kl.05 SRVs 3.1 3.3
~ 0 0 0 0 0 0 0 0 0 0 Plant air systems: Plant-Specific 259002K3.03 Reactor Water Level Control 2.7 2.9 0 0 ~ 0 0 0 0 0 0 0 0 Rod worth minimizer: Plant-Specific 259002K3.07 Reactor Water Level Control 3.4 3.4 0 0 ~ 0 0 0 0 0 0 0 0 Reactor water level indication 261000K4.04 SGTS 2.7 2.9 0 0 0 ~ 0 0 0 0 0 0 0 Radioactive particulate filtration 262001A2.01 AC Electrical Distribution 3.4 3.6 0 0 0 0 0 0 0 ~ 0 0 0 Turbine/generator trip 262002A 1.02 UPS (ACIDC) 2.5 2.9 0 0 0 0 0 0 ~ 0 0 0 0 Motor generator outputs 263000K4.02 DO Electrical Distribution 3.1 3.5 0 0 0 ~ 0 0 0 0 0 0 0 Breaker interlocks,permissives, bypasses and cross ties:
Plant Specific Page 2 of 3 11/29/2010 6:06 AM
ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 264000K1.04 EDGs 3.2 3.3
~ 0 0 0 0 0 0 0 0 0 0 264000K6.08 EDGs 3.6 3.7 0 0 0 0 0 ~ 0 0 0 0 0 300000K2.01 Instrument Air 2.8 2.8 0 ~ 0 0 0 0 0 0 0 0 0 40oo00G2.1.3O Component Cooling Water 4.4 4.0 0 0 0 0 0 0 0 0 0 0 ~
Page 30f 3 FORM ES-401-1 TOPIC:
Emergency generator cooling water system A.C. power Instrument air compressor Ability to locate and operate components, including local controls.
11/29/2010 6:06 AM
ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR Kl K2 K3 K4 KS K6 Al A2 A3 A4 G RO SRO 201002A2.04 RMCS 3.2 3.1 0 DOD 0 D D ~ DOD 201003A4.02 Control Rod and Drive Mechanism 3.S 3.5 0 D D D D D D D 0 ~ D 201006A4.02 RWM 2.9 2.9 0 D D DOD DOD ~ D 219000A1.09 RHRlLPCI: Torus/Pool Cooling Mode 3.2 3.3 0 D D DOD ~ DOD D 230000K2.02 RHRlLPCI: Torus/Pool Spray Mode 2.8 2.9 0 ~ DOD DOD 0 D D 245000K1.04 Main Turbine Gen./ Aux.
3.6 3.7
~ D D DOD D DOD D 256000K5.10 Reactor Condensate 2.8 2.8 D D D D ~ D DOD D D 259001 K6.01 Reactor Feedwater 3.0 3.0 0 D D D 0 ~ 0 DOD D 271000K4.09 Offgas 2.8 3.1 0 D D ~ D D D DOD D 272000A3.01 Radiation Monitoring 3.8 3.9 0 D D D D D D 0 ~ D D 288000G2.1.32 Plant Ventilation 3.8 4.0 DOD DOD D D D 0 ~
Page 1 of 2 FORM ES-401-1 TOPIC:
Control rod block CRD mechanism position: Plant-Specific Pushbutton indicating switches: P-Spec(Not-BWR6)
Suppression chamber air temperature: Plant-Specific Pumps Reactor protection system Air ejection operation Plant air systems Filtration of radioactive particulate Main steam isolation indications Ability to explain and apply all system limits and precautions.
11/29/2010 6:06 AM
E5-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 290001 K3.01 Secondary CTMT 4.0 4.4 0 0 ~ 0 0 0 0 0 0 0 0 Off-site radioactive release rates Page 2 of 2 11/29/2010 6:06AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.20 Conduct of operations G2.1.8 Conduct of operations G2.2.19 Equipment Control G2.2.21 Equipment Control G2.3.11 Radiation Control G2.3.12 Radiation Control G2.3.13 Radiation Control G2.4.16 Emergency Procedures/Plans G2.4.4 Emergency Procedures/Plans G2.4.5 Emergency Procedures/Plans T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.6 4.6 0 0 0 0 0 0 0 0 0 0 ~
3.4 4.1 0 0 0 0 0 0 0 0 0 0 ~
2.3 3.4 0 0 0 0 0 0 0 0 0 0 ~
2.9 4.1 DD DDDDDDDD~
3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~
3.2 3.7 0 0 0 0 0 0 0 0 0 0 ~
3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~
3.5 4.4 0.0 0 0 0 0 0 0 0 0 ~
4.5 4.7 0 0 0 0 0 0 0 0 0 0 ~
3.7 4.3 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 FORM ES-401-1 TOPIC:
Ability to execute procedure steps.
Ability to coordinate personnel activities outside the control room.
Knowledge of maintenance work order requirements.
Knowledge of pre-and post-maintenance operability requirements.
Ability to control radiation releases.
Knowledge of radiological safety principles pertaining to licensed operator duties Knowledge of radiological safety procedures pertaining to licensed operator duties Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.
Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
Knowledge of the organization of the operating procedures network for normal, abnormal and emergency evolutions.
11/29/2010 6:07 AM
E5-401, REV 9 KA NAME / SAFETY FUNCTION:
295001G2.4.41 Partial or Complete Loss of Forced Core Flow Circulation 11 & 4 295005G2.1.23 Main Turbine Generator Trip 13 295018AA2.03 Partial or Total Loss of CCW I 8 29502102.1.23 Loss of Shutdown Cooling I 4 SRO T1G1 BWR EXAMINATION OUTUNE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 4.6 0 0 0 0 0 0 0 0 0 0 ~
4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~
3.2 3.5 0 0 0 0 0 0 0 ~ 0 0 0 4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~
295026EA2.01 Suppression Pool High Water Temp. I 4.1 4.2 0 0 0 0 0 0 0 ~ 0 0 0 5
295031G2.2.25 Reactor Low Water Level/2 3.2 4.2 0 0 0 0 0 0 0 0 0 0 ~
295038EA2.03 High Off-site Release Rate 19 3.5 4.3 0 0 0 0 0 0 0 ~ 0 0 0 Page 1 of 1 FORM ES-401-1 TOPIC:
Knowledge of the emergency action level thresholds and classifications.
Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Cause for partial or complete loss....................
Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Suppression pool water temperature....................
Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
Radiation levels........................................
11129/2010 6:07 AM
ES-401, AEV 9 KA NAME / SAFETY FUNCTION:
295009G2.4.6 Low Reactor Water Level 12 295020G2.4.2 Inadvertent Cont. Isolation I 5 & 7 295034EA2.02 Secondary Containment Ventilation High Radiation 1 9 SAO T1G2 BWA EXAMINATION OUTUNE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.7 4.7 0 0 0 0 0 0 0 0 0 0 ~
4.5 4.6 0 0 0 0 0 0 0 0 0 0 ~
3.7 4.2 0 0 0 0 0 0 0 ~ 0 0 0 Page 1 of 1 FOAM ES-401-1 TOPIC:
Knowledge symptom based EOP mitigation strategies.
Knowledge of system set points. interlocks and automatic actions associated with EOP entry conditions.
Cause of high radiation levels........................
11/29/2010 6:07 AM
E8-401, REV 9 SRO T2G1 BWR EXAMINATION OUTUNE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 205000G2.4.20 Shutdown Cooling 3.8 4.3 D D D D D D D D D D ~
217000G2.4.45 RCIC 4.1 4.3 D D D D D D D D D D ~
259002A2.04 Reactor Water Level Control 3.0 3.1 D D D D D D D ~ D D D 262001A2.06 AC Electrical Distribution 2.7 2.9 D D D D D D D ~ D D D 264000G2.2.12 EDGs 3.7 4.1 D D D D D D D D D D ~
Page 1 of 1 FORM ES-401-1 TOPIC:
Knowledge of operational implications of EOP warnings, cautions and notes.
Ability to prioritize and interpret the significance of each annunciator or alarm.
RFP runout condition: Plant-Specific Deenergizing a plant bus Knowledge of surveillance procedures.
11/29/2010 6:07 AM
ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 201002G2.1.32 RMes 3.8 4.0 D D D D D D D D D D ~
256000G2.1.23 Reactor Condensate 4.3 4.4 D D D D D D D D D D ~
288000A2.01 Plant Ventilation 3.3 3.4 D D D D D D D ~ D D D Page 1 of 1 FORM E8-401-1 TOPIC:
Ability to explain and apply all system limits and precautions.
Ability to perform specific system and integrated plant procedures during all modes of plant operation.
High drywell pressure: Plant-Specific 11/29/2010 6:07 AM
E8-401, REV 9 KA NAME / SAFETY FUNCTION:
RO G2.1.44 Conduct of operations 3.9 G2.2.23 Equipment Control 3.1 G2.2.S Equipment Control 2.2 G2.3.12 Radiation Control 3.2 G2.3.1S Radiation Control 2.9 G2.4.28 Emergency Procedures/Plans 3.2 G2.4.S0 Emergency Procedures/Plans 4.2 SRO T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G SRO 3.8 DDDDDDDDDD ~
4.6 DDDDDDDDDD~
3.2 DDDDDDDDDD~
3.7 DD DDDDDDDD ~
3.1 DD DDDDDDD D~
4.1 DDDDDDDDD D~
4.0 DDDDDDDD DD~
Page 1 of 1 FORM ES-401-1 TOPIC:
Knowledge of RO duties in the control room during fuel handling.
Ability to track Technical Specification limiting conditions for operations.
Knowledge of the process for making design or operating changes to the facility Knowledge of radiological safety principles pertaining to licensed operator duties Knowledge of radiation monitoring systems Knowledge of procedures relating to emergency response to sabotage.
Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
11129/2010 6:07 AM
NRC DRAFT Administrative Topics Outline ES-301-1 FACILITY:
HATCH Date of Examination:
06/06/11 Exam Level:
RO X SRO-I X SRO-U X Operating Test Number:
2011-301 Admin Topic (see Note)
Type Code*
Describe activity to be performed Admin 1 ALL Conduct of Operations N, R Heat Stress Stay Time Determination G2.1.26 Admin 2 ALL Conduct of Operations N, R Fatigue Rule Determination G2.1.5 Admin 3 ALL Equipment Control D, S/R Determine Bulk Average DW temperature per 34SV-SUV-019-1, and then determine any additional DW cooling requirements. G2.2.12 Admin 4 SRO Only Radiation Control M, R Evaluate Venting DW Irrespective of Offsite Release rates IAW PCG 50000EK1.01 Admin 5 RO Only Emergency Procedures/Plan D, R Determine the Evacuation Route During an Emergency G2.4.39 Admin 6 SRO Only Emergency Procedures/Plan N, R Determine if an ENN Form (with errors) is ready for approval by Emergency Director G2.4.40 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 Room/In-Plant Systems Outline -RO DRAFT Form ES-301-2 Facility: PLANT E. I. HATCH HLT 6 Date of Examination: 06/06/2011 Exam Level: RO X SRO-I SRO-U Operating Test No.: 2011-301 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 CR/SIM 1 - Inject SBLC (With a Pump Trip &
Failure of 2G31-F004)
A,D, S SF-1 Reactivity 211000A2.01 CR/SIM 2 - With ED required, Term/Prevent Cond/FW M, S SF-2 Reactor Water Level Control 259001K4.05 CR/SIM 3 - Maintain Rx. Press within 600-800 psig using BPVs, then transition to SRVs with same band, after BPVs fail close.
A, N, L, S SF-3 Reactor Pressure Control 269002A4.01 CR/SIM 4 - RCIC/Place RCIC In Pressure Control Mode N, L, S SF-4 Heat Removal From The Core 217000A4.07 CR/SIM 5 - RHR/LPCI: Containment Spray Mode
/ Initiate Torus Spray with failure A, L, N, S SF-5 Containment Integrity 226001A2.11 CR/SIM 6 - Transfer 4160V Station Service 2A to Normal (SAT)
D, S SF-6 Electrical 262001A4.04 CR/SIM 7 - Respond to a Recirc Pump trip, close discharge valve, plot on P/F Map with Recirc speed
<35%
N, S SF-7 Instrumentation 216000A3.01 CR/SIM 8 - Manually place MCREC in pressurization Mode after failure to auto with C012A not starting A, C, M, EN SF-9 Radiation Release 290003A4.01 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
PLANT 1 - Crosstie Reactor Bldg Plant Service Water A, D, E, L, R SF-8 Plant Service Systems 295018AA1.01 PLANT 2 - Insert a Scram using the RPS Breakers D, E SF-1 Reactivity 295006AA1.05 PLANT 3 - Transfer Vital AC from Alternate to Normal D, R SF-6 Electrical 262002A4.01 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 / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
ES-301 Control Room/In-Plant Systems Outline -SRO I DRAFT Form ES-301-2 Facility: PLANT E. I. HATCH HLT 6 Date of Examination: 06/06/2011 Exam Level: RO SRO-I X SRO-U Operating Test No.: 2011-301 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 CR/SIM 1 - Inject SBLC (With a Pump Trip &
Failure of 2G31-F004)
A,D, S SF-1 Reactivity 211000A2.01 CR/SIM 2 - With ED required, Term/Prevent Cond/FW M, S SF-2 Reactor Water Level Control 259001K4.05 CR/SIM 3 - Maintain Rx. Press within 600-800 psig using BPVs, then transition to SRVs with same band, after BPVs fail close.
A, N, L, S SF-3 Reactor Pressure Control 269002A4.01 CR/SIM 5 - RHR/LPCI: Containment Spray Mode
/ Initiate Torus Spray with failure A, L, N, S SF-5 Containment Integrity 226001A2.11 CR/SIM 6 - Transfer 4160V Station Service 2A to Normal (SAT)
D, S SF-6 Electrical 262001A4.04 CR/SIM 7 - Respond to a Recirc Pump trip, close discharge valve, plot on P/F Map with Recirc speed
<35%
N, S SF-7 Instrumentation 216000A3.01 CR/SIM 8 - Manually place MCREC in pressurization Mode after failure to auto with C012A not starting A, C, M, EN SF-9 Radiation Release 290003A4.01 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
PLANT 1 - Crosstie Reactor Bldg Plant Service Water A, D, E, L, R SF-8 Plant Service Systems 295018AA1.01 PLANT 2 - Insert a Scram using the RPS Breakers D, E SF-1 Reactivity 295006AA1.05 PLANT 3 - Transfer Vital AC from Alternate to Normal D, R SF-6 Electrical 262002A4.01 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 / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
ES-301 Control Room/In-Plant Systems Outline -SRO-U DRAFT Form ES-301-2 Facility: PLANT E. I. HATCH HLT 6 Date of Examination: 06/06/2011 Exam Level: RO SRO-I SRO-U X Operating Test No.: 2011-301 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 CR/SIM 5 - RHR/LPCI: Containment Spray Mode
/ Initiate Torus Spray with failure A, L, N, S SF-5 Containment Integrity 226001A2.11 CR/SIM 6 - Transfer 4160V Station Service 2A to Normal (SAT)
D, S SF-6 Electrical 262001A4.04 CR/SIM 8 - Manually place MCREC in pressurization Mode after failure to auto with C012A not starting A, C, M, EN SF-9 Radiation Release 290003A4.01 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
PLANT 1 - Crosstie Reactor Bldg Plant Service Water A, D, E, L, R SF-8 Plant Service Systems 295018AA1.01 PLANT 2 - Insert a Scram using the RPS Breakers D, E SF-1 Reactivity 295006AA1.05 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 / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1