ML12103A367
| ML12103A367 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/29/2012 |
| From: | Bielby M Operations Branch III |
| To: | Exelon Generation Co |
| Shared Package | |
| ML11354A136 | List: |
| References | |
| Download: ML12103A367 (19) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Fermi-2 Date of Examination: 03/19/12 Examination Level: RO SRO Operating Test Number: 2012-1 Administrative Topic Type Describe activity to be performed (See Note) Code*
Conduct of Operations RD Perform Thermal Limit Verification (MAPRAT)
Conduct of Operations RD Perform Drywell Air Temperature Calculations Equipment Control SD HPCI System Piping Filled and Valve Position Verification Radiation Control RD Approve a Discharge Permit Emergency Plan SM Emergency Classification for Scenario1 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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, Page 22 of 27
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _________Fermi 2____________________ Date of Examination: 3/19/12 Exam Level: RO SRO-I X SRO-U Operating Test No.: 2012-1 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. Perform Rod Pattern Adjustment A, D, P, S SF-1
- b. Restore RWCU after isolation N, S SF-2
- c. Perform Main Steam Line Isolation Functional Test A, D, EN, P, S SF-3
- f. Restore 480V ESF Bus 72B to its Normal Power Source (Dead D, L, S SF-6 Bus Transfer)
- g. Manually Initiate Div 2 Emergency Equipment Cooling Water A, D, EN, S SF-8
- h. Respond to Refuel Floor High Radiation A, D, L, S SF-9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Place ESF Battery Charger in Service DR SF-6 j.MSL C Upscale Corrective Action D, R SF-9 k.Shutdown of plant from Relay Room D, E, R SF-7
@ 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 4-6 / 4-6 / 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 (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)
(R)CA 1/1/1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _________Fermi 2____________________ Date of Examination: 3/19/12 Exam Level: RO SRO-I SRO-U X Operating Test No.: 2012-1 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
- c. Perform Main Steam Line Isolation Functional Test A, D, EN, P, S SF-3
- f. Restore 480V ESF Bus 72B to its Normal Power Source (Dead D, L, S SF-6 Bus Transfer)
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) j.MSL C Upscale Corrective Action D, R SF-9 k.Shutdown of plant from Relay Room D, E, R SF-7
@ 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 4-6 / 4-6 / 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 (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)
(R)CA 1/1/1 (S)imulator
ES-301 Transient and Event Checklist Form ES-301-5 Facility: Fermi-2 Date of Exam: 3/19/2012 Operating Test Number: 2012-1 A E Scenarios P V P E 1 2 3 4 T M L N O I I T T N C CREW CREW CREW CREW A I A T POSITION POSITION POSITION POSITION N Y L M T P S A B S A B S A B S A B U E R T O R T O R T O R T O M(*)
O C P O C P O C P O C P R I U RO RX 1 1 1 1 0 SRO-I NOR 1,2 2 1 1 1 I/C 2,5,6 3457810 9 4 4 2 SRO-U MAJ 4,7,9 6 4 2 2 1 TS 2,3 2 0 2 2 RO RX 1 1 1 1 0 SRO-I NOR 1,2 2 1 1 1 I/C 2,8 458910 7 4 4 2 SRO-U MAJ 4,7,9 6 4 2 2 1 TS 3,4 2 0 2 2 RO RX 1 1 1 1 0 SRO-I NOR 1,2 2 1 1 1 I/C 2,8 458910 7 4 4 2 SRO-U MAJ 4,7,9 6 4 2 2 1 TS 3,4 2 0 2 2 RO RX 1 1 1 1 0 SRO-I NOR 1 1 1 I/C 2,5,6 3 4 4 2 SRO-U MAJ 4,7,9 3 2 2 1 TS 2,3 2 0 2 2 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs must serve in both the SRO and ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an instant SRO additionally serves in the BOP position, one (I/C) malfunction can be credited toward the two (IC) malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ES-301, Page 26 of 27
ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: Fermi 2 Date of Exam: 3/19/2012 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *
- 1. 1 3 3 4 4 3 3 20 4 3 7 Emergency &
Abnormal 2 1 1 1 N/A 2 1 N/A 1 7 2 1 3 Plant Evolutions Tier Totals 4 4 5 6 4 4 27 6 4 10 1 2 2 2 4 2 2 2 3 2 3 2 26 3 2 5 2.
Plant 2 2 1 2 1 1 1 0 2 0 1 1 12 0 2 1 3 Systems Tier Totals 4 3 4 5 3 3 2 5 2 4 3 38 5 3 8
- 3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 3 3 2 2 2 1 2 2 Note: 1. Ensure that at least two topics from every applicable K/A 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 K/A category shall not be less than two).
Note: 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.
Note: 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 Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
Note: 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.
Note: 5. Absent a plant-specific priority, only those K/As 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.
Note: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
Note: 7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A 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 K/As.
Note: 8. On the following pages, enter the K/A 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-only exams.
Note: 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401, Page 17 of 34
ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 295001 Partial or Complete Loss of Forced 0 1 Reactor SCRAM 3.4 1 Core Flow Circulation / 1 & 4 4 0
2 295003 Partial or Complete Loss of AC / 6 D.C. electrical distribution system 3.6 1 4
0 3 295004 Partial or Total Loss of DC Pwr / 6 Cause of partial or complete loss of D.C. power 3.2 1 1
- 01. Ability to use plant computers to evaluate system or component 4 295005 Main Turbine Generator Trip / 3 status.
3.9 1 19 0
5 295006 SCRAM / 1 Decay heat generation and removal. 3.7 1 1
0 6 295016 Control Room Abandonment / 7 Remote shutdown panel: Plant-Specific 4.4 1 1
0 7 295018 Partial or Total Loss of CCW / 8 Starting standby pump 3.3 1 4
0 8 295019 Partial or Total Loss of Inst. Air / 8 Instrument air compressor power supplies 3.0 1 3
0 9 295021 Loss of Shutdown Cooling / 4 RHR/shutdown cooling system flow 3.4 1 2
- 04. Ability to prioritize and interpret the significance of each 10 295023 Refueling Acc / 8 annunciator or alarm.
4.1 1 45 0
11 295024 High Drywell Pressure / 5 Drywell integrity: Plant-Specific 4.1 1 1
0 12 295025 High Reactor Pressure / 3 Reactor/turbine pressure regulating system: Plant-Specific 3.7 1 8
295026 Suppression Pool High Water 0 13 Reactor SCRAM 3.9 1 Temp. / 5 5 295027 High Containment Temperature / 5 0 0
14 295028 High Drywell Temperature / 5 Drywell pressure 3.9 1 4
0 15 295030 Low Suppression Pool Wtr Lvl / 5 Suppression pool temperature 3.9 1 2
04.
16 295031 Reactor Low Water Level / 2 Knowledge of EOP mitigation strategies. 3.7 1 06 295037 SCRAM Condition Present and 0
17 Reactor Power Above APRM Downscale or Boron effects on reactor power (SBLC) 4.2 1 3
Unknown / 1 0
18 295038 High Off-site Release Rate / 9 Control room ventilation 3.5 1 7
0 Actions contained in the abnormal procedure for plant fire on 19 600000 Plant Fire On Site / 8 site 2.8 1 4
700000 Generator Voltage and Electric Grid 0 20 Turbine/generator controls 3.8 1 Disturbances / 6 2 K/A Category Totals: 3 3 4 4 3 3 Group Point Total: 20
ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 0
21 295002 Loss of Main Condenser Vac / 3 PCIS/NSSSS 3.3 1 4
295007 High Reactor Pressure / 3 0 0
22 295008 High Reactor Water Level / 2 Swell 2.9 1 5
295009 Low Reactor Water Level / 2 0 295010 High Drywell Pressure / 5 0 295011 High Containment Temp / 5 0 0
23 295012 High Drywell Temperature / 5 Increased drywell cooling 3.5 1 1
295013 High Suppression Pool Temp. / 5 0 0
24 295014 Inadvertent Reactivity Addition / 1 Reactor power 3.9 1 7
0 25 295015 Incomplete SCRAM / 1 Reactor pressure: Plant-Specific 3.8 1 4
295017 High Off-site Release Rate / 9 0 Knowledge of RO tasks performed outside the main control 04.
26 295020 Inadvertent Cont. Isolation / 5 & 7 room during an emergency and the resultant operational 4.2 1 34 effects.
295022 Loss of CRD Pumps / 1 0 295029 High Suppression Pool Wtr Lvl / 5 0 295032 High Secondary Containment Area 0
Temperature / 5 295033 High Secondary Containment Area 0
Radiation Levels / 9 295034 Secondary Containment Ventilation 0
High Radiation / 9 295035 Secondary Containment High 0
Differential Pressure / 5 295036 Secondary Containment High 0 27 Affected systems so as to isolate damaged portions 3.5 1 Sump/Area Water Level / 5 2 500000 High CTMT Hydrogen Conc. / 5 0 K/A Category Totals: 1 1 1 2 1 1 Group Point Total: 7 ES-401, Page 19 of 34
ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 0 0 3.3; 28,29 203000 RHR/LPCI: Injection Mode Keep fill system; Valve closures 2 4 3 3.2 0
30 205000 Shutdown Cooling Motor operated valves 2.5 1 2
0 31 206000 HPCI Suppression pool level control: BWR-2, 3, 4 3.4 1 3
207000 Isolation (Emergency) 0 Condenser 0
32 209001 LPCS Pump minimum flow 2.6 1 5
209002 HPCS 0 0
33 211000 SLC Shutdown margin 3.2 1 3
0 34 212000 RPS Control rod drive hydraulic system 3.5 1 6
0 35 215003 IRM IRM channels/detectors 2.5 1 1
0 36 215004 Source Range Monitor RPS 3.4 1 1
0 37 215005 APRM / LPRM Flow biased trip setpoints 3.7 1 7
0 0 3.1; 38,39 217000 RCIC Flow indication; System flow 2 2 8 3.7 0 0 Prevent inadvertent initiatior of ADS logic; Primary 3.7; 40,41 218000 ADS containment instrumentation 2
1 7 3.4 223002 PCIS/Nuclear Steam Supply 0 42 Valve closures 3.7 1 Shutoff 2 0
43 239002 SRVs Leaky SRV 3.1 1 2
0 44 259002 Reactor Water Level Control Changes in reactor feedwater flow 3.2 1 4
0 0 45,46 261000 SGTS Charcoal bed decay heat removal; Fan 2.6; 3 2 2 3
- 04. Knowledge of how abnormal operating procedures are 47 262001 AC Electrical Distribution used in conjunction with EOPs.
3.8 1 08 0
48 262002 UPS (AC/DC) A.C. electrical power 2.7 1 1
0 49 263000 DC Electrical Distribution Battery charging/discharging rate 2.5 1 1
Loss of A.C. power; Knowledge of less than or equal to 0 02. 3.7; 50,51 264000 EDGs one hour Technical Specification action statements for 2 9 39 systems. 3.9 0
52 300000 Instrument Air Air temperature 2.9 1 2
0 53 400000 Component Cooling Water CCW indications and control 3.1 1 1
0 K/A Category Totals: 2 2 2 4 2 2 2 3 2 3 2 Group Point Total: 26 ES-401, Page 20 of 34
ES-401-1 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 0 201002 RMCS 0
- 01. Ability to locate and operate components, including local 54 201003 Control Rod and Drive Mechanism 4.4 1 30 controls.
201004 RSCS 0 201005 RCIS 0 201006 RWM 0 0
55 202001 Recirculation 7 Motor generator set trips: Plant-Specific 2.8 1 202002 Recirculation Flow Control 0 0
56 204000 RWCU 3 Reactor feedwater system 3.1 1 0
57 214000 RPIS 1 RWM: Plant-Specific 3.0 1 215001 Traversing In-core Probe 0 0
58 215002 RBM 6 Control rod selection: BWR-3, 4, 5 3.0 1 216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling Mode 0 223001 Primary CTMT and Aux. 0 226001 RHR/LPCI: CTMT Spray Mode 0 230000 RHR/LPCI: Torus/Pool Spray Mode 0 0
59 233000 Fuel Pool Cooling/Cleanup 4 Pool level 2.9 1 234000 Fuel Handling Equipment 0 0
60 239001 Main and Reheat Steam 4 Offgas system 2.8 1 239003 MSIV Leakage Control 0 241000 Reactor/Turbine Pressure Regulator 0 0
61 245000 Main Turbine Gen. / Aux. 7 Generator operations and limitations 2.6 1 0
62 256000 Reactor Condensate 1 System pumps 2.7 1 0
63 259001 Reactor Feedwater 7 Reactor water level control system malfunctions 3.7 1 268000 Radwaste 0 271000 Offgas 0 272000 Radiation Monitoring 0 0
64 286000 Fire Protection 1 A.C. electrical distribution: Plant-Specific 3.1 1 288000 Plant Ventilation 0 290001 Secondary CTMT 0 290003 Control Room HVAC 0 0
65 290002 Reactor Vessel Internals 3 Control rod drop accident 3.6 1 0
K/A Category Totals: 2 1 2 1 1 1 0 2 0 1 1 Group Point Total: 12 ES-401, Page 22 of 34
ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 295001 Partial or Complete Loss of Forced 0
Core Flow Circulation / 1 & 4 Ability to analyze the effect of maintenance activities, 02.
1 295003 Partial or Complete Loss of AC / 6 such as degraded power sources, on the status of 4.2 1 36 limiting conditions for operations.
295004 Partial or Total Loss of DC Pwr / 6 0 295005 Main Turbine Generator Trip / 3 0 295006 SCRAM / 1 0 Ability to evaluate plant performance and make
- 01. operational judgments based on operating 2 295016 Control Room Abandonment / 7 4.7 1 07 characteristics, reactor behavior, and instrument interpretation.
295018 Partial or Total Loss of CCW / 8 0 0
3 295019 Partial or Total Loss of Inst. Air / 8 Instrument air system pressure 3.6 1 1
0 4 295021 Loss of Shutdown Cooling / 4 Reactor water level 3.6 1 3
295023 Refueling Acc / 8 0 0
5 295024 High Drywell Pressure / 5 Suppression chamber pressure: Plant-Specific 3.9 1 4
295025 High Reactor Pressure / 3 0 295026 Suppression Pool High Water 0
Temp. / 5 295027 High Containment Temperature / 5 0 0
6 295028 High Drywell Temperature / 5 Drywell temperature 4.1 1 1
295030 Low Suppression Pool Wtr Lvl / 5 0 295031 Reactor Low Water Level / 2 0 295037 SCRAM Condition Present and Reactor Power Above APRM 0 Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 0
- 02. Ability to determine operability and/or availability of 7 600000 Plant Fire On Site / 8 4.6 1 37 safety related equipment.
700000 Generator Voltage and Electric Grid 0
Disturbances / 6 K/A Category Totals: 0 0 0 0 4 3 Group Point Total: 7
ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 0 295007 High Reactor Pressure / 3 0 295008 High Reactor Water Level / 2 0 0
8 295009 Low Reactor Water Level / 2 Steam flow/feedflow mismatch 3.7 1 2
295010 High Drywell Pressure / 5 0 295011 High Containment Temp / 5 0 295012 High Drywell Temperature / 5 0 295013 High Suppression Pool Temp. / 5 0 295014 Inadvertent Reactivity Addition / 1 0 295015 Incomplete SCRAM / 1 0 295017 High Off-site Release Rate / 9 0 295020 Inadvertent Cont. Isolation / 5 & 7 0 0
9 295022 Loss of CRD Pumps / 1 CRD system status 3.4 1 2
295029 High Suppression Pool Wtr Lvl / 5 0 Knowledge of the parameters and logic used to assess the 295032 High Secondary Containment Area 04. status of safety functions, such as reactivity control, core 10 cooling and heat removal, reactor coolant system integrity, 4.6 1 Temperature / 5 21 containment conditions, radioactivity release control, etc.
295033 High Secondary Containment Area 0
Radiation Levels / 9 295034 Secondary Containment Ventilation 0
High Radiation / 9 295035 Secondary Containment High 0
Differential Pressure / 5 295036 Secondary Containment High 0
Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 0 K/A Category Totals: 0 0 0 0 2 1 Group Point Total: 3 ES-401, Page 19 of 34
ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (SRO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection 0 205000 Shutdown Cooling Mode 0 206000 HPCI 0 207000 Isolation (Emergency) 0 Condenser 0
11 209001 LPCS D.C. failures 3.0 1 4
209002 HPCS 0 211000 SLC 0 212000 RPS 0 0
12 215003 IRM Up scale or down scale trips 3.8 1 4
01.
13 215004 Source Range Monitor Ability to interpret and execute procedure steps. 4.6 1 20 0
14 215005 APRM / LPRM Loss of recirculation flow signal 3.6 1 5
217000 RCIC 0 218000 ADS 0 223002 PCIS/Nuclear Steam Supply 0
Shutoff 239002 SRVs 0 259002 Reactor Water Level Control 0 261000 SGTS 0
- 04. Knowledge of the bases for prioritizing safety functions 15 262001 AC Electrical Distribution during abnormal/emergency operations.
4.4 1 22 262002 UPS (AC/DC) 0 263000 DC Electrical Distribution 0 264000 EDGs 0 300000 Instrument Air 0 400000 Component Cooling Water 0 0
K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401, Page 20 of 34
ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 0 0
16 201002 RMCS 2 Rod drift alarm 3.3 1 201003 Control Rod and Drive Mechanism 0 201004 RSCS 0 201005 RCIS 0 201006 RWM 0 202001 Recirculation 0 202002 Recirculation Flow Control 0 204000 RWCU 0 214000 RPIS 0 215001 Traversing In-core Probe 0 215002 RBM 0 Ability to interpret control room indications to verify the status 02.
17 216000 Nuclear Boiler Inst. and operation of a system, and understand how operator 4.4 1 44 actions and directives affect plant and system conditions.
219000 RHR/LPCI: Torus/Pool Cooling Mode 0 223001 Primary CTMT and Aux. 0 226001 RHR/LPCI: CTMT Spray Mode 0 0
18 230000 RHR/LPCI: Torus/Pool Spray Mode 3 Valve closures 3.2 1 233000 Fuel Pool Cooling/Cleanup 0 234000 Fuel Handling Equipment 0 239001 Main and Reheat Steam 0 239003 MSIV Leakage Control 0 241000 Reactor/Turbine Pressure Regulator 0 245000 Main Turbine Gen. / Aux. 0 256000 Reactor Condensate 0 259001 Reactor Feedwater 0 268000 Radwaste 0 271000 Offgas 0 272000 Radiation Monitoring 0 286000 Fire Protection 0 288000 Plant Ventilation 0 290001 Secondary CTMT 0 290003 Control Room HVAC 0 290002 Reactor Vessel Internals 0 0
K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 ES-401, Page 21 of 34
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:Fermi 2 Date of Exam:3/19/2012 RO SRO-Only Category K/A # Topic Q# IR # IR #
Ability to locate control room switches, controls, and indications, and to determine that 66 2.1. 31 they correctly reflect the desired plant lineup. 4.6 1 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high 67 2.1. 26 temperature, high pressure, caustic, chlorine, oxygen and hydrogen). 3.4 1
- 1. 2.1.
Conduct of 68 2.1. 08 Ability to coordinate personnel activities outside the control room. 3.4 1 Operations Knowledge of administrative requirements for temporary management directives, such as 19 2.1. 15 standing orders, night orders, operations memos, etc. 3.4 1 20 2.1. 42 Knowledge of new and spent fuel movement procedures. 3.4 1 Subtotal 3 2 Ability to perform pre-startup procedures for the facility, including operating those controls 69 2.2. 01 associated with plant equipment that could affect reactivity. 4.5 1 70 2.2. 14 Knowledge of the process for controlling equipment configuration or status. 3.9 1 71
- 2. 2.2. 22 Knowledge of limiting conditions for operations and safety limits. 4.0 1 Equipment 21 2.2. 40 Ability to apply Technical Specifications for a system. 4.7 1 Control 2.2.
2.2.
Subtotal 3 1 Knowledge of radiological safety principles pertaining to licensed operator duties, such as 72 2.3. 12 containment entry requirements, fuel handling responsibilities, access to locked high- 3.2 1 radiation areas, aligning filters, etc.
22 2.3. 06 Ability to approve release permits. 3.8 1 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 73
- 3. 2.3. 15 portable survey instruments, personnel monitoring equipment, etc. 2.9 1 Radiation 23 2.3. 11 Ability to control radiation releases. 4.3 1 Control 2.3.
2.3.
Subtotal 2 2 Ability to take actions called for in the facility emergency plan, including supporting or 24 2.4. 38 acting as emergency coordinator if required. 4.4 1 74 2.4. 43 Knowledge of emergency communications systems and techniques. 3.2 1 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the 75 4. 2.4. 47 appropriate control room reference material. 4.2 1 Emergency Ability to recognize abnormal indications for system operating parameters that are entry-25 Procedures 2.4. 04 level conditions for emergency and abnormal operating procedures. 4.7 1
/ Plan 2.4.
2.4.
Subtotal 2 2 Tier 3 Point Total 10 7 ES-401, Page 27 of 34
Appendix D Scenario Outline Form ES-D-1 Facility: Fermi 2 Scenario No. 1 Op-Test No: 2012-1 Examiners: Operators:
Initial Conditions: IC-20, MOC, 100% Rx. Power Turnover: The plant has been operating for 230 days. Reactor Power is currently 100% of Rated Thermal Power with Control Rods at the 107% Rod Line. Circulating Water Pump #5 is out of service for motor replacement with an expected return to service in 2 days. The shift will lower Reactor Power to <93% with Recirculation flow, to perform Surveillance Procedure 24.109.02 (Rev32) Turbine Bypass Valve Operability Test.
NOTE: The crews Pre-job Briefing for the reactor power decrease is to be conducted prior to entering the simulator. (Suggested time 30 minutes prior to beginning the scenario.)
Even Malf. No. Event Event t No. Type* Description
- 1. N/A R (ATC) Decrease reactor power with recirculation flow to 93%.
R (SRO)
- 2. B31MF0015 C (ATC) RRMG "A" Walkaway >10% speed. ATC trips the C (SRO) RRMG, and CRS enters TS 3.4.1.A.
- 3. E51MF0009 C(BOP) RCIC Spurious Initiation CRS enters TS 3.5.3.A
- 4. R14MF0001 M(All) Loss of Div 2 Offsite Power / EDGs start / Loss of all Heater Feed Pumps, Reactor Feed Pumps, and Scram N20MF0023
- 5. E41MF0009 C(BOP) HPCI Auto Start Failure / Isolation E41MF0005 C(SRO) The crew will manually start HPCI to restore RPV Level.
HPCI later isolates.
- 6. N21MF0031 C(BOP) SBFW F001 Fails As Is / Loss of power N21RF0019 C(SRO) BOP starts SBFW Pump A and identifies the injection valve failure. (Restored when overloads reset.)
- 7. B31MF0067 M(All) Recirc Loop B Rupture (LOCA)
Multiple EOP entries and re-entry
I (SRO)
ATC determines EECW is not isolated, and isolates.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, 38 of 39
Appendix D Scenario Outline Form ES-D-1 Facility: Fermi 2 Scenario No. 1 Op-Test No: 2012-1 Examiners: Operators:
Initial Conditions: IC-20, MOC, 100% Rx. Power.
NOTE: Continued from page 1 Event Malf. No. Event Event No. Type* Description
Crew restores water level 173 - 214 with available High Pressure and Low Pressure ECCS Systems. (CT)
Crew sprays the Drywell using SOP 23.205, RHR System, Encl A. (Hard Card) (CT)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, 38 of 39
Appendix D Scenario Outline Form ES-D-1 Facility: Fermi 2 Scenario No. 2 Op-Test No: 2012 Examiners: Operators:
Initial Conditions: IC- 14 Turnover: Reactor Startup is in progress with power at 23%. The Main Turbine generator is synchronized to the grid at 175 MW. After shift turnover, the crew will continue startup using GOP 22.000.02. First step to be completed is step 7.2.2.22, transferring from Startup Level Controller to Single Element control NOTE: The Pre-job Briefing on transferring to single element control using 23.107 is to be conducted by the crew prior to entering the simulator. (suggested time 30 minutes prior to the beginning of the scenario)
Event Malf. No. Event Event No. Type* Description
- 1. N/A N (All) Place Feed Water Control SULCV to single element.
- 2. N/A N (All) Swap of the running RRMG LO Pump due to loud noise
- 3. E41RF0008 I (All) CST Level Low Instrument Failure, Evaluates TS 3.3.5.1 ECCS Instrumentation and TS 3.3.5.2 RCIC System Instrumentation.
- 4. N30MF0044 C (All) Trip of Main Turbine Generator, TS 3.7.6 Main Turbine Bypass System and MSR.
NH01N3031
- 5. N21MF0029 C (All) Loss of North Reactor Feed Pump
Crew Inserts Control Rods (CT)
- 10. B21MF0023 C (All) SRV A fails open.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 1021, Draft Revision 9 40 of 41