ML13057A073

2013 Monticello Nuclear Generating Plant Initial License Examination Forms ES-401-1 and ES-401-3

ML13057A073
Person / Time
Site:	Monticello
Issue date:	01/29/2013
From:	Mcneil D NRC/RGN-III/DRS/OLB
To:
References
Download: ML13057A073 (8)

Text

ES-401 BWR Examination Outline Form ES-401-1 Facility: MNGP Date of Exam: 1/28/2013 RO K/A 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 3 3 4 4 3 20 5 2 7 Emergency &

Abnormal Plant 2 2 1 1 N/A 1 1 N/A 1 7 2 1 3 Evolutions Tier Totals 5 4 4 5 5 4 27 7 3 10 1 3 2 3 3 2 3 2 2 2 2 2 26 3 2 5 2.

Plant 2 2 0 1 1 1 2 1 1 1 1 1 12 n/ 2 1 3 Systems a Tier Totals 5 2 4 4 3 5 3 3 3 3 3 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 2 2 1 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).

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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A 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 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.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

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.

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.

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 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR  ?#

1 2 3 1 2 295001 Partial or Complete Loss of Forced R 2.1.25 Ability to interpret reference materials, such 3. 1 Core Flow Circulation / 1 & 4 as graphs, curves, tables, etc. 9 295003 Partial or Complete Loss of AC / 6 R AK1.06 Station Blackout 3. 2 8

295004 Partial or Total Loss of DC Pwr / 6 R S K2.01 Battery charger 3. 3 1/

A2.02 Extent of partial or complete loss of D.C. 3. 76 power 9 295005 Main Turbine Generator Trip / 3 R S K3.07 Bypass valve operation 3. 4 8/

A2.08 Electrical distribution status 77 3.

3 295006 SCRAM / 1 R A1.02 Reactor water level control system 3. 5 9

295016 Control Room Abandonment / 7 R A2.02 Reactor water level 4. 6 2

295018 Partial or Total Loss of CCW / 8 R A1.01 Backup systems 3. 7 3

295019 Partial or Total Loss of Inst. Air / 8 R S A2.02 Status of safety-related instrument air system 3. 8 loads 6/

78 2.1.20 Ability to interpret and execute procedure 4.

steps 6 295021 Loss of Shutdown Cooling / 4 S R A2.04 Reactor water temperature 3. 79 6/

2.2.36 Ability to analyze the effects of maintenance 3. 9 activities, such as degraded power sources, on the 1 status of limiting conditions for operations.

295023 Refueling Acc / 8 R K1.03 Inadvertent criticality 3. 10 7

295024 High Drywell Pressure / 5 R K2.10 A.C. distribution 3. 11 5

295025 High Reactor Pressure / 3 R K3.03 HPCI operation 3. 12 8

295026 Suppression Pool High Water R S A1.03 Temperature monitoring 3. 13 Temp. / 5 9/

A2.03 Reactor pressure 80 4.

0 295027 High Containment Temperature / 5 N/A MNGP 295028 High Drywell Temperature / 5 R A2.03 Reactor water level 3. 14 7

295030 Low Suppression Pool Wtr Lvl / 5 R 2.2.44 Ability to interpret control room indications to 4. 15 verify the status and operation of a system, and 2 understand how operator actions and directives affect plant and system conditions.

295031 Reactor Low Water Level / 2 R K1.01 Adequate core cooling 4. 16 6

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR  ?#

1 2 3 1 2 295037 SCRAM Condition Present R S K2.09 Reactor water level 4. 17 and Reactor Power Above APRM 0/

Downscale or Unknown / 1 2.4.8 Knowledge of how abnormal operating 81 procedures are used in conjunction with EOPs 4.

5 295038 High Off-site Release Rate / 9 R K3.03 Control room ventilation isolation 3. 18 7

600000 Plant Fire On Site / 8 R S A1.05 Plant and control room ventilation systems 3. 19 0/

A2.16 Vital equipment and control systems to be 82 maintained and operated during a fire. 3.

6 700000 Generator Voltage and Electric Grid R A2.07 Operational status of engineered safety 3. 20 Disturbances / 6 features 6 K/A Category Totals: 3 3 3 4 4 3 Group Point Total: 20/

/ /

5 2 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 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR  ?#

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 R K1.03 Loss of heat sink 3. 21 6

295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 N/A MNGP 295012 High Drywell Temperature / 5 S 2.1.25 Ability to interpret reference materials, such as 4. 83 graphs, curves, tables etc. 2 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 R K3.05 Reactor water level response 3. 22 8

295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment R K1.04 Impact of operating environment on components 3. 23 Area Temperature / 5 1 295033 High Secondary Containment R K2.04 Standby gas treatment system 3. 24 Area Radiation Levels / 9 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High R S A1.01 Secondary containment ventilation system 3. 25 Differential Pressure / 5 6/

A2.02 Off-site release rate 84 4.

1 295036 Secondary Containment High R A2.01 Operability of components within the affected 3. 26 Sump/Area Water Level / 5 area. 0 500000 High CTMT Hydrogen Conc. / 5 S R A2.01 Hydrogen monitoring system availability 3. 85 6/

2.1.30 Ability to locate and operate components, 4. 27 including local controls 4 K/A Category Point Totals: 2 1 1 1 1 1 Group Point Total: 7 2 1 3

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 System # / Name K K K K K K A A A A G K/A Topic(s) IR  ?#

1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection R R K4.04 Pump motor cooling 2. 28 Mode 6 K5.02 Core cooling methods 29 3.

5 205000 Shutdown Cooling R K6.04 Reactor water level 3. 30 6

206000 HPCI R A1.05 Suppression pool temperature 4. 31 1

207000 Isolation (Emergency) N/A MNGP Condenser 209001 LPCS R A2.03 A.C failures 3. 32 S 4/

A2.08 Valve openings 3. 86 1

209002 HPCS N/A MNGP 211000 SLC R A3.06 RWCU system isolation 4. 33 0

212000 RPS R A4.05 Reactor power 4. 34 3

215003 IRM R 2.2.38 Knowledge of conditions and 3. 35 limitations in the facility license. 6 215004 Source Range Monitor R K1.02 Reactor manual control 3. 36 4

215005 APRM / LPRM R S K2.02 APRM channels 2. 37 6/

2.2.22 Knowledge of limiting conditions for 4. 87 operations and safety limits 7 217000 RCIC R K3.01 Reactor water level 3. 38 7

218000 ADS R S K4.01 Prevent inadvertent initiator of ADS 3. 39 logic 7/

4. 88 A2.06 ADS initiation signals present 3 223002 PCIS/Nuclear Steam R K6.04 Nuclear boiler instrumentation 3. 40 Supply Shutoff 3 239002 SRVs R S K6.02 Air (Nitrogen) supply 3. 41 4/

2.4.30 Knowledge of events related to system 4. 89 operations/status that must be reported to 1 internal organizations or external agencies, such as State, the NRC, or the transmission system operator.

259002 Reactor Water Level R A1.01 Reactor water level 3. 42 Control 8 261000 SGTS R A2.01 Low system flow 2. 43 9

262001 AC Electrical R A3.02 Automatic bus transfer 3. 44 Distribution 2

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 System # / Name K K K K K K A A A A G K/A Topic(s) IR  ?#

1 2 3 4 5 6 1 2 3 4 262002 UPS (AC/DC) S R A2.01 UndervoltageA4.01 Transfer from 2. 45 alternative source to preferred source 8/

2. 90 8

263000 DC Electrical x R K1.03 Battery ventilation 2. 46 Distribution 6 2.1.28 Knowledge of the purpose and function 47 of major system components and controls 4.

1 264000 EDGs R R K1.03 Fire protection system 2. 48 9

K5.06 Load sequencing 49 3.

4 300000 Instrument Air R R K2.01 Instrument air compressor 2. 50 8

K3.02 Systems having pneumatic valves and 51 controls 3.

3 400000 Component Cooling R R K3.01 Loads cooled by CCWS 2. 52 Water 9 K4.01 Automatic start of standby pump 53 3.

4 K/A Category Point Totals: 3 2 3 3 2 3 2 2 2 2 2 Group Point Total: 26 3 2 5

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR  ?#

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive R K1.02 Reactor water 2.9 54 Mechanism 201004 RSCS N/A MNGP 201005 RCIS N/A MNGP 201006 RWM R K3.01 Reactor manual control system 3.2 55 202001 Recirculation S A2.06 Inadvertent recirculation flow decrease 3.8 91 202002 Recirculation Flow Control R K4.03 Signal failure detection 3.0 56 204000 RWCU 214000 RPIS R K5.01 Reed switches 2.7 57 215001 Traversing In-core Probe R K6.04 PCIS 3.1 58 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode S 2.2.36 Ability to analyze the effect of 4.2 92 maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

230000 RHR/LPCI: Torus/Pool Spray R K6.08 Nuclear boiler instrumentation 2.9 59 Mode 233000 Fuel Pool Cooling/Cleanup R A1.07 System temperature 2.7 60 234000 Fuel Handling Equipment 239001 Main and Reheat Steam S A2.13 High reactor water level 3.7 93 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate 259001 Reactor Feedwater R A2.06 Loss of AC electrical power 3.2 61 268000 Radwaste 271000 Offgas R A3.07 Process radiation monitoring system 3.4 62 indications 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation R A4.02 Area temperature 2.8 63 290001 Secondary CTMT 290003 Control Room HVAC R 2.4.41 Knowledge of the emergency action 2.9 64 level thresholds and classifications.

290002 Reactor Vessel Internals R K1.20 Nuclear instrumentation 3.2 65 K/A Category Point Totals: 2 0 1 1 1 2 1 1 1 1 1 Group Point Total: 12 2 1 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: MNGP Date of Exam: 1/28/2013 Category K/A # Topic RO SRO-Only IR  ?# IR #

2.1.14 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode 3.1 66 changes, etc.

2.1.19 Ability to use plant computers to evaluate system or 3.8 95 component status 1.

Conduct 2.1.30 Ability to locate and operate components, including local 4.4 67 of Operations controls 2.1.32 Ability to explain and apply system limits and precautions 3.8 68 2.1.34 Knowledge of primary and secondary plant chemistry 3.5 94 limits Subtotal 3 2 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated 4.6 69 power levels.

2.2.12 Knowledge of surveillance procedures 4.1 96 2.

2.2.22 Knowledge of limiting conditions for operations and safety Equipment 4.0 70 limits.

Control 2.2.38 Knowledge of conditions and limitations in the facility 3.6 71 license.

2.2.43 Knowledge of the process used to track inoperable alarms 3.3 97 Subtotal 3 2 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 72 emergency situations.

2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation

3. monitor alarms, containment entry requirements, fuel 3.8 98 Radiation handling responsibilities, access to locked high radiation Control areas, aligning filters, etc.

2.3.15 Knowledge or radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey 2.9 73 instruments, personnel monitoring equipment, etc.

Subtotal 2 1 2.4.27 Knowledge of fire in the plant procedures 3.4 74 2.4.34 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant 4.2 75

4. operational effects.

Emergency Procedures / 2.4.44 Knowledge of emergency plan protective action 4.4 99 Plan recommendations 2.4.46 Ability to verify that the alarms are consistent with the 4.2 100 plant conditions Subtotal 2 2 Tier 3 Point Total 10 7