ML102520107

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Examination Outline
ML102520107
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 08/16/2010
From: Widmann M
Division of Reactor Safety II
To: Krich R
Tennessee Valley Authority
References
50-259/10-301, 50-260/10-301, 50-296/10-301, ES-401-1 50-259/10-301, 50-260/10-301, 50-296/10-301
Download: ML102520107 (29)
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Text

ES-401 1 Rev. 9 BWR Examination Outline Form ES-401-1 Facility: r*, \( i .:"-1:

/' f Date of Exam: ~l c> ,)

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 4 3 3 20 3 4 7 Emergency & 1 1 1 2 1 1 7 1 2 3 2

Abnormal Plant N/A N/A Evolutions TIer Totals 5 4 4 6 4 4 27 4 6 10 1 3 2 2 3 1 2 3 2 3 3 2 26 2 3 5

2. 1 1 1 1 1 1 1 1 2 1 1 12 0 1 2 3 2

Plant Systems Tier Totals 4 3 3 4 2 3 4 3 5 4 3 38 3 5 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 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 (Le., 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 j

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 KlAs 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.
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 (Note
  1. 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. ForTIer 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 T1G1 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 295001G2.1.7 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 4.4 4.7 0 0 0 0 0 0 0 q 0 ~ Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

295003G2.1.27 Partial or Complete Loss of AC / 6 3.9 4 OOOOOOOODO~ Knowledge of system purpose and or function.

295004AA 1.03 Partial or Total Loss of DC Pwr / 6 3.4 3.6 0 0 0 0 0 0 ~ 0 0 0 0 . A.C. electrical distribution ......................... .

295005AA2.08 Main Turbine Generator Trip / 3 3.2 3.3 0 0 0 O~OOO Electrical distribution status ....................... .

295006AK3.03 SCRAM / 1 3.8 3.9 0 0 ~ 0 000000 Reactor pressure response ............................ .

295016AA 1.08 Control Room Abandonment / 7 4.0 4.0 0 0 0 0 0 ~ 0 o Reactor pressure ..................................... .

295018AK3.07 Partial or Total Loss of CCW / 8 3.1 3.2 0 0 ~ 0 0 0 0 0 0 0 0 Cross-connecting with backup systems ................. .

295019AA2.02 Partial or Total Loss of Inst. Air / 8 3.6 3.7 0 0 0 0 0 0 0 ~ 0 0 0 Status of safety-related instrument air system loads AK2.1 - AK2.19) ................................. .

295021AK2.01 Loss of Shutdown Cooling / 4 3.6 3.7 0 ~ 0 0 0 0 0 000 Reactor water temperature ............................ .

295023AA 1.05 Refueling Acc Cooling Mode / 8 2.8 3.5 0 0 0 0 0 0 ~ 000 Fuel transfer system: Plant-Specific ................ .

.01 High Drywell Pressure / 5 4.1 4.2 ~ 0 0 0 0 0 0 000 Drywell integrity: Plant-Specific ................... .

Page 1 of 2 8127/2009 2:26 PM

ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:

RO SRO 295025EK3.01 High Reactor Pressure / 3 4.2 4.3 0 0 ~ 0 0 0 0 0 0 0 0 Safety/relief valve opening .......................... .

295026EA2.01 Suppression Pool High Water Temp. / 4.1 4.2 0 0 0 ooo~ DO Suppression pool water temperature ................... .

5 High Drywell Temperature / 5 3.7 4.1 0 ~ 00000000 Drywell spray: Mark-I&II... ......................... .

Low Suppression Pool Wtr Lvi / 5 3.5 3.8 ~ 0 0 0 0 0 0 0 0 o Pump NPSH ............................................ .

295031 EK1.02 Reactor Low Water Level / 2 3.8 4.1 ~ 0 0 0 0 0 0 0 0 0 0 Natural circulation: Plant-Specific ................. .

295037EK2.13 SCRAM Condition Present and Power 3.4 4.1 0 ~ 0 0 0 0 0 0 0 0 0 Alternate boron injection methods: Plant-Specific ....

Above APRM Downscale or Unknown

/1 295038G2.4.9 High Off-site Release Rate / 9 3.8 4.2 0 0 0 0 0 0 0 0 O~ Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

600000AK1.02 Plant Fire On Site / 8 2.9 3.1 ~ 0 0 0 0 0 0 0 0 0 0 Fire Fighting 700000AA1.03 Generator Voltage and Electric Grid 3.8 3.7 0 0 ODD 0 ~ 0 ODD Voltatge regulator controls Distrurbancecs Page 2 of 2 8/27/2009 2:26 PM

ES-401, REV 9 T1G2 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 295002AK2.02 Loss of Main Condenser Vac 1 3 3.1 3.2 D ~ D D 0 0 0 D 0 0 D Main turbine ......................................... ,

295009AK1.05 Low Reactor Water Levell 2 3.3 3.4 ~ 0 0 0 0 D 0 0 0 0 0 Natural circulation .................................. .

295010AA1.06 High Drywell Pressure 1 5 3.3 3.5 0 0 0 D 0 0 ~ 0 0 0 Leakage detection systems ............................ .

295022G2.2.38 Loss of CRD Pumps 1 1 3.6 4.5 0 0 0 0 0 D 0 0 0 0 ~ Knowledge of conditions and limitations in the facility license.

295029EK3.03 High Suppression Pool Wtr Lvi 1 5 3.4 3.5 0 0 ~ 0 D 0 0 0 0 0 0 Reactor SCRAM ........................................ .

295034EA 1.02 Secondary Containment Ventilation High Radiation 1 9 3.9 4.0 0 0 D D 0 0 ~ 0 DO Process radiation monitoring system .................. .

295036EA2.01 Secondary Containment 3.0 3.2 0 D 0 0 D 0 0 ~ 0 0 0 Operability of components within the affected area ..

Sump/Area Water Levell Page 1 of 1 8/27/2009 2:26 PM

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 203000A1.01 RHRlLPCI: Injection Mode 4.2 4.3 0 0 ooo~oooo Reactor water level RHRlLPCI: Injection Mode 3.6 3.6 0 ooo~oooo System pressure 205000K3.05 Shutdown Cooling 2.6 2.7 0 0 ~ 0 0 ODD 0 0 0 Fuel pool cooling assist: Plant-Specific 206000K2.02 HPCI 2.8 3.1 0 Ii'] 0 0 0 0 0 0 0 o System pumps: BWR-2,3,4 209001K1.08 LPCS 3.2 3.3 ~ 0 0 0 0 0 0 000 electrical power 211000A3.01 SLC 3.5 3.5 0 0 0 0 0 0 0 0 ~ 0 0 Pump discharge pressure: Plant-Specific 212000A2.09 RPS 4.1 4.3 0 0 0 0 0 0 0 ~ DO High containment/drywell pressure 215003A4.04 IRM 3.1 3.3 0 0 0 0 0 0 0 0 0 ~ 0 ?IRM back panel switches, meters, and indicating lights 215003A4.05 IRM 3.4 3.4 0 0 0 0 0 0 0 0 0 ~ 0 Trip bypasses 215004G2.2.4 Source Range Monitor 3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~ (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

215005K4.01 APRM 1 LPRM 3.7 3.7 ODD ~ DOD Rod withdrawal blocks Page 1 of 3 812712009 2:26 PM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 217000K6.04 RCIC 3.5 3.5 0 0 0 0 0 ~ 0 0 0 0 0 Condensate storage and transfer system 218000K4.02 ADS 3.8 4.0 0 0 0 ~ 0 0 0 0 00 Allows manual initiation of ADS logic 218000K4.03 ADS 3.8 4.0 0 0 ~ 0 0 0 0 0 0 ADS logic control 223002K1.04 PC IS/Nuclear Steam Supply Shutoff 3.5 3.8 ~ 0 0 0 0 0 0 0 0 0 0 High pressure coolant injection:

223002K1.08 PCIS/Nuclear Steam Supply Shutoff 3.4 3.5 ~ 0 0 0 0 0 0 0 00 Shutdown cooling system/RHR 239002K2.01 SRVs 2.8 3.2 0 ~ 0 0 0 0 0 0 0 0 0 SRV solenoids 259002G2.2.40 Reactor Water Level Control 3.4 4.7 0 0 0 0 0 oooo~ Ability to apply technical specifications for a system.

SGTS 2.9 3.1 0 0 0 0 0 0 ~ 0 0 0 0 System flow 262001 K5.02 AC Electrical 2.6 2.9 0 0 0 0 ~ 0 0 0 0 0 0 Breaker control 262002K3.08 UPS (AC/DC) 2.7 2.8 0 0 ~ 0 000 0 000 Computer operation: Plant-Specific 263000A2.02 DC Electrical Distribution 2.6 2.9 Loss of ventilation during charging Page 2 of 3 8/27/2009 2:26 PM

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 264000A3.02 EOGs 3.1 3.1 0 0 0 0 0 0 0 0 ~ 0 0 Minimum time for load pick up 264000A3.04 EOGs 3.1 3.1 0 0 0 oooo~oo Operation of the governor control system on frequency and voltage control Instrument Air 2.6 2.7 0 0 0000 o~o Pressure gauges 4OOOOOK6.05 Component Cooling Water 3.0 3.1 0 0 0 0 0 ~ 0 0 0 0 0 Pumps Page 3 of 3 8/27/2009 2:26 PM

ES-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 201002A2.04 RMCS 3.2 3.1 0 0 0 0 0 0 0 ~ 0 0 0 Control rod block 215002A3.04 RBM 3.6 3.5 0 0 ooooo~oo Verification or proper functioning/ operability: BWR-3,4,5 216000A1.02 Nuclear Boiler Inst. 2.9 3.1 0 0 0 0 0 0 ~ 0 0 0 0 Removing or returning a sensor (transmitter) to service 230000A4.04 RHA/LPCI: Torus/Pool Spray Mode 3.1 2.9 0 0 0 0 0 0 0 0 0 ~ 0 Minimum flow valves Fuel Pool Cooling/Cleanup 2.8 2.9 0 ~ 0 0 0 0 0 0 0 0 0 RHRpumps 234000K5.02 Fuel Handling Equipment 3.1 3.7 000 0 ~ 0 0 0 00 Fuel handling equipment interlocks 241000K6.06 ReactorlTurbine Pressure Regulator 3.8 3.9 0 0 0 0 0 ~ 0 0 0 0 0 Reactor pressure 268000K3.04 2.7 2.8 0 0 ~ 0 0 0 0 0 0 0 0 Drain sumps 272000A3.01 Radiation Monitoring 3.8 3.9 0 0 0 0 0 0 0 0 ~ 0 0 Main steam isolation indications 286000G2.2.42 Fire Protection 3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to recognize system parameters that are entry-level conditions for Technical Specifications 290002K1.12 Reactor Vessel Internals 3.4 3.5 ~ 0 0 0 0 0 0 0 0 0 0 SBLC Page 1 of 2 8127/2009 2:26 PM

ES-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 290003K4.01 Control Room HVAC 3.1 3.2 0 0 ~DDDDDDD System initiationsireconfiguration: Plant-Specific Page 2 of 2 8/27/2009 2:26 PM

ES-401, REV 9 T3 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 G2.1.25 Conduct of operations 3.9 4.2 0 0 0 0 0 0 0 0 0 0 ~ Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

G2.1.27 Conduct of operations 4 3.9 000 oooooo~ Knowledge of system purpose and or function.

G2.1.8 Conduct of operations 3.4 4.1 0 oooooooo~ Ability to coordinate personnel activities outside the control room.

G2.2.20 Equipment Control 2.6 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the process for managing troubleshooting activities.

Equipment Control 4.0 4.7 0 0 0 0 0 0 0 0 O~ Knowledge of limiting conditions for operations and safety limits.

Equipment Control 3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~ (mUlti-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a faCility.

G2.3.14 Radiation Control 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.5 Radiation Control 2.9 2.9 0 0 0 0 0 0 0 0 0 0 ~ Ability to use radiation monitoring systems G2.4.20 Emergency Procedures/Plans 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of operational implications of EOP warnings, cautions and notes.

G2.4.45 Emergency Procedures/Plans 4.1 4.3 0 0 0 0 0 0 0 0 O~ Ability to prioritize and interpret the significance of each annunciator or alarm.

Page 1 of 1 8/27/2009 2:26 PM

ES-401, REV 9 SRO T1G1 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 295004AA2.01 Partial or Total Loss of DC Pwr / 6 3.2 3.6 0 0 0 0 0 0 0 ~ 0 0 0 Cause of partial or complete loss of D.C. power...... .

295016AA2.05 Control Room Abandonment / 7 3.8 3.9 0 0 0 0 0 0 0 ~ DO Drywell pressure ..................................... .

295018G2.1.27 Partial or Total Loss of CCW / 8 3.9 4 00000 oooo~ Knowledge of system purpose and or function.

295021G2.4.47 Loss of Shutdown Cooling / 4 4.2 4.2 0 0 0 0 0 0 0 0 0 0 ~ Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

295023G2.1.7 Refueling Acc Cooling Mode / 8 4.4 4.7 0 0 0 0 0 0 0 0 0 0 ~ Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

295024G2.1.31 High Drywell 5 4.6 4.3 0 0 ooooooo~ Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

295028EA2.06 High Drywell Temperature / 5 3.4 3.7 0 ooooo~ooo Torus/suppression chamber air space temperature: Plant-Specific ....................................... .

Page 1 of 1 8/27/2009 2:26 PM

ES-401, REV 9 SRO T1G2 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 295010G2.2.4 High Drywe/l Pressure 1 5 3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~ (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

295014AA2.01 Inadvertent Reactivity Addition 1 1 4.1 4.2 0 0 0 DDD~DDD Reactor power ........................................ .

295033G2.2.39 High Secondary Containment Area 3.9 4.5 0 0 0 0 0 0 0 0 0 ~ Knowledge of less than one hour technical specification Radiation Levels 1 9 action statements for systems.

Page 1 of 1 8/27/2009 2:26 PM

ES-401, REV 9 SRO 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:

AO SAO 203000A2.09 AHA/LPCI: Injection Mode 3.3 3.4 0 0 0 0 0 0 ~ 0 0 0 Inadequate system flow 211 OOOG2.1 .7 SLC 4.4 4.7 0 0 0 0 0 0 0 0 0 ~ Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

261000G2.2.4 SGTS 3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~ (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

263000G2.1.28 DC Electrical Distribution 4.1 4.1 0 0 0 0 0 0 0 0 0 ~ Knowledge of the purpose and of major system components and controls.

400000A2.02 Component Cooling Water 2.8 3.0 0 0 0 0 0 0 0 ~ 0 0 0 High/low surge tank level Page 1 of 1 8/27/2009 2:26 PM

ES-401, REV 9 SRO 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 215001G2.4.2 Traversing In-core Probe 4.5 4.6 D D D D D D D D D D ~ Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

216000A2.06 Nuclear Boiler Inst. 2.9 3.1 D D D D D D D ~ D D D Loss of power supply 219000G2.4.41 RHRlLPCI: Torus/Pool Cooling Mode 2.9 4.6 D D D D D D D D D D ~ Knowledge of the emergency action level thresholds and classifications.

Page 1 of 1 8/27/2009 2:26 PM

ES-401, REV 9 SRO T3 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 G2.1.41 Conduct of operations 2.8 3.7 0 0 DOD 0 0 0 0 0 ~ Knowledge of the refueling processes G2.2.39 Equipment Control 3.9 4.5 0 0 0 0 0 D~ Knowledge of less than one hour technical specification action statements for systems.

G2.2.43 Equipment Control 3.0 3.3 0 0 0 0 0 0 0 0 0 ~ Knowledge of the process used to track inoperable alarms Radiation Control 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ability to control radiation releases Radiation 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiological safety procedures pertaining to licensed operator duties G2.4.40 Emergency Procedures/Plans 2.7 4.5 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the SRO's responsibilities in emergency plan implementation.

G2.4.45 Emergency Procedures/Plans 4.1 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ability to prioritize and interpret the significance of each annunciator or alarm.

Page 1 of 1 8/27/2009 2:26 PM

HLT 0801 Administrative Topics Outline Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 6/7/2010 Examination Level: RO Operating Test Number: 1006 Administrative Topic Type Describe activity to be performed Code *

(see Note)

Conduct of Operations N 2.1.5 Evaluate Work Schedule against guidelines of SPP 1.5 Fatigue Management and Work Hour Limits (jpm551)

Conduct of Operations N 2.1.36 Complete SRM operability surveillance and determine if acceptance criteria is met for core alterations. (jpm554)

Equipment Control M 2.2.38 Drywell Leakage Calculation (jpm556)

Radiation Control P 2.3.12 Locked High Radiation Area Entry requirements (jpm548)

Emergency Plan 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 (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

(S)imulator

HLT 0801 Administrative Topics Outline Form ES-301-1

1. Evaluate Work Schedule for compliance with new fatigue management guidelines New SPP 1.5 Fatigue Management and Work Hour Limits 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. Importance RO 2.9
2. Complete SRM operability surveillance and determine if acceptance criteria is met for core alterations.

New 1-SR-3.3.1.2.4 Source Range Monitor System Count Rate and Signal to Noise Ratio Check 2.1.36 Knowledge of procedures and limitations involved in core alterations.

Importance RO 3.0

3. Drywell Leakage calculations per 2-SR-2 and determination of acceptance criteria Modified 2-SR-2 Instrument Checks and Observations Handout 2-SR-2 2.2.38 Knowledge of conditions and limitations in the facility license. Importance RO 3.6
4. Locked High Radiation Area Entry requirements Previous Handout JPM 548 RWP and Survey Map SPP 5.1 Radiological Controls 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. Importance RO 3.2

HLT 0801 Administrative Topics Outline Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 6/7/2010 Examination Level: SRO Operating Test Number: 1006 Administrative Topic Type Describe activity to be performed Code *

(see Note)

Conduct of Operations N 2.1.5 Evaluate Work Schedule against guidelines of SPP 1.5 Fatigue Management and Work Hour Limits (jpm551sro)

Conduct of Operations N 2.1.18 NRC Event Notification due to Reactor Scram (jpm553)

Equipment Control N 2.2.40 Controlling a containment penetration to meet the isolation requirements of TS 3.6.1.3 (jpm555)

Radiation Control P 2.3.12 Locked High Radiation Area Entry requirements (jpm548)

Emergency Plan N 2.4.44 Protective Action Recommendation Evaluation (jpm552)

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 (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

(S)imulator

HLT 0801 Administrative Topics Outline Form ES-301-1

1. Evaluate Work Schedule for compliance with new fatigue management guidelines New SPP 1.5 Fatigue Management and Work Hour Limits 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. Importance SRO 3.9
2. NRC Event Notification due to Reactor Scram New SPP 3.5 Regulatory Reporting Requirements 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards and reports.

Importance SRO 3.8

3. Controlling a containment penetration to meet the isolation requirements of TS 3.6.1.3 New Technical Specification 3.6.1.3 Drawing 2-47E811-1 SPP 10.2 Clearance Procedure to Safely Control Energy 2.2.40 Ability to apply Technical Specifications for a system. Importance SRO 4.7
4. Locked High Radiation Area Entry requirements Previous Handout JPM 548 RWP and Survey Map SPP 5.1 Radiological Controls 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. Importance SRO 3.7
5. Protective Action Recommendation Evaluation New EPIP-1 and 5 Emergency Classification Procedure and General Emergency Completed Notification Handout 2.4.44 Knowledge of emergency plan protective action recommendations. Importance SRO 4.4

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 6/7/2010 Exam Level: RO Operating Test No.: 1006 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. Control Rod Exercise SR 3.1.3.2 (U2/U3) M, A, S 1
b. Place a 2nd/3rd RFPT in service (U2/U3) N, S 2
c. Close MSIVs during Power Operation (U2/U3) N, S 3
d. Loss of Shutdown Cooling (U2/U3) M, L, P, A, S 4
e. Returning an IRM to service from Bypass (U2/U3) N, L, S 7
f. Return DW CAM to service after isolation (U2/U3) EN, N, S 9
g. Secure Sys II from Suppression Pool Cooling (U2/U3) N, S 5
h. Generator Synchronization and Load (U2/U3) N, A, S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Shutdown Unit 3 A DG at 4 KV Shutdown Board N, E, A 6
j. Suppression Pool Water Inventory Removal App 18 (U1) N, R, E 5
k. 0-SSI-2-1, ATTACHMENT 2 D, E, A 8

@ 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

HLT 0801 Control Room/In-Plant Systems JPM Narrative Control Room Systems:

a. Control Rod Exercise SR 3.1.3.3 (80)

Modified / Simulator / Alternate Path 3-SR 3.1.3.3, Control Rod Test for Withdrawn Control Rods Rev. 28 3-AOI-85-5 Rod Drift In Rev 9 201002 Reactor Manual Control System A2.02 Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm IMPORTANCE: RO 3.2 SRO 3.3

b. Place RFPT 3C in Service (202)

New / Simulator 3-OI-3 Reactor Feedwater System Rev 79, Section 5.7 259001 Reactor Feedwater System A4.02 Ability to manually operate and/or monitor in the Control Room: Manually start/control a RFP/TDRFP IMPORTANCE: RO 3.9 SRO 3.7

c. Close MSIVs during Power Operation (203)

New / Simulator 3-OI-1 Main Steam System Rev 29 Section 8.2 239001 Main and Reheat Steam System A4.01 Ability to manually operate and/or monitor in the control room: MSIVs IMPORTANCE: RO 4.2 SRO 4.0

d. Loss of Shutdown Cooling (225)

Modified from bank / Low-Power / Simulator / Previous Exam / Alternate Path 3-AOI-74-1 Loss of Shutdown Cooling Rev 17 295021 Loss of Shutdown Cooling AA1.02 Ability to operate and/or monitor the following as they apply to Loss of Shutdown Cooling: RHR/shutdown cooling IMPORTANCE: RO 3.5 SRO 3.5

e. Returning an IRM to service from Bypass (207)

Low-Power / Simulator / New

-OI-92A IRM Rev 15 section 6.2 215003 IRM System A2.02 Ability to (a) predict the impacts of the following on the IRM System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: IRM inop condition IMPORTANCE: RO 3.5 SRO 3.7

HLT 0801 Control Room/In-Plant Systems JPM Narrative

f. Return DW Cam to Service after isolation (208)

New / Simulator / Engineered Safety Feature 3-AOI-100-1 Reactor Scram Rev 51 step 37 272000 Radiation Monitoring System A2.10 Ability to (a) predict the impacts of the following on the Radiation Monitoring System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: LOCA IMPORTANCE: RO 3.9 SRO 4.1

g. Secure System II from Suppression Pool Cooling (209)

New / Simulator 3-EOI Appendix 17A RHR System Operation Suppression Pool Cooling, Rev 5 219000 RHR/LPCI: Torus Suppression Pool Cooling Mode A4.01 Ability to manually operate and/or monitor in the control room: Pumps IMPORTANCE: RO 3.8 SRO 3.7

h. Generator Synchronization and Load (210)

New / Alternate Path / Simulator 3-OI-47 Turbine Generator System, Rev. 84, Section 5.5 3-ARP-9-7B 3-XA-55-7B Rev 22 Window 32 262001 AC Electrical Distribution A4.04 Ability to manually operate and/or monitor in the control room: Synchronizing and paralleling of different AC Supplies IMPORTANCE: RO 3.6 SRO 3.7 In-Plant Systems:

i. Shutdown Unit 3 A DG from the 4KV Shutdown Board (211)

New / Emergency or Abnormal In-Plant / Alternate Path 3-OI-82, Standby Diesel Generator System, Rev. 88, Section 7.3 and 7.5 264000 Emergency Generators K4.07 Knowledge of Emergency Generators design features and/or interlocks for the following: Local operation and control IMPORTANCE:

RO 3.3 SRO 3.4

j. Suppression Pool Water Inventory Removal 1-EOI-Appendix 18 (212)

New / RCA Entry / Emergency or Abnormal In-Plant 1-EOI-Appendix 18, Rev. 0 295029 High Suppression Pool Water Level EK2.01 Knowledge of the interrelations between High Suppression Pool Water Level and the following: RHR/LPCI IMPORTANCE: RO 3.0 SRO 3.3

HLT 0801 Control Room/In-Plant Systems JPM Narrative

k. 0-SSI-2-1, ATTACHMENT 2 (127)

Bank / Emergency or Abnormal In-Plant / Alternate Path 0-SSI-2-1 Rev 7 600000 Plant Fire on Site AA2.16 Ability to determine and interpret the following as the apply to Plant Fire on Site: Vital equipment and control systems to be maintained and operated during a fire IMPORTANCE: RO 3.0 SRO 3.5

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 6/7/2010 Exam Level: SRO-U Operating Test No.: 1006 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. Control Rod Exercise SR 3.1.3.2 (U2/U3) M, A, S 1
d. Loss of Shutdown Cooling (U2/U3) M, L, P, A, S 4
f. Return DW CAM to service after isolation (U2/U3) EN, N, S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
j. Suppression Pool Water Inventory Removal App 18 (U1) N, R, E 5
k. 0-SSI-2-1, ATTACHMENT 2 D, E, A 8

@ 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

HLT 0801 Control Room/In-Plant Systems JPM Narrative Control Room Systems:

a. Control Rod Exercise SR 3.1.3.3 (80)

Modified / Simulator / Alternate Path 3-SR 3.1.3.3, Control Rod Test for Withdrawn Control Rods Rev. 28 3-AOI-85-5 Rod Drift In Rev 9 201002 Reactor Manual Control System A2.02 Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm IMPORTANCE: RO 3.2 SRO 3.3

d. Loss of Shutdown Cooling (225)

Modified from bank / Low-Power / Simulator / Previous Exam / Alternate Path 3-AOI-74-1 Loss of Shutdown Cooling Rev 17 295021 Loss of Shutdown Cooling AA1.02 Ability to operate and/or monitor the following as they apply to Loss of Shutdown Cooling: RHR/shutdown cooling IMPORTANCE: RO 3.5 SRO 3.5

f. Return DW Cam to Service after isolation (208)

New / Simulator / Engineered Safety Feature 3-AOI-100-1 Reactor Scram Rev 51 step 37 272000 Radiation Monitoring System A2.10 Ability to (a) predict the impacts of the following on the Radiation Monitoring System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: LOCA IMPORTANCE: RO 3.9 SRO 4.1 In-Plant Systems:

j. Suppression Pool Water Inventory Removal 1-EOI-Appendix 18 (212)

New / RCA Entry / Emergency or Abnormal In-Plant 1-EOI-Appendix 18, Rev. 0 295029 High Suppression Pool Water Level EK2.01 Knowledge of the interrelations between High Suppression Pool Water Level and the following: RHR/LPCI IMPORTANCE: RO 3.0 SRO 3.3

HLT 0801 Control Room/In-Plant Systems JPM Narrative

k. 0-SSI-2-1, ATTACHMENT 2 (127)

Bank / Emergency or Abnormal In-Plant / Alternate Path 0-SSI-2-1 Rev 7 600000 Plant Fire on Site AA2.16 Ability to determine and interpret the following as the apply to Plant Fire on Site: Vital equipment and control systems to be maintained and operated during a fire IMPORTANCE: RO 3.0 SRO 3.5

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 6/7/2010 Exam Level: SRO-I Operating Test No.: 1006 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. Control Rod Exercise SR 3.1.3.2 (U2/U3) M, A, S 1
b. Place a 2nd/3rd RFPT in service (U2/U3) N, S 2
c. Close MSIVs during Power Operation (U2/U3) N, S 3
d. Loss of Shutdown Cooling (U2/U3) M, L, P, A, S 4
e. Returning an IRM to service from Bypass (U2/U3) N, L, S 7
f. Return DW CAM to service after isolation (U2/U3) EN, N, S 9
h. Generator Synchronization and Load (U2/U3) N, A, S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Shutdown Unit 3 A DG at 4 KV Shutdown Board N, E, A 6
j. Suppression Pool Water Inventory Removal App 18 (U1) N, R, E 5
k. 0-SSI-2-1, ATTACHMENT 2 D, E, A 8

@ 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

HLT 0801 Control Room/In-Plant Systems JPM Narrative Control Room Systems:

a. Control Rod Exercise SR 3.1.3.3 (80)

Modified / Simulator / Alternate Path 3-SR 3.1.3.3, Control Rod Test for Withdrawn Control Rods Rev. 28 3-AOI-85-5 Rod Drift In Rev 9 201002 Reactor Manual Control System A2.02 Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm IMPORTANCE: RO 3.2 SRO 3.3

b. Place RFPT 3C in Service (202)

New / Simulator 3-OI-3 Reactor Feedwater System Rev 79, Section 5.7 259001 Reactor Feedwater System A4.02 Ability to manually operate and/or monitor in the Control Room: Manually start/control a RFP/TDRFP IMPORTANCE: RO 3.9 SRO 3.7

c. Close MSIVs during Power Operation (203)

New / Simulator 3-OI-1 Main Steam System Rev 29 Section 8.2 239001 Main and Reheat Steam System A4.01 Ability to manually operate and/or monitor in the control room: MSIVs IMPORTANCE: RO 4.2 SRO 4.0

d. Loss of Shutdown Cooling (225)

Modified from bank / Low-Power / Simulator / Previous Exam / Alternate Path 3-AOI-74-1 Loss of Shutdown Cooling Rev 17 295021 Loss of Shutdown Cooling AA1.02 Ability to operate and/or monitor the following as they apply to Loss of Shutdown Cooling: RHR/shutdown cooling IMPORTANCE: RO 3.5 SRO 3.5

e. Returning an IRM to service from Bypass (207)

Low-Power / Simulator / New 3-OI-92A IRM Rev 15 section 6.2 215003 IRM System A2.02 Ability to (a) predict the impacts of the following on the IRM System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: IRM inop condition IMPORTANCE: RO 3.5 SRO 3.7

HLT 0801 Control Room/In-Plant Systems JPM Narrative

f. Return DW Cam to Service after isolation (208)

New / Simulator / Engineered Safety Feature 3-AOI-100-1 Reactor Scram Rev 51 step 37 272000 Radiation Monitoring System A2.10 Ability to (a) predict the impacts of the following on the Radiation Monitoring System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: LOCA IMPORTANCE: RO 3.9 SRO 4.1

h. Generator Synchronization and Load (210)

New / Alternate Path / Simulator 3-OI-47 Turbine Generator System, Rev. 84, Section 5.5 3-ARP-9-7B 3-XA-55-7B Rev 22 Window 32 262001 AC Electrical Distribution A4.04 Ability to manually operate and/or monitor in the control room: Synchronizing and paralleling of different AC Supplies IMPORTANCE: RO 3.6 SRO 3.7 In-Plant Systems:

i. Shutdown Unit 3 A DG from the 4KV Shutdown Board (211)

New / Emergency or Abnormal In-Plant / Alternate Path 3-OI-82, Standby Diesel Generator System, Rev. 88, Section 7.3 and 7.5 264000 Emergency Generators K4.07 Knowledge of Emergency Generators design features and/or interlocks for the following: Local operation and control IMPORTANCE:

RO 3.3 SRO 3.4

j. Suppression Pool Water Inventory Removal 1-EOI-Appendix 18 (212)

New / RCA Entry / Emergency or Abnormal In-Plant 1-EOI-Appendix 18, Rev. 0 295029 High Suppression Pool Water Level EK2.01 Knowledge of the interrelations between High Suppression Pool Water Level and the following: RHR/LPCI IMPORTANCE: RO 3.0 SRO 3.3

k. 0-SSI-2-1, ATTACHMENT 2 (127)

Bank / Emergency or Abnormal In-Plant / Alternate Path 0-SSI-2-1 Rev 7 600000 Plant Fire on Site AA2.16 Ability to determine and interpret the following as the apply to Plant Fire on Site: Vital equipment and control systems to be maintained and operated during a fire IMPORTANCE: RO 3.0 SRO 3.5

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