ML102520107

From kanterella
Jump to navigation Jump to search
– Examination Outline
ML102520107
Person / Time
Site: Browns Ferry  
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)
v • d • e


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 &

2 1

1 1

2 1

1 7

1 2

3 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 Plant 2

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 KA NAME / SAFETY FUNCTION:

295001G2.1.7 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003G2.1.27 Partial or Complete Loss of AC / 6 295004AA 1.03 Partial or Total Loss of DC Pwr / 6 295005AA2.08 Main Turbine Generator Trip / 3 295006AK3.03 SCRAM / 1 295016AA 1.08 Control Room Abandonment / 7 295018AK3.07 Partial or Total Loss of CCW / 8 295019AA2.02 Partial or Total Loss of Inst. Air / 8 295021AK2.01 Loss of Shutdown Cooling / 4 295023AA 1.05 Refueling Acc Cooling Mode / 8

.01 High Drywell Pressure / 5 T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.4 4.7 0 0 0 0 0 0 0 q 0 ~

3.9 4

OOOOOOOODO~

FORM ES-401-1 TOPIC:

Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

Knowledge of system purpose and or function.

3.4 3.6 0 0 0 0 0 0 ~ 0 0 0 0.

A.C. electrical distribution..........................

3.2 3.3 0 0 0 O~OOO Electrical distribution status........................

3.8 3.9 0 0 ~ 0 000000 Reactor pressure response.............................

4.0 4.0 0 0 0 0 0 ~ 0 o

Reactor pressure......................................

3.1 3.2 0 0 ~ 0 0 0 0 0 0 0 0 Cross-connecting with backup systems..................

Status of safety-related instrument air system loads AK2.1 - AK2.19)..................................

3.6 3.7 0 0 0 0 0 0 0 ~ 0 0 0 3.6 3.7 0 ~ 0 0 0 0 0 000 Reactor water temperature.............................

2.8 3.5 0 0 0 0 0 0 ~ 000 Fuel transfer system: Plant-Specific.................

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 KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 295025EK3.01 High Reactor Pressure / 3 4.2 4.3 0 0 ~ 0 0 0 0 0 0 0 0 295026EA2.01 Suppression Pool High Water Temp. /

4.1 4.2 0 0 0 5

ooo~ DO High Drywell Temperature / 5 3.7 4.1 0 ~ 00000000 Low Suppression Pool Wtr Lvi / 5 3.5 3.8

~ 0 0 0 0 0 0 0 0 o

295031 EK1.02 Reactor Low Water Level / 2 3.8 4.1

~ 0 0 0 0 0 0 0 0 0 0 295037EK2.13 SCRAM Condition Present and Power 3.4 4.1 0 ~ 0 0 0 0 0 0 0 0 0 Above APRM Downscale or Unknown

/ 1 295038G2.4.9 High Off-site Release Rate / 9 600000AK1.02 Plant Fire On Site / 8 700000AA1.03 Generator Voltage and Electric Grid Distrurbancecs 3.8 4.2 0 0 0 0 0 0 0 0 O~

2.9 3.1

~ 0 0 0 0 0 0 0 0 0 0 3.8 3.7 0 0 ODD 0 ~ 0 ODD Page 2 of 2 FORM ES-401-1 TOPIC:

Safety/relief valve opening...........................

Suppression pool water temperature....................

Drywell spray: Mark-I&II.............................

Pump NPSH.............................................

Natural circulation: Plant-Specific..................

Alternate boron injection methods: Plant-Specific....

Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

Fire Fighting Voltatge regulator controls 8/27/2009 2:26 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

295002AK2.02 Loss of Main Condenser Vac 1 3 295009AK1.05 Low Reactor Water Levell 2 295010AA1.06 High Drywell Pressure 1 5 295022G2.2.38 Loss of CRD Pumps 1 1 295029EK3.03 High Suppression Pool Wtr Lvi 1 5 295034EA 1.02 Secondary Containment Ventilation High Radiation 1 9 295036EA2.01 Secondary Containment Sump/Area Water Levell T1G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.1 3.2 D ~ D D 0 0 0 D 0 0 D 3.3 3.4

~ 0 0 0 0 D 0 0 0 0 0 3.3 3.5 0 0 0 D 0 0 ~ 0 0 0 3.6 4.5 0 0 0 0 0 D 0 0 0 0 ~

3.4 3.5 0 0 ~ 0 D 0 0 0 0 0 0 3.9 4.0 0 0 D D 0 0 ~ 0 DO 3.0 3.2 0 D 0 0 D 0 0 ~ 0 0 0 Page 1 of 1 FORM ES-401-1 TOPIC:

Main turbine.........................................,

Natural circulation...................................

Leakage detection systems.............................

Knowledge of conditions and limitations in the facility license.

Reactor SCRAM.........................................

Process radiation monitoring system...................

Operability of components within the affected area..

8/27/2009 2:26 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

203000A1.01 RHRlLPCI: Injection Mode RHRlLPCI: Injection Mode 205000K3.05 Shutdown Cooling 206000K2.02 HPCI 209001K1.08 LPCS 211000A3.01 SLC 212000A2.09 RPS 215003A4.04 IRM 215003A4.05 IRM 215004G2.2.4 Source Range Monitor 215005K4.01 APRM 1 LPRM T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.2 4.3 0 0 ooo~oooo 3.6 3.6 0 ooo~oooo 2.6 2.7 0 0 ~ 0 0 ODD 0 0 0 2.8 3.1 0 Ii'] 0 0 0 0 0 0 0 o

3.2 3.3

~ 0 0 0 0 0 0 000 3.5 3.5 0 0 0 0 0 0 0 0 ~ 0 0 4.1 4.3 0 0 0 0 0 0 0 ~

DO 3.1 3.3 0 0 0 0 0 0 0 0 0 ~ 0 3.4 3.4 0 0 0 0 0 0 0 0 0 ~ 0 3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~

3.7 3.7 ODD ~

DOD Page 1 of 3 FORM ES-401-1 TOPIC:

Reactor water level System pressure Fuel pool cooling assist: Plant-Specific System pumps: BWR-2,3,4 electrical power Pump discharge pressure: Plant-Specific High containment/drywell pressure

?IRM back panel switches, meters, and indicating lights Trip bypasses (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

Rod withdrawal blocks 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 KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 264000A3.02 EOGs 3.1 3.1 0 0 0 0 0 0 0 0 ~ 0 0 264000A3.04 EOGs 3.1 3.1 0 0 0 oooo~oo Instrument Air 2.6 2.7 0 0 0000 o~o 4OOOOOK6.05 Component Cooling Water 3.0 3.1 0 0 0 0 0 ~ 0 0 0 0 0 Page 3 of 3 FORM ES-401-1 TOPIC:

Minimum time for load pick up Operation of the governor control system on frequency and voltage control Pressure gauges Pumps 8/27/2009 2:26 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

201002A2.04 RMCS 215002A3.04 RBM 216000A1.02 Nuclear Boiler Inst.

230000A4.04 RHA/LPCI: Torus/Pool Spray Mode Fuel Pool Cooling/Cleanup 234000K5.02 Fuel Handling Equipment 241000K6.06 ReactorlTurbine Pressure Regulator 268000K3.04 272000A3.01 Radiation Monitoring 286000G2.2.42 Fire Protection 290002K1.12 Reactor Vessel Internals T2G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.2 3.1 0 0 0 0 0 0 0 ~ 0 0 0 3.6 3.5 0 0 ooooo~oo 2.9 3.1 0 0 0 0 0 0 ~ 0 0 0 0 3.1 2.9 0 0 0 0 0 0 0 0 0 ~ 0 2.8 2.9 0 ~ 0 0 0 0 0 0 0 0 0 3.1 3.7 000 0 ~ 0 0 0 00 3.8 3.9 0 0 0 0 0 ~ 0 0 0 0 0 2.7 2.8 0 0 ~ 0 0 0 0 0 0 0 0 3.8 3.9 0 0 0 0 0 0 0 0 ~ 0 0 3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~

3.4 3.5

~ 0 0 0 0 0 0 0 0 0 0 Page 1 of 2 FORM ES-401-1 TOPIC:

Control rod block Verification or proper functioning/ operability: BWR-3,4,5 Removing or returning a sensor (transmitter) to service Minimum flow valves RHRpumps Fuel handling equipment interlocks Reactor pressure Drain sumps Main steam isolation indications Ability to recognize system parameters that are entry-level conditions for Technical Specifications SBLC 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 KA NAME / SAFETY FUNCTION:

G2.1.25 Conduct of operations G2.1.27 Conduct of operations G2.1.8 Conduct of operations G2.2.20 Equipment Control Equipment Control Equipment Control G2.3.14 Radiation Control G2.3.5 Radiation Control G2.4.20 Emergency Procedures/Plans G2.4.45 Emergency Procedures/Plans T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.9 4.2 0 0 0 0 0 0 0 0 0 0 ~

3.9 4

000 oooooo~

3.4 4.1 0

oooooooo~

2.6 3.8 0 0 0 0 0 0 0 0 0 0 ~

4.0 4.7 0 0 0 0 0 0 0 0 O~

3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~

3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~

2.9 2.9 0 0 0 0 0 0 0 0 0 0 ~

3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~

4.1 4.3 0 0 0 0 0 0 0 0 O~

Page 1 of 1 FORM ES-401-1 TOPIC:

Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

Knowledge of system purpose and or function.

Ability to coordinate personnel activities outside the control room.

Knowledge of the process for managing troubleshooting activities.

Knowledge of limiting conditions for operations and safety limits.

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

Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Ability to use radiation monitoring systems Knowledge of operational implications of EOP warnings, cautions and notes.

Ability to prioritize and interpret the significance of each annunciator or alarm.

8/27/2009 2:26 PM

ES-401, REV 9 SRO T1G1 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G 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 295016AA2.05 Control Room Abandonment / 7 3.8 3.9 0 0 0 0 0 0 0 ~ DO 295018G2.1.27 Partial or Total Loss of CCW / 8 3.9 4

00000 oooo~

295021G2.4.47 Loss of Shutdown Cooling / 4 4.2 4.2 0 0 0 0 0 0 0 0 0 0 ~

295023G2.1.7 Refueling Acc Cooling Mode / 8 4.4 4.7 0 0 0 0 0 0 0 0 0 0 ~

295024G2.1.31 High Drywell 5

4.6 4.3 0 0 ooooooo~

295028EA2.06 High Drywell Temperature / 5 3.4 3.7 0 ooooo~ooo Page 1 of 1 FORM ES-401-1 TOPIC:

Cause of partial or complete loss of D.C. power.......

Drywell pressure......................................

Knowledge of system purpose and or function.

Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

Torus/suppression chamber air space temperature: Plant-Specific........................................

8/27/2009 2:26 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

295010G2.2.4 High Drywe/l Pressure 1 5 295014AA2.01 Inadvertent Reactivity Addition 1 1 295033G2.2.39 High Secondary Containment Area Radiation Levels 1 9 SRO T1G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~

4.1 4.2 0 0 0 DDD~DDD 3.9 4.5 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1 FORM ES-401-1 TOPIC:

(multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

Reactor power.........................................

Knowledge of less than one hour technical specification action statements for systems.

8/27/2009 2:26 PM

ES-401, REV 9 SRO T2G1 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G AO SAO 203000A2.09 AHA/LPCI: Injection Mode 3.3 3.4 0 0 0 0 0 0 ~ 0 0 0 211 OOOG2.1.7 SLC 4.4 4.7 0 0 0 0 0 0 0 0 0

~

261000G2.2.4 SGTS 3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~

263000G2.1.28 DC Electrical Distribution 4.1 4.1 0 0 0 0 0 0 0 0 0 ~

400000A2.02 Component Cooling Water 2.8 3.0 0 0 0 0 0 0 0 ~ 0 0 0 Page 1 of 1 FORM ES-401-1 TOPIC:

Inadequate system flow Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

(multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

Knowledge of the purpose and components and controls.

High/low surge tank level of major system 8/27/2009 2:26 PM

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 215001G2.4.2 Traversing In-core Probe 4.5 4.6 D D D D D D D D D D ~

216000A2.06 Nuclear Boiler Inst.

2.9 3.1 D D D D D D D ~ D D D 219000G2.4.41 RHRlLPCI: Torus/Pool Cooling Mode 2.9 4.6 D D D D D D D D D D ~

Page 1 of 1 FORM ES-401-1 TOPIC:

Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Loss of power supply Knowledge of the emergency action level thresholds and classifications.

8/27/2009 2:26 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.41 Conduct of operations G2.2.39 Equipment Control G2.2.43 Equipment Control Radiation Control Radiation G2.4.40 Emergency Procedures/Plans G2.4.45 Emergency Procedures/Plans SRO T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 3.7 0 0 DOD 0 0 0 0 0 ~

3.9 4.5 0 0 0 0 0 D~

3.0 3.3 0

0 0 0 0 0 0 0 0 ~

3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~

3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~

2.7 4.5 0 0 0 0 0 0 0 0 0 0 ~

4.1 4.3 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1 FORM ES-401-1 TOPIC:

Knowledge of the refueling processes Knowledge of less than one hour technical specification action statements for systems.

Knowledge of the process used to track inoperable alarms Ability to control radiation releases Knowledge of radiological safety procedures pertaining to licensed operator duties Knowledge of the SRO's responsibilities in emergency plan implementation.

Ability to prioritize and interpret the significance of each annunciator or alarm.

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 (see Note)

Type Code

  • Describe activity to be performed 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 (see Note)

Type Code

  • Describe activity to be performed 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)

System / JPM Title Type Code*

Safety 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 (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

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)

System / JPM Title Type Code*

Safety 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 (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

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)

System / JPM Title Type Code*

Safety 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 (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

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

Retrieved from "https://kanterella.com/w/index.php?title=ML102520107&oldid=5292755"