ML100830061

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Initial Exam 2009-302 Draft Administrative Documents
ML100830061
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 02/11/2010
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
50-390/09-302
Download: ML100830061 (19)
v • d • e


Text

FACI LlTY NAM E: __

__ Section 1

________________

_ DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS:

IB"'Oraft Written Exam sample plan (ES-401-1/2/3)

CB1)raft Administrative Topics Outline (ES-301-1) g/Oraft Control Room Systems & Facility Walk-Through Test Outline (ES-301-2)

Location of Electronic Files: SubmittooBy:

1.1(A, if FACILITY NAME: __

__ Section 1 REPORTNUMBER:

__

_______ ___ DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS:

Written Exam sample plan (ES-401-1/2/3)

C!Y6raft Administrative Topics Outline (ES-301-1) g/Oraft Control Room Systems & Facility Walk-Through Test Outline (ES-301-2)

Location of Electronic Files: Submitted By:

By 1nJ 1. 2Jk , d

( ES-401 1 Rev. 9 PWR Examination Outline Form ES-401-2 I Facility:

Watts Bar Date of Exam: Nov 2009 I 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 3 3 3 3 3 3 18 3 3 6 Emergency

& 2 1 1 2 2 1 2 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 4 4 5 5 4 5 27 5 5 10 1 3 2 3 3 2 2 2 3 2 3 3 28 3 2 5 2. 1 0 1 1 1 1 1 1 1 1 1 10 2 1 3 Plant 2 Systems Tier Totals 4 2 4 4 3 3 3 4 3 4 4 38 5 3 8 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 1 2 2 2 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall nolbe 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. Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution*

in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or. higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SROtopicsJor 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; iffuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # 1 does not apply). Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topiCS from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

LimitSRO selections to KIAs that are linked to 10 CFR 55.43. ( ES-401 1 Rev. 9 PWR examination Outline Form ES-4D1-2 I Facility:

Watts Bar Date of Exam: Nov 2009 I 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 3 3 3 3 3 3 18 3 3 6 Emergency

& 2 1 1 2 2 1 2 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 4 4 5 5 4 5 27 5 5 10 1 3 2 3 3 2 2 2 3 2 3 3 28 3 2 5 2. 1 0 1 1 1 1 1 1 1 1 1 10 2 1 3 Plant 2 Systems Tier Totals 4 2 4 4 3 3 3 4 3 4 4 38 5 3 8 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 1 2 2 2 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two). 2. The point total for each group and tier in the proposed outline must match that specified in the table. ( The final point total for each group and tier may deviate by +/- 1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SROtopicsJor 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; iffuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # 1 does not apply). Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

LimitSRO selections to KIAs that are linked to 10 CFR 55.43.

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 007EG2.4.21 Reactor Trip -Stabilization

-Recovery 4.0 4.6 0 0 0 0 0 0 0 0 0 0 11 009EA2.20 Small Break LOCA 13 2.6 2.9 0 0 0 0 0 0 0 0 0 0 011 EK1.01 Large Break LOCA I 3 4.1 4.4

_ .... _,---_ .. _--_ ... 015AK1.03 RCP Malfunctions 14 3 4 022AA1.02 Loss of Rx Coolant Makeup I 2 3 2.9 TOPIC: Knowledge of the parameters and logic used to assess the status of safety functions Containment vent damper position indicator Natural circulation and cooling, including reflux boiling. The basis for operating at a reduced power level when one RCP is out of service CVCS charging low flow alarm, sensor and indicator

---_ .. _--------_._----------_._

.. _---------_

.. _---02SAK2.0S Loss of RHR System 14 2.6 2.6 o 0 0 0 0 0 0 0 0 0 Reactor building sump 026AK3.02 Loss of Component Cooling Water I 8 3.6 3.9 The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 027AK2.03 Pressurizer Pressure Control System 2.6 Malfunction I 3 2.8 Controllers and positioners 029EK1.0S ATWS/1 2.8 3.2 00000'000 definition of negative temperature coefficient as applied to large PWR coolant systems 038EA2.11 Steam Gen. Tube Rupture I 3 3.7 3.9 Local radiation reading on main steam lines 040AA1.23 Steam Line Rupture -Excessive Heat 3,6 3.S All pressure gauges per steam generator (for pressure Transfer 14 drop) Page 1 of 2 2111/20097:17AM ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 007EG2.4.21 Reactor Trip -Stabilization

-Recovery 4.0 4.6 0 0 0 0 0 0 0 0 0 0 11 009EA2.20 Small Break LOCA 13 2.6 2.9 0 0 0 0 0 0 0 0 0 0 Large Break LOCA 1 3 4.1 4.4 0 0 0 0 0 0 0 0 0 0 015AK1.03 RCP Malfunctions 14 3 4 022AA1.02 Loss of Rx Coolant Makeup 1 2 3 2.9 DODD 0 0 0 0 0 0 FORM ES-401-2 TOPIC: Knowledge of the parameters and logic used to assess the status of safety functions Containment vent damper position indicator Natural circulation and cooling, including reflux boiling. The basis for operating at a reduced power level when one RCP is out of service CVCS charging low flow alarm, sensor and indicator

--_._-_._--_.-

025AK2.05 Loss of RHR System 14 2.6 2.6 0 0 0 0 0 0 0 0 0 0 Reactor building sump 026AK3.02 Loss of Component Cooling Water 18 3.6 3.9 The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 027AK2.03 Pressurizer Pressure Control System 2.6 Malfunction 1 3 2.8 Controllers and positioners 029EK1.05 ATWS/1 2.8 3.2 definition of negative temperature coefficient as applied to large PWR coolant systems 038EA2.11 Steam Gen. Tube Rupture 13 3.7 3.9 Local radiation reading on main steam lines 040AA1.23 Steam Line Rupture -Excessive Heat 3.6 3.5 All pressure gauges per steam generator (for pressure Transfer 14 drop) Page 1 of 2 2111/2009 7:17 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

054AK3.03 Loss of Main Feedwater / 4 055EA2.06 Station Blackout / 6 057 AG2.1.23 Loss of Vital AC Inst. Bus / 6 058AG2.4.34 Loss of DC Power / 6 065AK3.04 Loss of Instrument Air / 8 077AK2.03 Generator Voltage and Electric Grid Disturbances / 6 WE04EA 1.3 LOCA Outside Containment / 3 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.8 4.1 0 0 Ii'l 0 0 0 0 0 0 0 3.7 4.1 0 0 0 0 0 0 0 Ii'l 0 0 0 4.3 4.4 0 0 0 0 0 DOD 0 0 Ii'l 4.2 4.1 0 0 0 0 0 0 DDDIi'l 3 3.2 0 0 Ii'l 0 0 0 0 0 0 0 0 3.0 3.1 0 Ii'l 0 0 0 0 0 0 0 0 0 3.8 4.0 0 0 0 0 0 0 Ii'l 0 0 0 0 Page 2 of 2 FORM ES-401-2 TOPIC: Manual control of AFW flow control valves Faults and lockouts that must be cleared prior to energizing buses Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Cross-over to backup air supplies Sensors, detectors, indicators Desired operating results during abnormal and emergency situations.

2111/2009 7:17 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

054AK3.03 Loss of Main Feedwater / 4 055EA2.06 Station Blackout / 6 057 AG2.1.23 Loss of Vital AC Ins!. Bus / 6 058AG2.4.34 Loss of DC Power / 6 065AK3.04 Loss of Instrument Air / 8 077AK2.03 Generator Voltage and Electric Grid Disturbances / 6 WE04EA 1.3 LOCA Outside Containment

/3 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.8 4.1 0 0 0 0 0 0 0 0 0 0 3.7 4.1 0 0 0 0 0 0 0 0 0 0 4.3 4.4 0 0 0 0 0 0 0 0 0 0 4.2 4.1 0 0 0 0 0 0 0 0 0 0 3 3.2 0 0 0 0 0 0 0 0 0 0 3.0 3.1 0 0 0 0 0 0 0 0.0 0 3.8 4.0 0 0 0 0 0 0 0 0 0 0 Page 2 of 2 .--'-" FORM ES-401-2 TOPIC: Manual control of AFW flow control valves Faults and lockouts that must be cleared prior to energizing buses Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Cross-over to backup air supplies Sensors, detectors, indicators Desired operating results during abnormal and emergency situations.

2/11/2009 7:17 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

024AA2.02 Emergency Boration 11 028AK3.0S Pressurizer Level Malfunction I 2 036AG2.4.2 Fuel Handling Accident I 8 OS9AK3.01 Accidental Liquid RadWaste ReI. 19 067 AK1.01 Plant Fire On-site 19 8 069AA 1.01 Loss of CTMT Integrity I S WE01 EA 1.3 Rediagnosis I 3 we13EG2.1.31 Steam Generator OverCpressure I 4 WE1SEK2.2 Containment Flooding IS T1 G2 PWR EXAMINATION OUTLINE IR K1 K2K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.9 4.4 0 0 0 0 0 0 0 0 0 0 3.7 4.1 0 0 0 0 0 0 0 0 0 0 4.S 4.6 0 0 0 0 0 0 0 0 0 0 3.S 3.9 0 0 0 0 0 0 0 0 0 0 2.9 3.9 0 0 0 0 0 0 0 0 0 0 3.S 3.7 000 0 0 0 000 0 3.4 3.8 0 0 0 0 0 0 DOD 0 4.6 4.3 0 0 0 0 0 0 0 0 0 0 2.7 2.9 0 0 0 0 0 0 0 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC: When use of manual boration valve is needed Actions contained in EOP for PZR level malfunction Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Termination of a release of radioactive liquid Fire classifications by type Isolation valves, dampers and electropneumatic devices. Desired operating results during abnormal and emergency situations.

Ability to locate control room switches, controls and, indications and to determine that they are correctly reflecting the desired plant lineup. Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

2111/2009 7:17 AM ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 024AA2.02 Emergency Boration / 1 3.9 4.4 0 0 0 0 0 0 0 0 0 0 028AK3.05 Pressurizer Level Malfunction / 2 3.7 4.1 0 0 0 0 0 0 0 0 0 0 036AG2.4.2 Fuel Handling Accident I 8 4.5 4.6 0 0 0 0 0 0 0 0 0 0 059AK3.01 Accidental Liquid RadWaste ReI. / 9 3.5 3.9 0 0 0 0 0 0 0 0 0 0 067AK1.01 Plant Fire On-site / 9 8 2.9 3.9 0 0 0 0 0 0 0 0 0 0 069AA 1.01 Loss of CTMT Integrity / 5 3.5 3.7 0 0 0 0 0 0 0 0 0 0 WE01 EA 1.3 Rediagnosis / 3 3.4 3.8 0 0 0 0 0 0 0 0 0 0 we13EG2.1.31 Steam Generator Over-pressure / 4 4.6 4.3 0 0 0 0 0 0 0 0 0 0 WE15EK2.2 Containment Flooding 15 2.7 2.9 0 0 0 0 0 0 0 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC: When use of manual boration valve is needed Actions contained in EOP for PZR level malfunction Knowledge of system set pOints, interlocks and automatic actions associated with EOP entry conditions.

Termination of a release of radioactive liquid Fire classifications by type Isolation valves, dampers and electropneumatic devices. Desired operating results during abnormal and emergency situations.

Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup. Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

2I11/20097:17AM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 003A1.09 Reactor Coolant Pump 2.8 2.8 Seal flow and D/P ---------004K5.36 Chemical and Volume Control 2.5 2.B Solubility of boron in water; tem perature effect 005G2.1.23 Residual Heat Removal 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

005K6.03 Residual Heat Removal 2.5 2.6 RHR heat exchanger 006K5.09 Emergency Core Cooling 3.3 3.6 Thermodynamics of water and steam, including subcooled margin, superheat and saturation 007A4.01 Pressurizer Relief/Quench Tank 2.7 2.7 PRT spray supply valve 007A4.09 Pressurizer Relief/Quench Tank 2.5 2.7 Relationships between PZR level and changing levels of the PRT and bleed holdup tank 00BK1.05 Component Cooling Water 3.0 3.1 Sources of makeup water 010A4.03 Pressurizer Pressure Control 4.0 3.B PORV and block valves 012A3.03 Reactor Protection 3.4 3.5 Power supply 012G2.1.30 Reactor Protection 4.4 4.0 Ability to locate and operate components, including local controls.

Page 1 of 3 2I11/20097:17AM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 003A1.09 Reactor Coolant Pump 2.B 2.B Seal flow and D/P 004K5.36 Chemical and Volume Control 2.5 2.B Solubility of boron in water; temperature effect 005G2.1.23 Residual Heat Removal 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

005K6.03 Residual Heat Removal 2.5 2.6 RHR heat exchanger 006K5.09 Emergency Core Cooling 3.3 3.6 Thermodynamics of water and steam, including subcooled margin, superheat and saturation 007A4.01 Pressurizer Relief/Quench Tank 2.7 2.7 PRT spray supply valve 007A4.09 Pressurizer Relief/Quench Tank 2.5 2.7 Relationships between PZR level and changing levels of the PRT and bleed holdup tank 00BK1.05 Component Cooling Water 3.0 3.1 Sources of makeup water -010A4.03 Pressurizer Pressure Control 4.0 3.B PORV and block valves 012A3.03 Reactor Protection 3.4 3.5 Power supply 012G2.1.30 Reactor Protection 4.4 4.0 Ability to locate and operate components, including local controls.

Page 1 of 3 2111/2009 7:17 AM

,J'(.'-..."" \ ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 013K6.01 Engineered Safety Features Actuation 2.7 3.1 0 0 0 0 0 0 0 0 0 0 022K2.02 Containment Cooling 2.S 2.4 0 0 0 0 0 0 0 0 0 0 026K4.0B Containment Spray 4.1 4.3 0 0 0 0 0 0 000 039K1.02 Main and Reheat Steam 3.3 3.3 0 0 0 0 0 0 0 0 0 0 OS9K3.04 Main Feedwater 3.6 3.B 0 0 0 0 0 0 0 0 0 0 OS9K4.02 Main Feedwater 3.3 3.5 0 0 0 0 0 0 0 0 0 0 061A2.0B Auxiliary/Emergency Feedwater 2.7 2.9 0 0 0 0 0 0 0 0 0 0 062A2.09 Electrical Distribution 2.7 3.0 0 0 0 0 0 0 0 0 0 0 062A2.10 AC Electrical Distribution 3.0 3.3 LJ 0 DOD 0 0 0 0 0 063K3.01 DC Electrical Distribution 3.7 4.1 0 0 0 000000 063K4.01 DC Electrical Distribution 2.7 3.0 0 0 Page 2 of 3 FORM ES-401-2 TOPIC: Sensors and detectors Automatic swapover to containment sump suction for recirculation phase after LOCA (RWST low-low level alarm) Atmospheric relief dump valves RCS Automatic turbine/reactor trip runback Flow rates expected from various combinations of AFW pump discharge valves Consequences of exceeding current limitations Effects of switching power supplies on instruments and controls ED/G Manual/automatic transfers of control 211112009 7: 17 AM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 013K6.01 Engineered Safety Features Actuation 2.7 3.1 0 0 0 0 0 0 0 0 0 0 022K2.02 Containment Cooling 2.5 2.4 0 0 0 0 0 0 0 0 0 0 026K4.0B Containment Spray 4.1 4.3 0 0 0 0 0 0 0 0 0 0 039K1.02 Main and Reheat Steam 3.3 3.3 0 0 0 0 0 0 0 0 0 0

-059K3.04 Main Feedwater 3.6 3.B 0 0 0 0 0 0 0 0 0 0 059K4.02 Main Feedwater 3.3 3.5 0 0 0 0 0 0 0 0 0 0 061A2.0B Auxiliary/Emergency Feedwater 2.7 2.9 0 0 0 0 0 0 0 0 0 0 062A2.09 AC Electrical Distribution 2.7 3.0 0 0 0 0 0 0 0 0 0 0 062A2.10 AC Electrical Distribution 3.0 3.3 DOD 0 0 0 0 0 0 0 063K3.01 DC Electrical Distribution 3.7 4.1 0 0 0 0 0 0 0 0 0 0 063K4.01 DC Electrical Distribution 2.7 3.0 0 0 0 0 0 0 0 0 0 0 Page 2 of 3 FORM ES-401-2 TOPIC: Sensors and detectors Chillers Automatic swapover to containment sump suction for recirculation phase after LOCA (RWST low-low level alarm) Atmospheric relief dump valves RCS Automatic turbine/reactor trip runback Flow rates expected from various combinations of AFW pump discharge valves Consequences of exceeding current limitations Effects of switching power supplies on instruments and controls ED/G Manual/automatic transfers of control 2/1112009 7:17 AM

"'"-,.

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

064A1.04 Emergency Diesel Generator 064K1.03 Emergency Diesel Generator 073K3.01 Process Radiation Monitoring 076K2.01 Service Water 078A3.01 Instrument Air 103G2.4.30 Containment T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 2.8 2.9 D D D D D D 21 D D D D" Crankcase temperature and pressure 3.6 4.0 21 D D D D D D D D D D oil supply system 3.6 4.2 D D 21 D D D D D D D D Radioactive effluent 2.7 2.7 D 21 --=-==----::---,----------------D D D D D D D D Service water 3.1 3.2 D D D D D D D D 21 D D 2.7 4.1 D D D D D D D D D D 21 Page 3 of 3 Air pressure Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

2I11/20097:17AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

064A1.04 Emergency Diesel Generator 064K1.03 Emergency Diesel Generator 073K3.01 Process Radiation Monitoring 076K2.01 Service Water 078A3.01 Instrument Air 103G2.4.30 Containment T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 2.9 0 0 0 0 0 0 0 0 0 0 3.6 4.0 0 0 0 0 0 0 0 0 0 0 3.6 4.2 0 0 0 0 0 0 0 0 0 0 2.7 2.7 0 0 0 0 0 0 0 0 0 0 3.1 3.2 0 0 0 0 0 0 0 0 0 0 2.7 4.1 0 0 0 0 0 0 0 0 0 0 Page 3 of 3 FORM ES-401-2 TOPIC: Crankcase temperature and pressure Diesel fuel oil supply system Radioactive effluent releases Service water Air pressure Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

2111/2009 7:17 AM

REV.9 KA NAME / SAFETY FUNCTION:

001A1.13 Control Rod Drive 002A4.05 Reactor Coolant T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.0 4.2 D D D D D D D D D D 2.8 2.7 D D D D D D D D D D FORM ES-401-2 TOPIC: 'Prepower dependent insertion limit' and pbwer dependent insertion limit, determined with metroscope The HPI system when it is used to refill the refueling cavity -----_._._

..

016G2.2.38 Non-nuclear Instrumentation 3.6 4.5 D D D D D D D D D D Knowledge of conditions and limitations in the facility license. 027K1.01 Containment Iodine Removal 033A3.01 Spent Fuel Pool Cooling 035K6.01 Steam Generator 045K4.46 Main Turbine Generator 055K3.01 Condenser Air Removal 071A2.02 Waste Gas Disposal 086K5.04 Fire Protection 3.4 3.7 2.5 2.7 3.2 3.6 2.5 2.8 2.5 2.7 D D D D D D D D D 3.3 3.6 D D D D D D D D D D 2.9 3.5 D D D D D D D D D D Page 1 of 1 CSS Temperature control valves MSIVs Defeat of reactor trip by overs peed trip test lever Main condenser Use of waste gas release monitors, radiation, gas flow rate and totalizer Hazards to personnel as a result cif fire type and methods of protection 2111/2009 7:17 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

001A1.13 Control Rod Drive 002A4.05 Reactor Coolant 016G2.2.38 Non-nuclear Instrumentation 027K1.01 Containment Iodine Removal T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.0 4.2 D D D D D D D D D D 2.8 2.7 D D D D D D D D D D 3.6 4.5 D D D D D D D D D D 3.4 3.7 D D D D D D D D D D FORM ES-401-2 TOPIC: "Prepower dependent insertion limit" and power dependent insertion limit, determined with metroscope The HPI system when it is used to refill the refueling cavity Knowledge of conditions and limitations in the facility license. CSS 033A3.01 .---.-.-....

Spent Fuel Pool Cooling 2.5 2.7 D D D D D D D D D D Temperature control valves 035K6.01 Steam Generator 045K4.46 Main Turbine Generator 055K3.01 Condenser Air Removal 071A2.02 Waste Gas Disposal 086K5.04 Fire Protection 3.2 3.6 D D D D D D D D D D 2.5 2.8 D D D D D D D D D D 2.5 2.7 D D D D D D D D D D 3.3 3.6 D D D D D D D D D D 2.9 3.5 D D D D D D D D D D Page 1 of 1 MSIVs Defeat of reactor trip by overspeed trip test lever Main condenser Use of waste gas release monitors, radiation, gas flow rate and totalizer Hazards to personnel as a result of fire type and methods of protection 2111/2009 7:17 AM

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

G2.1.29 Conduct of operations G2.1.30 Conduct of operations G2.1.6 Conduct of operations G2.2.41 Equipment Control G2.2.42 Equipment Control G2.3.13 Radiation Control G2.3.6 Radiation G2.4.12 Emergency Procedures/Plans G2.4.21 Emergency Procedures/Plans G2.4.39 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.1 4.0 0 0 0 0 0 0 0 0 0 0 4.4 4.0 0 0 0 0 0 0 0 0 0 0 3.8 4.8 3.5 3.9 000000000 3.9 4.6 3.4 3.8 2.0 3.8

-4.0 4.3 4.0 4.6 3.9 3.8 Page 1 of 1 3 FORM TOPIC: Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc. Ability to locate and operate components, including local controls.

Ability to manage the control room crew during plant transients.

Ability to obtain and interpret station electrical and mechanical drawings Ability to recognize system parameters that are level conditions for Technical Specifications Knowledge of radiological safety procedures pertaining to licensed operator duties Ability to aprove release permits Knowledge of general operating crew responsibilities during emergency operations.

Knowledge of the parameters and logic used to assess the status of safety functions Knowledge of the RO's responsibilities in emergency plan implementation.

2111/2009 7:17 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

RO G2.1.29 Conduct of operations 4.1 G2.1.30 Conduct of operations 4.4 G2.1.6 Conduct of operations 3.8 G2.2,41 Equipment Control 3.S G2.2.42 Equipment Control 3.9 G2.3.13 Radiation Control 3.4 G2.3.6 Radiation Control 2.0 G2.4.12 Emergency Procedures/Plans 4.0 G2.4.21 Emergency Procedures/Plans 4.0 G2.4.39 Emergency Procedures/Plans 3.9 T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G SRO 4.0 4.0 4.8 3.9 4.6 3.8 3.8 4.3 . -4.6 3.8 Page 1 of 1 3 FORM TOPIC: Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc. Ability to locate and operate components, including local controls.

Ability to manage the control room crew during plant transients.

Ability to obtain and interpret station electrical and mechanical drawings Ability to recognize system parameters that are level conditions for Technical Specifications Knowledge of radiological safety procedures pertaining to licensed operator duties Ability to aprove release permits Knowledge of general operating crew responsibilities during emergency operations . Knowledge of the parameters and logic used to assess the status of safety functions Knowledge of the RO's responsibilities in emergency plan implementation.

2111/2009 7:17 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

022AA2.03 Loss ot'Rx Coolant Makeup /2 029EG2.2.22 ATWS/1 038EG2.2.4 Steam Gen. Tube Rupture 13 058AA2.02 Loss of DC Power 16 077AA2.07 Generator Voltage and Electric Grid Disturbances I 6 we05EG2.4.3 Inadequate Heat Transfer -Loss of Secondary Heat Sink I 4 SRO T1G1 PWR EXAMINATION OUTLINE IR K1 K2K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.1 3.6 0 0 0 0 0 DOli'] 0 0 0 4.0 4.7 0 0 0 0 0 0 0 0 DOli'] 3.6 3.6 0 0 0 0 0 0 0 0 DOli'] 3.3 3.6 0 0 0 0 0 DOli'] 0 0 0 3.6 4.0 0 0 0 0 0 DOli'] 0 0 0 3.7 3.9 0 0 0 0 0 DOD DOli'] Page 1 of 1 FORM ES-401-2 TOPIC: Failures of flow control valve or controller 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.

125V dc bus voltage, lowlcriticallow, alarm Operational status of engineered safety features Ability to identify post-accident instrumentation.

2/11/2009 7:17 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

022AA2.03 Loss o(Rx Coolant Makeup / 2 029EG2.2.22 ATWS / 1 038EG2.2.4 Steam Gen. Tube Rupture / 3 058AA2.02 Loss of DC Power / 6 077AA2.07 Generator Voltage and Electric Grid Disturbances / 6 we05EG2.4.3 Inadequate Heat Transfer -Loss of Secondary Heat Sink / 4 SRO T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.1 3.6 D D D D D D D D D D 4.0 4.7 D D DOD D D D D D 3.6 3.6 D D D D D D D D D D 3.3 3.6 D D D D D D D D D D 3.6 4.0 D D D D D D D D D D 3.7 3.9 D D D D D D D D D D Page 1 of 1 FORM ES-401-2 TOPIC: Failures of flow control valve or controller 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.

125V dc bus voltage, low/critical low, alarm Operational status of engineered safety features Ability to identify post-accident instrumentation.

2111/2009 7:17 AM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 033AG2.2.40 Loss of Intermediate Range NI/7 3.4 4.7 0 0 0 0 0 0 0 0 0 0 067AA2.12 Plant Fire On-site 1 9 8 2.9 3.9 0 0 0 0 0 0 0 0 0 0 we06EG2.1.23 Degraded Core Cooling 1 4 4.3 4.4 0 0 0 0 DOD 0 0 0 WE09EA2.1 Natural Circ. 14 3.1 3.8 0 0 0 0 0 0 0 0 0 0 Page 1 of 1 -", FORM ES-401-2 TOPIC: Ability to apply technical specifications for a system. Location of vital equipment within fire zone Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

2I11/20097:17AM ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 033AG2.2.40 Loss of Intermediate Range NI/7 3.4 4.7 0 0 0 0 0 0 0 0 0 0 067AA2.12 Plant Fire On-site 1 9 8 2.9 3.9 ° 0 0 0 0 0 0 0 0 0 0 we06EG2.1.23 Degraded Core Cooling 14 4.3 4.4 0 0 0 0 0 0 DO 0 0 0 WE09EA2.1 Natural Circ. 1 4 3.1 3.8 0 0 0 0 0 0 0 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC: Ability to apply technical specifications for a system. Location of vital equipment within fire zone Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

2111/2009 7:17 AM ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 008G2.2.25 Component Cooling Water 3.2 4.2 n n n n n D D D D 010A2.02 Pressurizer Pressure Control 3.9 3.9 D D D D D D D DOD 026A2.03 Containment Spray 4.1 4.4 063G2.4.20 DC Electrical Distribution 3.8 4.3 DOD 0 D D D D D D 103A203 Containment 3.5 Page 1 of 1 -,-'---...., FORM ES-401-2 TOPIC: Knowledge of the bases in Technical Specifications for lim iting conditions for operations and safety lim its. Spray valve failures of ESF Knowledge of operational implications of EOP warnings, cautions and notes. 2I11/20097:17AM ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 008G2.2.25 Component Cooling Water 3.2 4.2 D D D D D D D D D D 010A2.02 Pressurizer Pressure Control 3.9 3.9 D D D D D D D D D D 026A2.03 Containment Spray 4.1 4.4 D D D D D D D D D D 063G2.4.20 DC Electrical Distribution 3.8 4.3 D D D D D D D D D D 103A203 Containment 3.5 3.8 D D D D D D D D D D Page 1 of 1 ---.. FORM ES-401-2 TOPIC: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. Spray valve failures Failure of ESF Knowledge of operational implications of EOP warnings, cautions and notes. Phase A and B isolation 2111/2009 7:17 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

028A2.01 068A2.03 071G2.4.9 Hydrogen f!ecombiner and Purge Control Liquid Radwaste Waste Gas SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.4 3.6 0 0 0 0 0 0 0 lilI 0 0 0 2.5 2.6 0 0 0 0 0 0 0 lilI 0 0 0 3.8 4.2 0 D 0 [j 0 0 0 0 0 0 lilI Page 1 of 1 FORM ES-401-2 TOPIC: Hydrogen recombiner power setting. determined by using plant data book Insufficient sampling frequency of the boric acid in the evaporator bottoms Knowledge of low power 1 shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

2111/2009 7:17 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

028A2.01 068A2.03 071G2.4.9 Hydrogen Recombiner and Purge Control Liquid Radwaste Waste Gas Disposal SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.4 3.6 0 0 0 0 0 0 0 0 0 0 2.5 2.6 0 0 0 0 0 0 0 0 0 0 3.8 4.2 0 0 0 0 0 0 0 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC: Hydrogen recombiner power setting, determined by using plant data book Insufficient sampling frequency of the boric acid in the evaporator bottoms Knowledge of low power 1 shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

2111/2009 7:17 AM

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

G2.1.41 Conduct of operations G2.222 Equipment Control G2.2.37 Equipment Control G2.3.6 Radiation Control G2.3.7 Radiation Control SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 3.7 0 0 0 0 0 0 DO 0 0 4.0 4.7 0 0 0 0 0 0 0 0 0 0 TOPIC: Knowledge of the refueling processes

'-, 3 FORM ES-401'\ Knowledge of lim iting conditions for operations and safety limits.

3,6 4.6 0 0 0 0 0 0 0 0 0 0 Ability to determine operability and/or availability of safety related equipment 2.0 3.8 0 0 0 0 0 0 0 0 0 0 3.5 3.6 0 0 0 0 0 0 0 0 0 0 Ability to aprove release permits Ability to comply with radiation work permit requirements during normal or abnormal conditions

---,_._--G2.4.18 Emergency Procedures/Plans 3.3 4.0 0 0 0 0 0 0 0 0 0 0 Knowledge of the specific bases for EOPs. G2.4.3 Emergency Procedures/Plans 3.7 3.9 0 0 0 0 0 0 0 0 0 0 to identify post-accident instrumentation.

Page 1 of 1 2111/20097:17AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.41 Conduct of operations G2.2.22 Equipment Control G2.2.37 Equipment Control G2.3.6 Radiation Control G2.3.7 Radiation Control SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 3.7 D D D D D D D D D D 4.0 4.7 D D D D D D D D D D 3.6 4.6 D D D D D D D D D D 2.0 3.8 D D D D D D D D D D 3.5 3.6 D D D D D D D D D D TOPIC: Knowledge of the refueling processes 3 FORM Knowledge of limiting conditions for operations and safety limits. Ability to determine operability and/or availability of safety related equipment Ability to aprove release permits Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.18 Emergency Procedures/Plans 3.3 4.0 D D D D D D D D D D Knowledge of the specific bases for EOPs. G2.4.3 Emergency Procedures/Plans 3.7 3.9 D D D D D D D D D D Ability to identify post-accident instrumentation.

Page 1 of 1 2111/2009 7:17 AM

/ ( ES-401 Tierl Group 1/1 2/2 2/2 3 Randomly Selected KIA 015 AK1.03 027 K1.01 033 A3.01 G 2.3.6 Record of Rejected KI As Watts Bar Nov. 2009 RO exam Reason for Rejection Reactor Coolant Pump (RCP) Malfunctions Form ES-401-4 Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow): AK1.03 The basis for operating at a reduced power level when one RCP is out of service. Replaced because Watts Bar procedures do not allow this operating configuration.

Replaced by Chief Examiner on 08/04/09 with KA AK1.02 Containment Iodine Removal System (CIRS) Knowledge of the physical connections andlor cause effect relationships between the CIRS and the following systems: CSS Replaced -Watts Bar CSS has no interface with the iodine removal function.

Replaced by Chief Examiner on 08/04/09 with KA K5.01 Spent Fuel Pool Cooling System (SFPCS) Ability to monitor automatic operation of the Spent Fuel Pool Cooling System including:

Temperature control valves Replaced because Watts Bar design is using manual valves only; there are no automatic temperature control valves for SFP cooling. . Replaced by Chief Examiner on 08/04/09 with KA A2.03 Ability to approve release permits. Replaced -per alignment with Chief Examiner, it is not feasible to write an operationally valid question for an RO to approve . release permits. Replaced by Chief Examiner on 08/04/09 with KA G2.3.4 ES-401 Record of Rejected KlAs Form ES-401-4 ( Watts Bar Nov. 2009 RO exam Tier/ Randomly Reason for Rejection Group Selected KIA 1/1 015 AK1.03 Reactor Coolant Pump (RCP) Malfunctions Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow): AK1.03 The basis for operating at a reduced power level when one RCP is out of service. Replaced because Watts Bar procedures do not allow this operating configuration.

Replaced by Chief Examiner on 08/04/09 with KA AK1.02 2/2 027 K1.01 Containment Iodine Removal System (CIRS) Knowledge of the physical connections and/or cause effect relationships between the CIRS and the following systems: CSS Replaced -Watts Bar CSS has no interface with the iodine removal function.

Replaced by Chief Examiner on 08/04/09 with KA K5.01 ( 2/2 033 A3.01 Spent Fuel Pool Cooling System (SFPCS) Ability to monitor automatic operation of the Spent Fuel Pool Cooling System including:

Temperature control valves Replaced because Watts Bar design is using manual valves only; there are no automatic temperature control valves for SFP cooling. Replaced by Chief Examiner on 08/04/09 with KA A2.03 3 G 2.3.6 Ability to approve release permits. Replaced -per alignment with Chief Examiner, it is not feasible to write an operationally valid question for an RO to approve release permits. Replaced by Chief Examiner on 08/04/09 with KA G2.3.4 (

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Watts Bar Date of Examination:

11/30/2009 Examination Level: RO 181 SRO 0 Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code* G 2.1.1 Knowledge of conduct of operations Conduct of Operations M,R .. requirements.

3.8 / 4.2 JPM: Determine License Status. G 2.1.25 Ability to interpret reference materials, such as Conduct of Operations N,R graphs, curves, tables, etc. 3.9/4.2 JPM: Perform RCS Deboration Calculation.

G 2.2.12 Knowledge of surveillance procedures.

3.7/4.1 Equipment Control N,R JPM: Perform 1-SI-0-2A-03, "1900-0700 Shift and " Daily Surveillance Log Mode Three. G 2.3.4 Knowledge of radiation exposure limits under Radiation Control D,R normal or emergency conditions.

3.2/3.7 JPM: Determine Potential Dose for Valve Alignment.

.. Emergency Procedures

/ --N/A 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, (S)imulator, or Class(R)oom (D)irect from bank (.::5. 3 for ROs; .::5. 4 for SROs & RO retakes) (N)ew or (M)odified from bank 1) (P)revious 2 exams (.::5. 1; randomly selected)

ES 301, Page 22 of 27 ES-301 Administrative Topics Outline Form ES-301-1 ( Facility:

Watts Bar Date of Examination:

11/30/2009 Examination Level: RO J:8J SRO D Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code* G 2.1.1 Knowledge of conduct of operations Conduct of Operations M,R requirements.

3.8/4.2 JPM: Determine License Status. G2.1.25 Ability to interpret reference materials, such as Conduct of Operations N,R graphs, curves, tables, etc. 3.9 1 4.2 JPM: Perform RCS Deboration Calculation.

G 2.2.12 Knowledge of surveillance procedures.

3.7/4.1 Equipment Control N,R JPM: Perform 1-SI-0-2A-03, "1900-0700 Shift and ( Daily Surveillance Log Mode Three. G 2.3.4 Knowledge of radiation exposure limits under Radiation Control D,R normal or emergency conditions.

3.21 3.7 JPM: Determine Potential Dose for Valve Alignment.

Emergency Procedures 1 --N/A 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, (S)imulator, or Class(R)oom (D)irect from bank 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 Administrative Topics Outline Form ES-301-1 Facility:

Watts Bar Date of Examination:

11/30/2009 Examination Level: ROO SRO (gj Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code* G 2.1.1 Knowledge of conduct of operations Conduct of Operations M,R requirements.

3.8 1 4.2 JPM: Determine License Status. G 2.1.25 Ability to interpret reference materials, such as Conduct of Operations D,R graphs, curves, tables, etc. 3.9 1 4.2 JPM: Review of Estimated Critical Position Calculation.

G 2.2.12 Knowledge of surveillance procedures.

3.71 4.1 Equipment Control N,R JPM: Review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three." G 2.3.4 Knowledge of radiation exposure limits under Radiation Control D,R normal or emergency conditions.

3.2 1 3.7 JPM: Determine Potential Dose for Valve Alignment.

G 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.

2.5/3.3 Emergency Procedures 1 M,R G 2.4.41 Knowledge of the emergency action level Plan thresholds and classifications.

2.9 14.6 JPM: Classify the Event and Determine PAR. NOTE: All items (5 total) are required forSROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank 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 220f 27 ES*301 Administrative Topics Outline Form ES*301*1 ( Facility:

Watts Bar Date of Examination:

11/30/2009 Examination Level: ROO SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code* G 2.1.1 Knowledge of conduct of operations Conduct of Operations M,R requirements.

3.8 / 4.2 JPM: Determine License Status. G 2.1.25 Ability to interpret reference materials, such as Conduct of Operations D,R graphs, curves, tables, etc. 3.9/4.2 JPM: Review of Estimated Critical Position Calculation.

G 2.2.12 Knowledge of surveillance procedures.

3.7/ 4.1 Equipment Control N,R JPM: Review 1-SI-0-2A-03, "1900-0700 Shift and ( Daily Surveillance Log Mode Three." , G 2.3.4 Knowledge of radiation exposure limits under Radiation Control D,R normal or emergency conditions.

3.2/3.7 JPM: Determine Potential Dose for Valve Alignment.

G 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.

2.5/3.3 Emergency Procedures

/ M,R G 2.4.41 Knowledge of the emergency action level Plan thresholds and classifications.

2.9 /4.6 JPM: Classify the Event and Determine PAR. NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:::. 3 for ROs; :::. 4 for SROs & RO retakes) (N)ew or (M)odified from bank 1) (P)revious 2 exams (:::. 1; randomly selected) ( ES 301, Page 22 of 27 \

. ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Watts Bar Date of Examination:

Nov-Dec 2009 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 (Bo/ded JPMs are SRO-U.) (Italicized JPM is RO only.) 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. Exercise Control Rods per 1-SI-85-2.

N 1 b. Perform FR-1.1,"High Pressurizer Level." A,M,L 2 c. Align RHR for Hot Leg Recirculation.

A,D,EN 3 d. Place Standby Main Feedwater Pump in service for Periodic Operation N 4S with Main Feedwater Pumps. e. Align CRDM Coolers. N 5 f. Reinstate Source Range following a Reactor Trip. A,M 7 g. Transfer 6.9 KV RCP Board 1 D from Alternate to Normal per SOI-202.01.

A,M 6 h. Swap CCS Pumps (place 18 in service, remove 1A from service).(RO Only) A,N 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Isolate The RCP Seal Injection And Thermal Barrier Per ECA-O.O. D,E,L,R 2 j. Align High Pressure Fire Protection (HPFP) to Centrifugal Charging Pump D,EN,R 8 1A-A Lube Oil Coolers. k. Align the Upper Containment Monitor to Lower Containment Locally. D,R 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 / (E)mergency or abnormal in-plant 1 / / 1 (EN)gineeredsafety feature -/ -/ 1 (L)ow-Power

/ Shutdown 1 / / 1 (N)ew or (M)odified from bank including 1 (A) / 1 (P)revious 2 exams / 2 (randomly selected) (R)CA 1 / / 1 (S)imulator ES-301, Page 23 of 27 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ( Facility:

Watts Bar Date of Examination:

Nov-Dec 2009 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 (Bolded JPMs are SRO-U.) (Italicized JPM is RO only.) 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. Exercise Control Rods per 1-SI-85-2.

N 1 b. Perform FR-1.1,"High Pressurizer Level." A,M,L 2 c. Align RHR for Hot Leg Recirculation.

A,D,EN 3 d. Place Standby Main Feedwater Pump in service for Periodic Operation N 4S with Main Feedwater Pumps. e. Align CROM Coolers. N 5 f. Reinstate Source Range following a Reactor Trip. A,M 7 g. Transfer 6.9 KV RCP Board 10 from Alternate to Normal per SOI-202.01.

A,M 6 h. Swap CCS Pumps (place 18 in service, remove 1A from service).(RO Only) A,N 8 ( In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Isolate The RCP Seal Injection And Thermal Barrier Per ECA-O.O. D,E,L,R 2 j. Align High Pressure Fire Protection (HPFP) to Centrifugal Charging Pump D,EN,R 8 1 A-A Lube Oil Coolers. k. Align the Upper Containment Monitor to Lower Containment Locally. O,R 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 / 4 (E)mergency or abnormal in-plant .=:: 1 / ,=::1 / .=:: 1 (EN)gineered safety feature -/ -/ > 1 (L)ow-Power

/ Shutdown .=:: 1 / .=::1 / .=::1 (N)ew or (M)odified from bank including 1 (A) .=::2/ .=::2 / .=:: 1 (P)revious 2 exams / 2 (randomly selected) (R)CA .=:: 1 / .=::1 / .=:: 1 (S)imulator ES-301, Page 23 of 27

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