ML092810413

Initial Exam 2009-301 Draft Administrative Documents

ML092810413
Person / Time
Site:	Watts Bar
Issue date:	10/08/2009
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
50-390/09-301, 50-391/09-301
Download: ML092810413 (17)

Text

ES*401 PWR Examination Outline Form ES*401*2 NRC Exam Facility: Watts Bar Date of Exam: May 2009 RO Tier RO KIA Category Points SRO-Only Points Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4

• 3 3 3 3 3 3 18

1. 1 Emergency N/A N/A 2 2 1 1 2 1 9

& Abnormal 2 Plant Tier Totals 5 5 4 4 5 4 27 Evolutions 3 2 2 3 3 3 2 3 2 2 3 28 1

2.

1 1 1 1 1 1 1 1 1 0 1 10 Plant 2 Systems Tier Totals 4 3 3 4 4 4 3 4 3 2 4 38

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 2 2 3 3 Note: 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 based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate 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) KlAs 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. Refer to Section D.1.b of ES-401 for the applicable KlAs.

s. 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 does not apply). Use duplicate pages for RO and SRO-onlyexams.

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. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

Note: This outline was provided by the Chief Examiner.

Watts Bar Nuclear Plant NRC Exam March 2009

ES-401 2 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Emeraenc and Abnormal Plant Evolutions - Tier 1/GrouD 1 eRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KIA Tooic(s) IR #

000008 Pressurizer Vapor Space 2.2.20 Knowledge of the process for managing 2.6 1 Accident/3 troublestiooting activities.

000009 Small Break LOCA / 3 03 Interrelations between SBLOCA and S/Gs. 3.0 1 000011 Large Break LOCA / 3 05 Operate/monitor man/auto transfer of charging 4.3 1 suction to borated source.

000015/17 RCP Malfunctions / 4 10 Interrelations between RCP malfunctions and 2.8 1 indicators/controls.

000025 Loss of RHR System /4 01 Reasons for shift to alternate flowpath as it applies to 3.1 1 LossofRHR.

000026 Loss of Component Cooling 04 Reasons for effect on CCW flow header of a loss of 3.5 1 CCW.

Water /8 000027 Pressurizer Pressure Control 03 Op implications of latent heat of vaporization. 2.6 1 System Malfunction / 3 000029 ATWS /1 12 Operate/monitor M/G set pwr supply & Rx trip brkrs. 4.1 1 000038 Steam Gen. Tube Rupture /3 03 Op implications of natural circulation. 3.9 1 000054 (CE/E06) Loss of Main 2.2.22 Knowledge of LCOs and safety limits. 4.0 1 Feedwater /4 000056 Loss of Offsite Power / 6 04 Implication of saturation conditions for the systems. 3.1 1 000057 Loss of Vital AC Elec. Inst. Bus 19 Determinelinterpret auto actions that occur. 4.0 1

/6 000058 Loss of DC Power / 6 02 Operate/monitor dc input brkr, freq. meter, ac output 3.1 1 detector and ground fault detector.

000062 Loss of Nuclear Service Water 01 Determinelinterpret location of a leak in the SWS 2.9 1

/4 000065 Loss of Instrument Air /8 03 Reasons for effects on plant ops of isolating certain 2.9 1 equipment from instrument air.

W /E04 LOCA Outside Containment / 3 Interrelations between LOCA outside containment 01 and comp'onents and functions of control and safety 3.5 1 s~tems, inc!. instrumentation, signals, interlocks, failure modes and auto and manual features.

W/E11 Loss of Emergency Coolant 01 Determine/interpret facility conditions and select 3.4 1 appropriate procedures.

Recirc./4 000040 (W/E12) Steam Line Rupture- 2.2.36 Analyze effect of maintenance activities on status of 3.1 1 LCOs.

Excessive Heat Transfer /4 3 3 3 3 3 3 18 KIA Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant NRC Exam March 2009

ES-401 3 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Emel encv and Abnormal Plant Evolutions - Tier 1/GrouD 2 IRQ)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KIA TODicls) IR #

000001 Continuous Rod Withdrawal/1 01 petermine/interpret reactor tripped brkr 4.2 1 IndIcator.

000003 Dropped Control Rod /1 Interpret indications to verify status and 2.2.44 operation of a s~tem, and ~erator actions 4.2 1 and directives a ecting con Itions.

000028 Pressurizer Level Malfunction / 2 01 Op implications of PZR ref. leak abnormalities 2.8 1 000033 Loss of Intermediate Range NI/ 7 Determine/interpret equivalency between 01 source range, intermeaiate range, and power 3.0 1 range channel readings 000059 Accidental Liquid RadWaste ReI. / 9 02 Interrelations with radioactive gas monitors 2.7 1 000076 High Reactor Coolant Activity /9 05 Reasons for corrective actions as a result of 2.9 1 high fission product rad level in RCS W/E08 RCS Overcooling - PTS /4 03 Operate/monitor desired operating results. 3.6 1 (W/E14) High Containment Pressure /5 Interrelations between Loss of CTMT Integri~

and components and functions of control an 01 safety systems, incl. instrumentation, signals, 3.4 1 interloci(s, failure modes and auto and manual features.

W/E15 Containment Flooding /5 02 Op implications of procedures 2.7 1 KIA Category Point Totals: 2 2 1 1 2 1 Group Point Total: 9 Watts Bar Nuclear Plant NRC Exam March 2009

ES-401 4 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Fonn ES-401-2 Plant Systems- Tier 2/Group 1 (RO System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Topic(s) IR #

02 Knowledge of pwr supplies 2.5 1 003 Reactor Coolant Pump to CCW pumps.

Im~acts of RCP seal 004 Chemical and Volume Control 05 fai ures on CVCS, and 4.0 1 procedures.

Imp of Keff by' means other 08 than 6-factor formula: 2.6 1 relationshi~ of count rate to reactivity c anges.

005 Residual Heat Removal 06 Effect of loss on CSS. 3.1 1 Manually o~erate/monitor 006 Emergency Core Cooling 05 transfer of CCS flowpaths 3.9 1 prior to recirculation.

01 Design/interlocks for 2.6 1 007 Pressurizer Relief/Quench Tank quench tank cooling 02 Method of fonnin~ steam 3.1 1 bubble in the PZ .

Sys. se4>Oints, interlocks, 008 Component Cooling Water 2.4.2 auto actions associated with 4.5 1 EOP entry conditions.

04 Effect of loss/malf. of PRT. 2.9 1 010 Pressurizer Pressure Control 01 Impacts of and rerocedures 3.1 1 for faulty bistab e operation.

012 Reactor Protection Local AO tasks during 2.4.35 emerg., including effects. 3.8 1 013 Engineered Safety Features 01 Power supplies to ESFAS 3.6 1 Actuation equipment control.

Monitor auto 0fes. of 022 Containment Cooling 01 initiation of sa eguards 4.1 1 mode.

02 Connections/cause & effect 2.7 1 with refrigerant systems.

025 Ice Condenser 02 Features/interlocks for 2.8 1 system control.

Featureslinterlocks for rad 026 Containment Spray 09 release (interlock on RWST 3.7 1 isol. after swapover).

02 Monitor auto operation of 3.1 1 039 Main and Reheat Steam MRSS isolation.

03 Impacts of and procedures 2.7 1 059 Main Feedwater for overfeeding event.

I~lications of pp. head 061 Auxiliary/Emergency Feedwater 03 e ects when control vlv 2.6 1 shut.

2.4.11 Knowledge of abnormal 4.0 1 062 AC Electrical Distribution procedures.

01 Effects on battery capacity 2.5 1 063 DC Electrical Distribution of discharge rate.

07 Effects of loss of air rcvrs. 2.7 1 064 Emergency Diesel Generator 08 Effects of loss of fuel tanks. 3.2 1 073 Process Radiation Monitoring 01 Effect of loss/malf. on 3.6 1

.. releases .

076 Service Water Predict chan~es associated 02 with reactor turbo bldg. 2.6 1 closed cooling water temps.

01 Monitor pressure gauges. 3.1 1 078 Instrument Air 01 Relations with sensor air. 2.8 1 103 Containment 01 Relations with CCS 3.6 1 3 2 2 3 3 3 2 3 2 2 3 28 KIA Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant NRC Exam March 2009

ES-401 5 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Plant Svstems- Tier 2/Grouo 2 (RO SYStem # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Tooic(s) IR #

001 Control Rod Drive 03 Effect of loss on reactor trip 3.7 1 breakers.

002 Reactor Coolant 03 Effect of loss/malf. on 4.2 1 containment.

016 Non-nuclear 01 Separation of control and 2.7 1 Instrumentation protection circuits.

017 In-Core Temperature 01 3.2 1 Monitor Relationship with plant computer.

027 Containment Iodine 01 3.1 1 Removal Power supplies to fans.

033 Spent Fuel Pool Cooling 01 Design features for spent fuel 2.9 1 level.

034 Fuel Handling Equipment 02 Monitor water level in refuel canal 2.9 1 045 Main Turbine Generator 2.2.37 Determine operability/availability 3.6 1 of safety related equipment.

068 Liquid Radwaste 02 Monitor automatic isolation. 3.6 1 072 Area Radiation Monitoring 01 Im~acts/procedures of erratic or 2.7 1 fai ed power supply.

1 1 1 1 1 1 1 1 1 0 1 10 KIA Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant NRC Exam March 2009

ES*401 Generic Knowledge and Abilities Outline (Tier 3) Form ES*401*3 NRC EXAM Facility: Watts Bar Date of Exam: May 2009 RO Category KIA # Topic RO SRO-Only IR # IR #

2.1.4 Operator responsibilities for shift staffing. 3.3 1 2.1.42 New and spent fuel movement procedures. 2.5 1 1.

Conduct of Operations Subtotal 2 2.2.20 Process for managing troubleshooting activities. 2.6 1 2.2.21 Pre- and post-maintenance operability requirements. 2.9 1 2.

Equipment Control Subtotal 2 2.3.12 Radiological safety principles pertaining to licensed operator 3.2 1 duties.

2.3.14 Knowledge of radiation or contamination hazards. 3.4 1 3.

Radiation 2.3.15 Radiation monitoring systems. 2.9 1 Control Subtotal 3 2.4.9 Low power/shutdown implications in accident mitigation. 3.8 1 2.4.19 EOP layout, symbols and icons. 3.4 1 4.

Emergency 2.4.27 Knowledge of fire in the plant procedures. 3.4 1 Procedures /

Plan Subtotal 3 Tier 3 Point Total 10 Note: This outline was provided by the Chief Examiner.

ES-401 PWR Examination Outline Form ES-401-2 Facility: Watts Bar Date of Exam: May 2009 SRO Tier RO KIA Category Points SRO-Only Points Group K K K K K K A A A A G Total A2. G* Total 1 2 3 .4 5 6 1 2 3 4

• 3 3 6

1. 1 Emergency N/A N/A 2 2 4

& Abnormal 2 Plant 5 5 10 Evolutions Tier Totals 2 3 5 1

2.

2 1 2 3 Plant Systems Tier Totals 3 5 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 1 2 2 2 Note: 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 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/evolutjons that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate 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) KlAs 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. Refer to Section D.1.b of ES-401 for the applicable KlAs.

B. 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 does not apply). Use duplicate pages for RO and SRO-onlyexams.

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. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

Note: This outline was provided by the Chief Examiner.

Watts Bar Nuclear Plant NRC Exam May 2009 Page 1 of 5

ES-401 2 Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Emenencv and Abnormal Plant Evolutions - Tier 1/GrouD 1 (SRQ)

E/APE # I Name I Safetv Function K1 K2 K3 A1 A2 G KIA TODicls) IR #

000008 Pressurizer Vapor Space 2.1.20 Interpret and execute procedure steps. 4.6 1 Accident I 3 000011 Large Break LOCA I 3 01 Determine actions, based on RCS temperature and 4.7 1 pressure.

000025 Loss of RHR System 14 06 DetelTT!ine existence of proper RHR overpressure 3.4 1 protection.

000056 Loss of Offsite Power I 6 2.4.45 Prioritize and interpret the significance of each 4.3 1 annunciator or alarm.

000065 Loss of Instrument Air I 8 03 Location and isolation of leaks. 2.9 1 W IE04 LOCA Outside Containment I 3 2.4.21 Parameters and logic used to assess the status of 4.6 1 safety functions.

3 3 6 KIA Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant Exam May 2009 Page 2 of5

ES*401 3 Form ES*401*2 ES-401 PWR Examination Outline Form ES-401-2 Emeraencyand Abnormal Plant Evolutions - Tier 1/GrouD 2 (SRQ)

E/APE # 1 Name 1 Safety Function K1 K2 K3 A1 A2 G KIA TODic(s) IR #

0000028 Pressurizer Level Malfunction 12 01 Interpret PZR level indicators and alarms. 3.6 1 000076 High Reactor Coolant Activity 1 9 02 Determine corrective actions for high reactor 3.4 1 coolant activity.

W IE03 LOCA Cooldown - Depress. 1 4 2.4.30 Events that must be reported to internal 4.1 1 organizations or external agencies.

W/E10 Natural Circ. With Steam Void 14 2.2.37 Determine op.erability and/or availability of 4.6 1 safety relatea equipment.

KIA Category Point Totals: 2 2 Group Point Total: 4 Watts Bar Nuclear Plant Exam May 2009 Page 3 of5

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S\ stems- Tier 2/Grou 1 (SRO)

SYStem # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Tooic(s) IR #

" ""/

03 Impacts of and procedures 3.1 1 005 Residual Heat Removal for motor/pump malf.

Obtain and inter:pret 008 Component Cooling 2.4.41 station electrical and 4.6 1 Water mechanical drawings.

2.2.38 Conditions and limitations 4.5 1 026 Containment Spray in the facility license.

06 Ke~ing safeguards buses 3.9 1 062 AC Electrical Distribution ele rically separate.

Determine 0p.erabiliJ:y 063 DC Electrical Distribution 2.2.37 and/or availability of safety 4.6 1 related equipment.

KIA Category Point Totals:

2 3 Group Point Total:

~I Watts Bar Nuclear Plant Exam May 2009 Page 4 of 5

ES-401 5 Form ES-401-2

~,..

ES-401 PWR Examination Outline F Plant Systems- Tier 2/Group 2 (SRO)

System # I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KIA Topic(s) IR #

028 Hydrogen Recombiner Perform without reference to and Purge Control 2.4.49 procedures immediate 4.4 1 operation of components and controls.

055 Condenser Air Removal Use plant computers to 2.1.19 evaluate system or component 3.8 1 status.

079 Station Air 01 Cross connection with lAS. 3.2 1 1 2 3 KIA Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant Exam May 2009 Page 5 of 5

ES*401 Generic Knowledge and Abilities Outline (Tier 3) Form ES*401*3 NRC EXAM Facility: Watts Bar Date of Exam: May 2009 SRO Category KIA # Topic SRO-Only IR #

2.1.8 Coordinate activities outside the control room. 4.1 1.

Conduct of Operations Subtotal 2.2.15 Determine expected plant configuration using documents.

2.2.42 System parameters that are Tech Spec entry conditions. 4.6 2.

Equipment Control Subtotal 2 2.3.4 Radiation exposure limits.

2.3.15 Knowledge of radiation monitoring systems. 3.1 3.

Radiation Control Subtotal 2 2.4.35 Local AO emergency tasks and operational effects.

2.4.38 Take actions of EPlan, inc!. emergency coordinator. 4.4 4.

Emergency Procedures /

Plan Subtotal 2 Tier 3 Point Total 7 Note: This outline was provided by the Chief Examiner.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: 05/18/2009 Examination Level: RO~ SRO 0 Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

2.1.7 Ability to evaluate plant performance and make operational judgments based on operating Conduct of Operations R,M characteristics, reactor behavior, and instrument interpretation.

Calculate Shutdown Margin 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Conduct of Operations R,M Calculate Target Boron Concentration for Load Escalation Using Appendix E of 501-62.02.

2.2.40 Ability to apply Technical Specifications for a Equipment Control R,M system.

Perform a QPTR Calculation per 0-51-0-21.

Radiation Control - ---

2.4.39 Knowledge of RO responsibilities in emergency Emergency Procedures 1 plan implementation.

R,D Plan Perform Control Room Operator Medical Response Checklist.

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 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: 05/18/2009 Examination Level: ROO SRO ~ Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument Conduct of Operations R,M interpretation.

Perform Technical Review of Shutdown Margin Calcu lation.

2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Conduct of Operations R,M Perform Independent Verification of Target Boron Concentration for Load Escalation Calculation.

2.2.24 Knowledge of the process used to track Equipment Control R,N inoperable alarms.

Review/Approve Disabled Alarm Checklist.

2.3.6 Ability to approve release permits.

Radiation Control R,N Review/Approve Liquid Release Permit.

2.4.41 Knowledge of the emergency action level Emergency Procedures / thresholds and classifications.

R,D Plan Classify an Event (High RCS Activity, SGTRlFauited SG).

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: May 2009 Exam Level: RO ~ SRO-I 0 SRO-U 0 Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System I JPM Title Type Code*

Function

a. Withdraw Shutdown Banks. ALMS 1

b. Place Excess Letdown in Service. DC 2

c. Isolate Cold Leg Accumulators. AENS 3

d. Place RHR Spray in Service. ADLS 4P

e. Place the Containment H2 Recombiner in Service. DLS 5

f. Synchronize DIG from Main Control Room. MS 6

g. Return Power Range Monitor to Service. ADS 7

h. Shutdown A Train Emergency Gas Treatment System. OS 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Perform Local Boration of RCS. AELMR 1

j. Local Isolation of Steam Lines Following a SGTR. MEL 3

k. Place Cation Bed in Service for High RCS Activity. MER 9

@ 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 I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank ~91 ~8 I ~4 (E)mergency or abnormal in-plant ~ 1 I ~1 I ~ 1 (EN)gineered safety feature - I - I ~1 (L)ow-Power I Shutdown ~1 I ~1 I ~ 1 (N)ew or (M)odified from bank including 1(A) ~21 ~2 I ~ 1 (P)revious 2 exams ~3 ~ 3 I ~ 2 (randomly selected)

(R)CA ~1 I ~1 I ~ 1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: May 2009 Exam Level: RO 0 SRO-I [gI SRO-U 0 Operating Test Number: 1 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. Withdraw Shutdown Banks. ALMS 1

b. Place Excess Letdown in Service. DC 2

c. Isolate Cold Leg Accumulators. AENS 3

d. Place RHR Spray in Service. ADLS 4P

e. Place the Containment H2 Recombiner in Service. DLS 5

f. (Not required for I-SRO). - -

g. Return Power Range Monitor to Service. ADS 7

h. Shutdown A Train Emergency Gas Treatment System. DS 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Perform Local Boration of RCS. AELMR 1

j. Local Isolation of Steam Lines Following a SGTR. MEL 3

k. Place Cation Bed in Service for High RCS Activity. MER 9

@ 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 (L)ow-Power / Shutdown ~ 1 / ~1 / ~1 (N)ew or (M)odified from bank including 1(A) ~2/ ~2 / ~1 (P)revious 2 exams ~3 ~ 3 / ~ 2 (randomly selected)

(R)CA ~ 1 / ~1 / ~1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: May 2009 Exam Level: RO 0 SRO-I 0 SRO-U ~ Operating Test Number: 1 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. (Not required for U - SRO). - -

b. (Not required for U - SRO). - -

c. Isolate Cold Leg Accumulators. AENS 3

d. (Not required for U - SRO). - -

e. Place the Containment H2 Recombiner in Service. DLS 5

f. (Not required for U - SRO). - -

g. Return Power Range Monitor to Service. ADS 7

h. (Not required for U - SRO). - -

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Perform Local Boration of RCS. AELMR 1

j. (Not required for U - SRO). - -

k. Place Cation Bed in Service for High RCS Activity. MER 9

@ 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 (L)ow-Power / Shutdown ~ 1 / ~1 / ~1 (N)ew or (M)odified from bank including 1(A) ~2/ ~2 / ~ 1 (P)revious 2 exams ~3 ~3 / ~ 2 (randomly selected)

(R)CA ~ 1 / ~1 / ~1 (S)imulator ES-301, Page 23 of 27