ML110140247

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Initial Exam 2010-301 Draft Administrative Documents
ML110140247
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 10/19/2010
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
50-390/10-301
Download: ML110140247 (21)
v • d • e


Text

ES-401, Rev. 9E PWR Examination Outline Form ES-401-2 Facility: Watts Bar 201 0-301 August 2010 RO K/A Category Points SRO-Only Points Tier Group KKKKKKAAAAG 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 &

Abnormal Plant 2 1 2 1 N/A 1 2 N/A 2 9 2 2 4 Evolutions Tier Totals 4 5 4 4 5 5 27 5 5 10 1 33222333322 28 3 2 5 2.

Plant 2 11110111102 10 1 1 1 3 Systems TierTotals 44332444424 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 2 2 2 1 Note:1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/- 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
e. Absent a plant-specific priority, only those K/As having an importance rating (lR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G on the SRO only exam, enter it on the left side of Column A2 for Tier 2, Group 2. Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

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ES-401, Rev. 9 2 Form ES-401 -2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnomial Plant Evolutions - Tier 1/Group 1 (RO / SRO)

EJAPE #1 Name / Safety Function K K K A A G K/A Topic(s) IR 12312 007EK3.01 Knowledge of the reasons for the 000007 (BW/E02&E10; CE/E02) Reactor Trip X 4.04.

/ 6 following as the apply to a reactor trip: Actions

- Stabilization - Recovery! 1 contained in EOP for reactor trip 008AK2.O1 Knowledge of the interrelations 000008 Pressurizer Vapor Space Accident! 3 X 2 7 /2 7 between the Pressurizer Vapor Space Accident and the following Valves 009EA2 23 Ability to determine or interpret the 000009 Small Break LOCA /3 X following as they apply to a small break LOCA 2 8/3 3 RCP operating parameters and limits 011 EK2.02 Knowledge of the interrelations 000011 Large Break LOCA / 3 X between the and the following Large Break 2.6 / 2. 7 LOCA: Pumps: CVCS letdown and charging 000015/17 RCP Malfunctions!4 022AA1 .01 Ability to operate and I or monitor the 000022 Loss of Rx Coolant Makeup! 2 X following as they apply to the Loss of Reactor Coolant Makeup: How long PZR level can be maintained within limits 022AA2.04 Ability to determine and interpret the 000022 Loss of Rx Coolant Makeup / 2 (SRO) X 2.93. 8 following as they apply to the Less of Reactor Coolant Makeup:

025AG2.1.7 Loss of RHR system; Abilityto 000025 Loss of RHR System /4 X evaluate plant performance and make 44/4 7 operational judgments based on operating characteristics, reactor behavior, and instrument interpretation 025AA2 03 Ability to determine and interpret the 000025 Loss of RHR System 4 (SRO) X 3 6/3 following as they apply to the Loss of Residual Heat Removal System Increasing reactor building sump level 000026 Loss of Component Cooling Water! 8 027AA2.09 Ability to determine and interpret the -

000027 Pressurizer Pressure Control System X 336 following as they apply to the Pressurizer Malfunction / 3 (SRO)

Pressure Control Malfunctions: Reactor power 029EA1 .08 Ability to operate and monitor the 000029 ATWS! 1 X following as they apply to a ATWS: Reactor Trip switch pushbutton 038EK1 .03 Knowledge of the operational 000038 Steam Gen. Tube Rupture /3 X implications of the following concepts as they 3 9/4 2 apply to the SGTR: Natural circulation O4OAK1 .05 Knowledge of the operational 000040 (BW/E05; CEJEO5; W/E12) Steam X 414 4 implications of the following concepts as Line Rupture Excessive Heat Transfer /4 they apply to Steam Line Rupture: Reactivity effects of cooldown

054AG2.1.23 Loss of Main Feedwater- Ability to 000054 (CE/E06) Loss of Main Feedwater /4 X perform specific system and integrated plant procedures during all modes of plant operation.

055EK3.02 Knowledge of the reasons for the 000055 Station Blackout / 6 X following responses as the apply to the Station 43/46 Blackout: Actions contained in EOP for loss of offsite and onsite power 056AG2.4.41 Knowledge of the emergency 000056 Loss of Off site Power / 6 (SRO) X 2 9/4 6 action level thresholds and classifications 057AG2.4.1 Knowledge of EOP entry conditions 000057 Loss of Vital AC Inst. Bus /6 X and immediate action steps. 4.6/4.8 058AA2.02 Ability to determine and interpret the 000058 Loss of DC Power /6 X 3.3/3.6 following as they apply to the Loss of DC Power: 1 25V dc bus voltage, low/critical low, alarm 062AA2.03 Ability to determine and interpret the 000062 Loss of Nuclear Svc Water/ 4 X 2.6/2.9 following as they apply to the Loss of Nuclear Service Water The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition 065AK3.03 Knowledge of the reasons for the 000065 Loss of Instrument Air /8 X 2.9/3.4 following responses as they apply to the Loss of Instrument Air: Knowing effects on plant operation of isolating certain equipment from instrument air 065G2.4.21 Knowledge of the parameters and 000065 Loss of Instrument Air / 8 (SRO) X logic used to assess the status of safety 4.0/46 functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity containment conditions radioactivity release control etc 000077 Generator Voltage and Electric Grid Disturbances / 6 WEO4EK1 .3 Knowledge of the operational W/E04 LOCA Outside Containment / 3 X implications of the following concepts as they 3.5/3.9 apply to the (LOCA Outside Containment)

Annunciators and conditions indicating signals, and remedial actions associated with the (LOCA Outside Containment).

W!E1 I Loss of Emergency Coolant Recirc. /4 X WE1 1 EG2.1 .30 Ability to locate and operate 4.4/4.0 components, including local controls.

(SRO)

BW/E04 W/E05 Inadequate Heat Transfer Loss of Secondary Heat Sink / 4 W/E05 Inadequate Heat Transfer Loss of X WEO5EA1 2 Ability to operate and I or monitor 3 7/40 Secondary Heat Sink/ 4 the following as they apply to the (Loss of Secondary Heat Sink) Operating behavior characteristics of the facility.

WE1 1 EK2.1 Knowledge of the interrelations WE1 1; Loss of Emergency Coolant X between the (Loss of Emergency Coolant 3.6/3.9 Recirculation Recirculation) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

K/A Category Totals: 3 3 3 3 3 3 Group Point Total: i8 SRO K/A Category Totals: = = = = 3 3 Group Point Total: s

ES-401, Rev. 9 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401 -2 Emergency and Abnormal Plant Evolutions- Tier 1/Group 2 (RO / SRO)

EIAPE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 X 003AG2.4.1 Knowledge of EOP entry 4.6/4.8 conditions and immediate action steps.

000005 Inoperable/Stuck Control Rod / 1 X OO5AK1 .05 Knowledge of the operational 3.3/4.1 implications of the following concepts as they apply to Inoperable! Stuck Control

, Rod: Calculation of minimum shutdown margin 005AG2.132 Ability to explain and apply 000005 Inoperable/Stuck Control Rod! 1 (SAD> 38/4.0 system limits and precautions.

000024 Emergency Boration / 1 (SAD) 024AA2.03 Ability to determine and 29/3.0 interpret the following as they apply to the Emergency Boration: Correlation between boric acid controller setpoint and boric acid flow 000028 Pressurizer Level Malfunction / 2 032AK2.01 Knowledge of the 000032 Loss of Source Range NI / 7 X 2.7/3.1 interrelations between the Loss of Source Range Nuclear Instrumentation and the following: Power supplies, including proper switch positions X 033AA2.03 Ability to determine and 000033 Loss of Intermediate Range NI I7 2.8/3.1 interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation: Indication of blown fuse 000036 (BW/A08) Fuel Handling Accident /8 X 036AG2.4.46 Ability to verify that the 4.2/4.2 alarms are consistent with the plant conditions.

000037 Steam Generator Tube Leak! 3 037AA1 .04 Ability to operate and I or 3.6/3.9 monitor the following as they apply to the Steam Generator Tube Leak:

Condensate air ejector exhaust radiation monitor and failure indicator 000051 Loss of Condenser Vacuum /4 000059 Accidental Liquid RadWaste Rel. /9

000060 Accidental Gaseous Radwaste Rd. / 9 (SRO) X 060AG2.4.3 Ability to identify post- 3.7/3.9 accident instrumentation.

061AK2.01 Knowledgeof the 000061 ARM System Alarms /7 X 2.5/2.6 interrelations between the Area Radiation Monitoring (ARM) System Alarms and the following: Detectors at each ARM system location 061AA2.01 Abilityto determine and 000061 ARM System Alarms/7 (SRO) interpret the following as they apply to the Area Radiation Monitoring (ARM)

System Alarms: ARM panel displays 000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. /8 000069 (W!E14) Loss of CTMT Integrity! 5 000074 (W/E06&E07) mad. Core Cooling! 4 000076 High Reactor Coolant Activity / 076AA2.03 Ability to determine and 2.5/3.0 interpret the following as they apply to the High Reactor Coolant Activity: RCS radioactivity level meter W!EO1 & E02 Rediagnosis & SI Termination I 3 WEO2EK3.1 SI Termination: Facility X operating characteristics during transient 3.3/3.6 conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

W!E13 Steam Generator Over-pressure / 4 W!E15 Containment Flooding / 5 W!E16 High Containment Radiation! 9 BW!A01 Plant Runback /

BW!A02&A03 Loss of NNI-XJY / 7 -

BW!A04 Turbine Trip I 4 BW!A05 Emergency Diesel Actuation / 6 BW!A07 Flooding! 8 -

BW!E03 Inadequate Subcooling Margin / 4 -

BW!E08; W!E03 LOCA Cooldown Depress. /4 BW!E09; CEJA13; W/E09&E10 Natural Circ. /4 SW/El 3&E14 EOP Rules and Enclosures

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ES-401, Rev. 9 4 Form ES-401 -2 ES-401 PWR Examination Outline Form ES-401 -2 Plant Systems Tier 2/Group i(RO / SRO)

System #1 Name K K K K K K A A A A G K/A Topic(s) IR #

1234561234 003K5.04 Knowledge of the operational 003 Reactor Coolant Pump X 3 2/3 5 implications of the following concepts as they apply to the RCPS: Effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow, and feed flow 003K6.14 Knowledge of the effect of a 003 Reactor Coolant Pump X 2.6/2.9 loss or malfunction on the following will have on the RCPS: Starting requirements 003A2.03 Ability to (a) predict the 003 Reictor Coohnt Pump (SRO) X impacts of the following malfunctions or 273 1 operations on the RCPS; and (b) based on those predictions use procedures to correct, control or mitigate the consequences of those malfunctions or operations: Problems associated with RCP motors ncluding faulty motors and current, and winding and bearing temperature problems 004K6.36Knowledge of the physical 004 Chemical and Volume Control X connections anciior cause-effect 2.6/2.8 relationships between the CVCS and the following systems: CCWS 005K5.01 Knowledge of the operational 005 Residual Heat Removal X implications of the following concepts 2.6/2.9 as they apply the RHRS Nil ductility transition temperature (brittle fracture) 005A2.01 Ability to (a) predict the 005 Residual Heat Removal (SRO) X impacts of the following malfunctions or 2 F2 S operations on the RHRS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation 006K2.01 Knowledge of bus power 006 Emergency Core Cooling X supplies to the following: ECCS pumps 36/39 006K6 13 Knowledge of the effect of a 006 Emergency Core Cooling X loss or malfunction on the following will have on the ECCS Core flood tanks (accumulators)

007A1 .01 Ability to predict and/or monitor 007 Pressurizer Relief/Quench Tank X changes in parameters (to prevent 2.9/3.1 exceeding design limits) associated with operating the PRTS controls including:

Maintaining quench tank water level within limits 008A2 05 Ability to (a) predict the 008 Component Cooling Water X 3 impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: Effect of loss of instrument and control air on the position of the CCW valves that are air operated; 008A4.loAbilitytomanuallyoperate 008 Component Cooling Water X 3 1/3 1 and/or monitor in the control room Conditions that require the operation of two CCW coolers 010A3.10 Ability to monitor automatic 010 Pressurizer Pressure Control X 0/3 2 operation of the PZR PCS, including PRT 3 temperature and pressure during PORV testing 01 2K1 .05 Knowledge of the physical 012 Reactor Protection X connections an&or cause effect 3.8/3.9 relationships between the RPS and the following: ESFAS 012 Reactor Protection 013G2.4.6 Knowledge of EOP mitigation 013 Engineered Safety Features X strategies.

Actuation 013G22 12 Knowledge of surveillance 013 Engineered Safety Features X procedures 3 7/4 1 Actuation (SRO) 022G2.2.36 Ability to analyze the effect 022 Containment Cooling X 3.1/4.2 of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

025K1 .01 Knowledge of the physical 025 Ice Condenser X 2.7/2.7 connections anchor cause- effect relationships between the ice condenser system and the following systems Containment ventilation 026A4 05 Ability to manually operate 026 Containment Spray X and/or monitor in the control room 3 53 5 Containment spray reset switches

039K3.04 Knowledge of the effect that a 039 Main and Reheat Steam X loss or malfunction of the MRSS will 2.5/2.6 have on the following: MFW pumps 059K3.02 Knowledge of the effect that a 059 Main Feedwater X loss or malfunction of the MFW will 36/37 have on the following: AFW system 059A203 Ability to (a) predict the 059 Main Feedwater X impacts of the following malfunctions or 2.7/3.1 operations on the MFW; and (b) based on those predictions, use procedures to correct control, or mitigate the consequences of those malfunctions or operations: Overfeeding event 061A1 04 Ability to predict and/or 061 Auxiliary/Emergency Feedwater X monitor changes in parameters (to 2 6/2 7 prevent exceeding design limits) associated with operating the AFW controls including: AFW source tank level 062A3.05 Ability to monitor automatic 062 AC Electrical Distribution X operation of the ac distribution system, 3.5/3.6 including: Safety-related indicators and controls 062K2.01 Knowledge of bus power suppli 062 AC Electrical Distribution X to the following Major system loads 3 4 063A1 01 Ability to predict and/or 063 DC Electrical Distribution X monitor changes in parameters 2 5/3 3 associated with operating the DC electrical system controls including:

Battery capacity as it is affected by discharge rate 063A2.01 Ability to (a) predict the 063 DC Electrical Distribution X impacts of the following malfunctions or 2.5/3.2 operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Grounds 064K1 .03 Knowledge of the physical 064 Emergency Diesel Generator X connections and/or cause-effect 3.6/4.0 relationships between the EDIG system and the following systems: Diesel fuel oil supply system 064K4.03 Knowledge of EDIG system 064 Emergency Diesel Generator X design feature(s) and/or inter lock(s) 2 5/3 0 which provide for the following:

Governor valve operation

073K4.02 Knowledge of PRM system 073 Process Radiation Monitoring X design feature(s) andlor interlock(s) 331:39 which provide for the following: Letdown isolation on high-RCS activity 076A2.01 Ability to (a) predict the 076 Service Water X 35,/37 impacts of the following mal-functions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations Loss of SWS 078K2.02 Knowledge of bus power 078 Instrument Air X supplies to the following Emergency air a 5 compressor 078G2.4.4 Ability to recognize abnormal 078 Instrument Air (SRO) X indications for system operating parameters that are entry level conditions for emergency and abnormal operating procedures.

1 03A3.O1 Ability to monitor automatic 103 Containment X operation of the containment system, 3942 including: Containment isolation K/A Category PointTotals: 3 3 21212 3 3 3 3 2 I 2 I Group PointTotal:

K/A Category Point Totals: (SRO) = = = = = ..

= I I 2 Group Point Total: 5

ES-401, Rev. 9 5 Form ES-401 -2 ES-401 PWR Examination Outline Form ES-401-2 Systems Tier 2/Group 2 (RO I SRO)

System #1 Name K K K K K K A A A A G KJA Topic(s) IR 1 234561234 001 Control Rod Drive 002K6.07 Knowledge of the effect or a 002 Reactor Coolant X loss or malfunction on the following 2.5/2.8 RCS components: Pumps 01 1 Pressurizer Level Control 014A1.04 Ability to predict and/or 014 Rod Position Indication X monitor changes in parameters (to 5/3 8 prevent exceeding design limits) associated with operating the RPIS controls, including: Axial and radial power distribution 015 Nuclear Instrumentation X 015A3.03 Ability to monitor automatic 3.9/3.9 operation of the NIS, including:

Verification of proper functioning/operability 01 6K3.06 Knowledge of the effect that a 016 Non nuclear Instrumentation X loss or malfunction of the NNIS will have on the following AFW system 017 In-core Temperature Monitor 028 Hydrogen Recombiner and X 028K2.01 Knowledge of bus power 2.5/2.8 Purge Control supplies to the following: Hydrogen recombiners.

029 Containment Purge 033 Spent Fuel Pool Cooling 034K5 03 Knowledge of the operational 034 Fuel Handling Equipment X implication of the following concepts as 2 112 7 (SRO) they apply to the Fuel Handling System:

Residual heat removal; decay 035 Steam Generator X 035G2.1 .20 Ability to interpret and 4.6/4.6 execute procedure steps.

041 A2.03 Ability to (a) predict the 041 Steam Dumprruibine Bypass X 2 8/3 1 impacts of the following malfunctions or Control (SRO) operations on the SDS and (1) based on those predictions or mitigate the consequences of those malfunctions or operations: Loss of AS 045 Main Turbine Generator 055 Condenser Air Removal

056 Condensate X 056G2 1 32 Ability to explain and apply 38/40 system limits and precautions 068 Liquid Radwaste 071 Waste Gas Disposal 072K4.03 Knowledge of ARM system 072 Area Radiation Monitoring X design feature(s) and/or interlock(s) 3 2/3 6 which provide for the following: Plant ventilation systems 075 Circulating Water 079K1 .01 Knowledge of the physical 079 Station Air X connections and/or cause effect 3 0/3 1 relationships between the SAS and the following systems lAS 079G2.1 .20 Ability to interpret and 079 Station Air (SRO) X execute procedure steps 646 086A2.04 Ability to (a) predict the 086 Fire Protection X impacts of the following malfunctions or operations on the Fire Protection System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations Failure to actuate the FPS when required, resulting in fire damage KJA Category PointTotals 1 1 1 1 0 1 1 i ii 1 ol 21 Group PointTotal KIA Category Point Totals: (SRO) = = = = = 1 I 1 I I i Group Point Total: 3

Facility: Watts Bar Date of Exam: 8/23/2010 2010-301 RO SRO-Only Category K/A # Topic IR Q# IR Q#

Knowledge of administrative requirements for temporary management directives, such as 2.1.15 standing orders, night orders, Operations 2.7 3.4 memos, etc.

Ability to make accurate, clear, and concise logs, records, status boards, and reports. 3.6 3.8 2.1.18 Conduct of Ability to identify and interpret diverse indications Operations 2.1.45 to validate the response of another indication. 4.3 4.3 2.1.21 Ability to verify the controlled procedure copy. 3.6 Ability to coordinate personnel activities outside 2 1 8 4 the control room.

Subtotal 3 2 Ability to determine the expected plant configuration using design and configuration 22.15 control documentation, such as drawings, line- 3.9 4.3 ups, tag-outs, etc.

Knowledge of the process for managing maintenance activities during shutdown

2. 2.2.18 operations, such as risk assessments, work 2.6 3.8 Equipment Control prioritization, etc.

Knowledge of the process used to track inoperable alarms.

Knowledge of the process for conducting special 22 7 6 or infrequent tests.

Subtotal 2 2 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable 2.3.5 survey instruments, personnel monitoring 2.9 2.9 equipment, etc.

Ability to control radiation releases.

2.3.11 3.8 4.3 Knowledge of radiation monitoring systems,

3. such as fixed radiation monitors and alarms, Radiation Control 2.3.15 portable survey instruments, personnel 3.1 monitoring equipment, etc.

Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable 2.3.5 survey instruments, personnel monitoring 2.9 equipment, etc.

Subtotal 2 2

Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, 2.4.16 3.5 4.4 abnormal operating procedures, and severe accident management guidelines.

Knowledge of RO tasks performed outside the main control room during an emergency and the 2 4 34 42 41

. resultant operational effects.

4. Knowledge of local auxiliary operator tasks Emergency during an emergency and the resultant Procedures / Plan 2.4.35 3.8 4.0 operational effects.

Knowledge of emergency plan protective action 2.4.44 recommendations. 4.4 Subtotal 3 Tier 3 Point Total 10 7

\.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: August 2010 Examination Level: RO SRO E Operating Test Number: Exam 1 Administrative Topic Tvne

  • Describe activity to be performed (See Note) Code A.1-1 Determine Values for Raising RWST Level.

Conduct of Operations M, R 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (41.10 / 43.5 / 45.2 / 45.6) 4.3/4.4.

A.1-2 Determine Protective Clothing for Electrical Arc Flash Protection and Pre-Job Briefing Requirements.

Conduct of Operations N, R 2.1 .26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen). (41.10 /45.12)3.4/3.6.

A.2 Perform 1-SI-0-4, Monthly Surveillances, for the Auxiliary Control Room.

Equipment Control M, S 2.2.12 Knowledge of surveillance procedures. (41.10/

45.13) 3.7/4.1.

A.3 Determine if Stay Times Exceed Emergency Exposure Limits.

Radiation Control M, R 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (41.12 I 43.4 /45.10) 3.2/3.7.

Emergency Procedures /

Plan Not Required.

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 RO Admin JPM Summary Al-i The applicant performs the calculations necessary to determine the amount of primary water, and the amount of boric acid solution required to raise RWST volume by 3000 gallons while maintaining a 3100 ppm concentration in the RWST.

A.1-2 The applicant determines the minimum protective clothing requirements for swapping a specific breaker in preparation for a test, and the pre-job briefing requirements per OPDP-1, Conduct of Operations.

A.2 The applicant completes specified portions of 1-Sl-0-4, Monthly Surveillances, and determines that two parameters do not meet Technical Specifications and one parameter requires calibration per the surveillance.

A. 3 The applicant uses data provided to calculate the maximum stay time for performance of a task which will not exceed Emergency Dose Limits.

A.4 Not Required.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: August 2010 Examination Level: RO SRO Operating Test Number: NRC Exam 1 Administrative Topic Tvne r

Describe activity to be performed (See Note) Code

  • A.1-1 Determine Values for Raising RWST Level.

Conduct of Operations M, R 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (41.10 /

43.5 / 45.2 I 45.6) 4.3/4.4.

A.1-2 Determine Protective Clothing for Electrical Arc Flash Protection and Pre-Job Briefing Requirements.

Conduct of Operations N, R 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

(41.10/ 45.12) 3.4/3.6.

. A.2 Determine a Technical Specification Completion Time Extension Equipment Control N, R 2.2.42 Ability to track Technical Specification limiting conditions for operations. (41.10 / 43.2 / 45.13) 3.1/4.6 A.3 Determine if Stay Times Exceed Emergency Exposure Limits.

Radiation Control M, R 2.3.4 Knowledge of radiation exposure limits under normal or

. emergency conditions. (41.12 / 43.4 / 45.10) 3.2/3.7.

A.4 Determine if conditions warrant a Follow-up Report or Upgrade based on changing conditions.

Emergency Procedures / Plan M, R 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. [2.5/3.3] (CFR: 41.10 / 43.5 / 45.11)

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 SRO Admin JPM Summary A.1-1 The applicant will perform the calculations necessary to determine the amount of primary water, and the amount of boric acid solution required to raise RWST volume by 3000 gallons while maintaining a 3100 ppm concentration, in the RWST.

A.1-2 The applicant determines the minimum protective clothing requirements for swapping a specific breaker in preparation for a test, and the pre-job briefing requirements per OPDP-1, Conduct of Operations.

A.2 The applicant evaluates the information presented and determines the LATEST date and time that Unit must be placed in Mode 4 based on the information presented.

A. 3 The applicant uses data provided to calculate the maximum stay time for performance of a task which will not exceed Emergency Dose Limits.

A.4 The applicant evaluates changes to plant conditions, determines that an upgrade from a Site Area Emergency to a General Emergency is required, prepares forms for emergency notification, and initiates Protective Action Recommendations.

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ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: August 2010 Exam Level: RO SRO-l SRO-U Operating Test Number: NRC Exam 1 EBolded JPMs are SRO-U.)

(Italicized JPM is RD only.)

Control Room Systems@ (8 forRO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System I JPM Title Type Code*

Function

a. Perform a Minor Dilution. A, M I 004 A Chemical and Volume Control_System_(4.07,_3.9/3.7).
b. Fill Cold Leg Accumulator #4. M, L 2 006_Emergency_Core Cooling_System_(A4.07,_4.4/4.4).
c. Perform ES-i .3 Transfer to Containment Sump. EN, M 3 Oil Large_Break_LOCA(EA1.li,_4.2/4.2).
d. Respond to IA RHR pump trip per AOI-14. D, L 4P 025 Loss of Residual Heat Removal_System_(AA1 .09,_3.2/3.1)
e. Respond to a PRT High Pressure alarm. A, M 5 007 Pressurizer Relief Tank/Quench Tank_(A4.i0,_3.6/3.8)
f. Shutdown of DG from Main Control Room. C or 5, A, EN, 6 064 Emergency Diesel Generators (A4.Oi, 4.0/4.3). M
g. Return Failed RCS Temperature Channel to Service. A, N 7 016 Non-Nuclear Instrumentation_System_(A4.01,_2.9/2.8).
h. Shutdown Instrument Room Purge. C or 5, N 8 029 Containment Purge System (A2.03, 2.7/3.2).

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

i. Bypassing 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, for local control. D, R 2 004 Chemical and Volume Control_System_(Ai.ii,_3.0/3.0).
j. Transfer 250v DC Turbine Building Distribution Board 1 from Normal to Alternate. D 6 063 DC Electrical Distribution_System_(K4.02._2.9/3.2).
k. Local Restart of C&SS Air Compressors. A, D, E 8 065 Loss of Instrument Air (AK3.08, 3.7/3.8).

@ All RD and S RD-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 RD / S RD-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrom bank <9 / <8 / <4 (E)mergency or abnormal in-plant 1 / 1 I 1 (EN)gineeredsafetyfeature - / - / ?1 (L)ow-Power / Shutdown > 1 I > 1 / > I (N)ew or (M)odified from bank including 1(A) > 2 I 2 / I (P)revious 2 exams < 3 < 3 1< 2 (randomly selected)

(R)CA >1 I >1 / >1 (S)imulator ES-30 I, Page 23 of 27 p -

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Control Roomlln-Plant System JPM Summary B.1 .a Applicant aligns the CVCS system to accomplish a minor dilution using SOl-62.02, Boron Concentration Control, Section 6.6, Minor Dilution. When the dilution is initiated, 1-FCV-62-128, MAKEUP TO VCT INLET, and 1-FCV-62-143, PW TO BLENDER, fail open. The operator enters AOl 3,Malfunction of Reactor Makeup Control, and terminates the dilution by stopping the primary water pumps.

B.1.b Applicant adds water to the cold leg accumulator with reactor coolant system pressure at approximately 1520 psig. The lower RCS pressure requires a different alignment to be established during the filling process.

B.1 .c Applicant aligns the ECCS systems to the Containment Sump. The applicant identifies the failure of 1-FCV-63-3, SI PMPS RECIRC HDR TO RWST to close and the failure of 1 -FCV-63-1 1, RHR PMP B TO SI PMPS SUCT to open, and takes required compensatory actions.

B.1 .d THIS JPM IS DESIGNATED AS THE RO ONLYJPM.

The applicant responds to the trip of IA-A RHR pump in accordance with A 01-14, Loss of RHR Shutdown Cooling, Section 3.5, RHR Pump IA-A Trip and places the lB-B RHF? pump in seivice.

B.1 .e The applicant uses ARI 88-C actions to reduce PRT pressure to 6.5 psig and then diagnoses the failure of PZR PORV 1-68-334 open, and terminates the depressurization by placing 1-HS-68-332A BLOCK VALVE FOR PORV 334 in the CLOSED position.

B.1 .f This JPM may be performed either in the Main Control Room or on the Simulator.

During a normal shutdown of the I B-B Diesel Generator from the Control Room, the applicant determines that an emergency stop of the diesel generator is required upon receipt of annunciator 203-D, CRANKCASE PRESS HI and performs an emergency stop of the I B-B Diesel Generator.

B.1 .g The applicant returns Loop 2 RCS Tavg and AT inputs to the rod control system, using AOI-2, Malfunction of Reactor Control System. When rods are returned to automatic, a continuous rod bank withdrawal occurs. The applicant initiates a manual reactor trip upon diagnosis of the continuous rod bank withdrawal.

8.1 .h This JPM may be performed either in the Main Control Room or on the Simulator.

The applicant shuts down the instrument room purge using SOl-30.02, Containment Purge System, Section 7.6, SHUTDOWN of Instrument Room Purge.

B.1.i The applicant performs the manual actions required to bypass PCV-62-81, LETDOWN PRESS CONTROL in accordance with SOl-62.01 Section 8.15.

B.1 .j The applicant completes the transfer of 250V DC Turbine Building Distribution Board #1 from its Normal to Alternate supply perSOl-239.O1, 250V Battery Board 1, Section 8.7.1, Transferfrom Normal to Alternate.

B.1 .k After a station blackout, the applicant aligns and restarts the A and B Air Compressors using AOl-I 0, Loss of Control Air. Recovery of the A Control and Station Air Compressor requires the reset of the high air temperature alarm, and hand loading of the compressor after restart.

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